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Home My WebLink About851155.tiff rJoe"""`°uty� UNITED STATES NUCLEAR REGULATORY COMMISSION I ° : � „ REGION IV or �yy 611 RYAN PLAZA DRIVE, SUITE 1000 to a ARLINGTON,TEXAS 76011 ***lc. MAY 0 1985 kr/I L7. ` r1""v In Reply Refer To: �� , '%iM, Docket: 50-267 if. "70 ` -7.S Iy 4� Public Service Company of Colorado • „i ATTN: 0. R. Lee, Vice President � 4 ' % Electric Production P. 0. Box 840 Denver, Colorado 80201 Dear Mr. Lee: This is to confirm arrangements made with Mr. M. Holmes of your staff during telephone conversations on May 8, 1985, for a meeting between Public Service Company and NRC personnel on May 16, 1985. The meeting will be conducted in your Denver, Colorado, office. The meeting was requested by the NRC to ensure the proper understanding of the design and operation of the Fort St. Vrain electrical systems. Our review of the material you have provided has resulted in some concerns which, if valid, will require some corrective action. Therefore, we requested a meeting on short notice to confirm the actual design aspects so that we can complete our review. Should you have questions on this subject, please contact the NRC Project Manager. Sincerely, E. H. Johnson, Chief Reactor Project Branch 1 cc: Mr. D. W. Warembourg, Manager Nuclear Engineering Division Public Service Company of Colorado P. 0. Box 840 Denver, Colorado 80201 (cont. on next page) 851155 Public Service Company of Colorado -2- Mr. David Alberstein, 14/159A GA Technologies, Inc. P. 0. Box 85608 San Diego, California 92138 Kelley, Stansfield & O'Donnell Public Service Company Building 550 15th Street, Room 900 Denver, Colorado 80202 Chairman, Board of County Comm. of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1860 Lincoln Street Denver, Colorado 80203 Mr. H. L. Brey, Manager Nuclear Licensing/Fuels Div. Public Service Company of Colorado P. 0. Box 840 Denver, Colorado 80201 J. W. Gahm, Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 19} Platteville, Colorado 80651 L. Singleton, Manager, Quality Assurance Division (same address) Colorado State Department Health SSINS No. 6835 IN 84-52, SUPPLEMENT 1 UNITED STATES 1 '� "'-"Y ..... °`t NUCLEAR REGULATORY COMMISSION Lr' OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 7( ,;' ill MAY 1 31985 May 8, 1985 J . GREELEY. COLO. IE INFORMATION NOTICE NO. 84-52, SUPPLEMENT 1: INADEQUATE MATERIAL PROCUREMENT CONTROLS ON THE PART OF LICENSEES AND VENDORS Addressees: All nuclear power reactor facilities holding an operating license (OL) or construction permit (CP). Purpose: This notice provides additional information to licensees of hardware problems and deficient procurement controls and quality assurance (QA) practices on the part of suppliers of nuclear material that have been inspected by the IE Vendor Program Branch (VPB) since IE IN 84-52 was issued. It also is intended to call attention to generic problems in procurement activities on the part of licensees. No specific action is required in response to this information notice, but it is expected that recipients will review the information presented for applicability to their facilities. Discussion: Information Notice 84-52 described deficient procurement controls and QA practices identified during inspections performed by the VPB from 1982 to early 1984. Since that time, 13 additional inspections have been performed of material suppliers and material manufacturers. Deficiencies similar to those noted in IN 84-52 were found for all 13 vendors. Those deficiencies are described in Attachment 1. In addition to procurement and QA deficiencies, hardware deficiencies were noted for three of these vendors. IN 85-15, was issued on February 22, 1985, to specifically address the hardware deficiencies identified at one of the three vendors, Interstate Steel and Supply Company. The hardware deficiencies identi- fied at the other two vendors, Phoenix Steel Corporation, Tube Division, and LTV Steel Company (formerly Jones and Laughlin Steel), Tubular Division, Campbell Plant, are discussed in this notice. The hardware deficiencies identified involved the production and shipment of seamless carbon steel pipe, portions of which did not meet the required minimum wall thickness because of inadequate manufacturing process controls and inadequate inspection methods. An NRC inspection of seamless pipe supplied by the two companies was recently performed at a nuclear power plant in which 20% of the LTV pipe and 40% of the Phoenix pipe inspected did not meet the minimum wall thickness requirements 8505060418 m tq S 15-g5 IN 84-52, Supplement 1 May 8, 1985 Page 2 of 3 specified by the ASME Code. The worst case found during the inspection was a pipe which was 5. 3% below the required minimum wall thickness along a portion of its length. However, because of the inadequate manufacturing process control and inadequate inspection methods by the two vendors, this cannot be assumed to be a limiting worst case. With the exception of the hardware deficiencies identified above, the issues listed in Attachment 1 are representative of findings made by the Vendor Program Branch during other inspections of quality programs and of the implementation of quality programs in the material supply and manufacturing industry. The number and nature of the findings suggest that significant problems may exist in the implementation of the nuclear industry' s vendor evaluation and surveillance programs. The NRC' s position is that the ultimate responsibility for the adequacy of these programs rests with the licensees. A contributing factor to the overall problem discussed above has been deficiencies identified with respect to licensee procure- ment and associated QA activities. Deficiencies of this type include: a. inadequate inspection of materials and components when received b. inadequate survey and auditing of vendor QA programs c. failure to perform adequate internal audits of the procurement process d. inadequate training of personnel who procure nuclear materials under the requirements of 10 CFR 21, Appendix B to 10 CFR 50, and the ASME Code e. insufficient management attention to procurement activities Attachment 1 lists vendors and recent VPB inspection reports where specific discrepancies have been identified regarding implementation of the vendors' quality assurance programs. These reports are published quarterly by the NRC in the "Licensee Contractor and Vendor Inspection Status Report," NUREG- 0040. Copies of this document (the White Book) may be obtained at a nominal cost from the National Technical Information Service, Springfield, Virginia 22161. Correspondence with contractors and vendors relative to the inspection data contained in NUREG-0040 is placed in the NRC Public Document Room, 1717 H Street, N.W. , Washington, D.C. 20555. All of the vendors listed in Attachment 1 have submitted corrective action plans addressing the noted deficiencies. IN a4-52, Supplement 1 May 8, 1985 Page 3 of 3 No specific action or written response is required by this information notice. If you have any questions regarding this notice, please contact the Regional Administrator of the appropriate NRC regional office or the technical contact listed below. OLaG dward . Jordan, Director Divisi n of Emergency Preparedness andEngineering Response Office of Inspection and Enforcement Technical Contact: E. Baker, IE (301) 492-4874 Attachments: 1. Deficient Practices Identified in Recent VPB Inspections 2. 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C m 5 a a r � 4-) CC C •C w o E U1 ,-1 ,i .1 � � L0 00000 r I LC) UDR Cr Cr Cr vv it CC N Z N00 CO CO CO y R ro \\\\\ CC H F_d Cr) LO Cr CV 01 CF. 1.0 O1O11n 0000 O00 O O O O O O O1 O1OO11O1O1O1 O1 O1 O1 O1 O1 O1 O1 O1 O1 O1 O . U O U a >v•-• . a a o = nU ) • o C -o 4- (0 C ro a) nwe U OL Nv C }a a N N U) • N O 0 re U L r C rwa rd ota) 4a +W. C C C7 =CO] fCi00O w V L O U Ol L C) C N N t 7 g5 C SS. AttacTAhent 2 IN 84-52, Supplement 1 May 8, 1985 LIST OF RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to 85-35 Failure Of Air Check Valves 4/30/85 To Seat All power reactor facilities holding an OL or CP 85-34 Heat Tracing Contributes To 4/30/85 All t Corrosion Failure Of Stainless reactor Steel Piping facilities l holding an OL or CP 84-84 Deficiencies In Ferro- 4/24/85 Rev. 1 Resonant Transformers fal power reactor facilities holding an OL or CP 85-33 Undersized Nozzle-To-Shell 4/22/85 Welded Joints In Tanks And All power reactor Heat Exchangers Constructed an OLLio facilities ci eC holding r Under The Rules Of The ASME or CP Boiler And Pressure Vessel Code 85-32 Recent Engine Failures Of 4/22/85 All Emergency Diesel Generators power reactor e faal cilities holding an OL or CP 85-31 Buildup Of Enriched Uranium 4/19/85 All uranium fuel In Ventilation Ducts And fabrication licensees Associated Effluent Treatment Systems 85-30 Microbiologically Induced 4/19/85 Corrosion Of Containemnt All power reactor Service Water System an OL facilities c L or oreC holding CP 85-29 Use Of Unqualified Sources 4/12/85 All well logging In Well Logging Applications source licensees 85-03 Separation Of Primary Reactor 4/9/85 Sup. 1 Coolant Pump Shaft And All power reactor Impellerfacilities holding an OL or CP 85-28 Partial Loss Of AC Power And 4/9/85 All power reactor l Diesel Generator Degradationfacilities holding an OL or CP OL = Operating License CP = Construction Permit �—g5 coltnaoi4• UNITED STATES O . "� NUCLEAR REGULATORY COMMISSION o I I S REGION IV OY. d qq 611 RYAN PLAZA DRIVE. SUITE 1000 r •0 ARLINGTON.TEXAS 78011 MIT 0 } a , In Reply Refer To: j, i {a u Docket: 50-267 3 ite„, eon Public Service Company of Colorado ATTN: 0. R. Lee, Vice President Electric Production P. O. Box 840 Denver, Colorado 80201 Dear Mr. Lee: We have completed a preliminary review of your November 4, 1983, response to Generic Letter 83-28, "Required Actions Based on Generic Implications of Salem ATWS Events," dated July 8, 1983. This review indicates that some of the responses are incomplete and that additional information is required to complete the review. A list of the incomplete responses, with a brief description of the deficiency, is given in the enclosure to this letter. We request that you review the enclosure and provide a response within 30 days of your receipt of this letter. We note that various Owner's Groups, INPO and NSSS Vendors have been or are producing generic responses to some of the Generic Letter 83-28 items which may be useful in meeting the requirements contained therein. If you have any questions on this subject, please contact the NRC Project Manager. Sincerely, E. H. Johnson, Chief Reactor Project Branch 1 Enclosure: Request for Information cc: Mr. D. W. Warembourg, Manager Nuclear Engineering Division Public Service Company of Colorado P. 0. Box 840 Denver, Colorado 80201 (cont. on next page) Public Service Company of Colorado -2- Mr. David Alberstein, 14/159A GA Technologies, Inc. P. 0. Box 85608 San Diego, California 92138 Kelley, Stansfield & O'Donnell Public Service Company Building 550 15th Street, Room 900 Denver, Colorado 80202 Chairman, Board of County Comm. of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1860 Lincoln Street Denver, Colorado 80203 Mr. H. L. Brey, Manager Nuclear Licensing/Fuels Div. Public Service Company of Colorado P. 0. Box 840 Denver, Colorado 80201 J. W. Gahm, Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 19} Platteville, Colorado 80651 L. Singleton, Manager, Quality Assurance Division (same address) Colorado State Department Health Enclosure Request for Information Fort St. Vrain Response to Generic Letter 83-28 Item 2.1 (first part) - Incomplete Licensee's response does not indicate that all RTS components will be identified as safety-related in the established procedures for maintenance test and other work orders. These procedures are required to include such identification, therefore, the licensee shall modify all such procedures to incorporate identification of the RTS components as safety-related. Item 2.1 (second part) - Incomplete Licensee needs to describe their program for maintaining contact with suppliers of safety-related equipment other than the NSSS for the purpose of ensuring that vendor technical information is kept complete, current and controlled during the life of the plant. The response should indicate how this information is incorporated into revisions and updates of operating, maintenance, and test procedures. Item 2.2.2 - Incomplete Licensee needs to present their evaluation of the NUTAC program and describe how it will be implemented at Fort St. Vrain. The staff found the NUTAC program fails to address the concern about establishing and maintaining an interface between all vendors of safety-related equipment and the utility. Accordingly, the licensee will need to supplement his response to address this concern. This additional information should describe how current procedures will be modified and new ones initiated to meet each element of the Item 2.2.2 concern. Item 3.1.3 - Incomplete Licensee needs to state if they have identified any post maintenance testing requirements in Technical Specifications that may degrade rather than enhance safety. Any changes to such test requirements shall be submitted for staff approval . Item 3.2.3 - Incomplete Licensee needs to submit the same type of information for all other safety-related components that was required in Item 3.1.3 for RTS components. -2- Item 4.5.3 - Incomplete Licensee needs to submit the results of their review of existing on-line testing intervals to determine that those intervals are consistent with achieving high RTS availability when considering the five items listed in Generic Letter 83-28, Item 4.5.3. Jc,,t' new UNITED STATES •O !\ -'t. NUCLEAR REGULATORY COMMISSION ti l ;. REGION IV ? q; 611 RYAN PLAZA DRIVE. SUITE 1000 T. nay ` �14"O 0 ARLINGTON.TEXAS 70011Jtnitte 12;1 MAY 0 7 1985 MAY1 In Reply Refer To: 3 pgas Docket: 50-267 GH`cFLFY, OocO. Public Service Company of Colorado • ATTN: 0. R. Lee, Vice President Electric Production P. 0. Box 840 Denver, Colorado 80201 Dear Mr. Lee: On April 3, 1985, members of your staff met with members of the NRC's Region IV and NRR staffs in Bethesda, Maryland, to discuss the equipment qualification issues for the Fort St. Vrain facility (FSV). One of the key issues discussed at this meeting was the capability of an operator to terminate certain steam pipe rupture events within 4 minutes. The justification for this response time is contained in your March 28, 1985, response to our January 28, 1985, request for additional information. It is our understanding that, if certain steam pipe ruptures are not terminated within the 4 minutes, the qualification criteria for some electrical equipment may be exceeded. The staff's position on the operator response time is contained in the enclosure to this letter. The additional issues of aging and operability times were also discussed and are included in the list of positions contained in the enclosure. We request that you respond to the positions/concerns contained in the enclosure within 30 days of your receipt of this letter. Since this reporting requirement relates solely to FSV, OMB clearance is not required under PL 96-511. If you have any questions on this subject, please contact the Project Manager. Sincerely, E. H. Johnson, Chief Reactor Project Branch 1 Enclosure: As stated cc: (cont. on next page) Public Service Company of Colorado -2- Mr. D. W. Warembourg, Manager Nuclear Engineering Division Public Service Company of Colorado P. 0. Box 840 Denver, Colorado 80201 Mr. David Alberstein, 14/159A GA Technologies, Inc. P. 0. Box 85608 San Diego, California 92138 Kelley, Stansfield & O'Donnell Public Service Company Building 550 15th Street, Room 900 Denver, Colorado 80202 Chairman, Board of County Comm. of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1860 Lincoln Street Denver, Colorado 80203 Mr. H. L. Brey, Manager Nuclear Licensing/Fuels Div. Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 J. W. Gahm, Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 19} Platteville, Colorado 80651 L. Singleton, Manager, Quality Assurance Division (same address) • Colorado State Department of Health Enclosure NRC Staff Positions on Equipment Qualification at FSV Following a Meeting on April 3, 1985 1. The licensee has not adequately demonstrated the ability of the operators to respond as required. The staff stated that.the licensee would have to demonstrate (through simulation or historical data) that the operators could respond correctly to these events in the required time, when presented with a wide variety of accident situations. Any such validation would have to be conducted under as close to actual operative conditions as possible, and include cognitive as well as the operative response times that were provided in the licensee's submittal of March 28, 1985. In the absence of such demonstrated performance, the staff could only accept operator action starting at 10 minutes, with 1 minute for each subsequent action, which is based on current industry-validated information. 2. The staff also noted that the licensee has not fully evaluated alternative approaches to this problem. The staff concludes that the licensee should make a full evaluation of the systems required to fully automate the isolation of all steam rupture within the time required to assure continued equipment operability. 3. The staff recommends that PSC expedite the evaluation of aging effects for the affected equipment, which is presently underway. 4. Operability times need to be established in order to determine the necessary qualification conditions. Hello