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Home My WebLink About841148.tiff °`fPA AEG0<gr UNITED STATES W � NUCLEAR REGULATORY COMMISSION 'r..- 3 REGION IV / 611 RYAN PLAZA DRIVE, SUITE 1000 �T o�yo N°� ARLINGTON,TEXAS 76011 JUL 20184 0idL. � fU Docket: 50-267 � . JUL24 \r Mr. 0. R. Lee, Vice President Electric Production Public Service Company of Colorado P. 0. Box 840 Denver, Colorado 80201 Dear Mr. Lee: We have reviewed your June 15, 1984, response to our May 16, 1984, request for the details of your proposed tendon surveillance program. We find that your program requires considerably less surveillance than we believe should be performed. Because the degradation of the tendon assemblies is a serious condition which must be controlled to ensure the integrity of the prestressed concrete reactor vessel (PCRV), we recommend a surveillance program similar to that described in the enclosure. Therefore, we request that you review the program and propose it, or the equivalent, in a FSV Technical Specification change application within 30 days of the date of this letter. In addition, as our April 19, 1984, letter indicates, we are concerned about any corrosive atmosphere which may exist within the tendon tubes. The atmosphere within the tendon tubes must be controlled. Although your April 25, 1984, letter (P-84119) states that "design modifications may be warranted to minimize tendon corrosion," no mention of possible design modifications is made in your June 15, 1984, response. Therefore, please provide the details of the evaluations you have conducted of possible modifications within 30 days of the date of this letter. Further, we have not as yet received the results of metallurgical examinations of tendon wires removed during your inspection. Please include your schedule for providing this information with the design evaluation details discussed above. Since these reporting requirements relate solely to FSV, OMB clearance is not required under P. L. 96-511. If you have any questions on this matter please contact the NRC Project Manager, Philip C. Wagner at (817) 860-8127. Sincerely, ichard P. Denise, Director Division of Reactor Safety & Projects Enclosure: Proposed Technical Specification 841148 Public Service Company of Colorado 2 cc: C. K. Millen Chairman, Board of County Commissioners Senior Vice President of Weld County, Colorado Public Service Company Greeley, Colorado 80631 of Colorado P. 0. Box 840 Regional Representative Denver, Colorado 80201 Radiation Programs Environmental Protection Agency David Alberstein, 14/159A 1860 Lincoln Street GA Technologies, Inc. Denver, Colorado 80203 P. 0. Box 85608 San Diego, CA 92138 Don Warembourg Nuclear Production Manager Public Service Company of Colorado P. 0. Box 368 J. K. Fuller, Vice President Platteville, Colorado 80651 Public Service Company of Colorado Albert J. Hazle, Director P. 0. Box 840 Radiation Control Division Denver, Colorado 80201 Department of Health 4210 East 11th Avenue Denver, Colorado 80220 G. L. Plumlee NRC Senior Resident Inspector Kelly, Stansfield & O'Donnell P. 0. Box 640 Public Service Company Building Platteville, Colorado 80651 Room 900 550 15th Street Denver, Colorado 80202 Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Fort St. Vrain 01 Technical Specifications Amendment P Page 5.2-5 The intervals specified for testing the overpressure protection assemblies are adequate to demonstrate the operability of the overpressure protection systems. The intervals specified for testing the associated instrumentation and controls are adequate to assure reliability of rupture disc and safety valve operation and to monitor the integrity of the PCRV safety valve piping and containment tank. Specification SR 5.2.2 - Tendon Corrosion and Anchor Assemblies Surveillance The serviceability of the corrosion protection applied to and the condition of the prestressing tendons shall be monitored in accordance with paragraphs a) and b). Surveillance of the tendon assemblies shall be performed in accordance with paragraphs c) and d) . a) Corrosion protected wire samples of sufficient length (i.e. , initially at least 15 feet where practical ) , or half the tendon length, whichever is shorter) shall be inserted with selected tendons. Corrosion inspection of at least one of these wires shall be made at the end of the first and third calendar year after prestressing. Additional inspections shall be conducted at five calendar year intervals thereafter. Fort St. Vrain !i Technical Specifications Amendment # Page 5.2-6 An accelerated tendon wire sample program shall consist of removing at least one longitudinal and one bottom cross head, top cross head or circumferential wire samples for inspection at least once per 18 months. b) A sample of the atmosphere contained in at least one longitudinal , circumferential , bottom cross head and top cross head tendon tubes shall be drawn and analyzed for products of corrosion, in coordination with and at the same time intervals as for paragraph a) above. c) A visual examination of at least 5% of the prestressing anchor assemblies for the top cross head tendons and the r circumferential tendons shall be performed at least once per 18 months. A visual examination of at least 33% of the prestressing anchor assemblies for the longitudinal tendons and the bottom cross head tendons shall be performed at least once per 18 months. One tendon from each of the above four groups may be kept unchanged, the remaining tendons shall be selected on a random but representative basis so that the entire population of tendons within the group are examined. The visual examinations of the prestressing anchor assemblies shall include examination of assembly hardware ._. . . .__ . . Fort St. Vrain #1 Technical Specifications Amendment # Page 5.2-6a (such as bearing plates, stressing washers, shims and buttonheads) and the surrounding concrete. The method used to remove the corrosion protection grease to permit visual examination of the hardware shall neither increase the effects of corrosion nor damage the steel . d) A liftoff test shall be performed on at least 5% of the top crosshead, 5% of the circumferential , 15% of the longitudinal and 15% of the bottom crosshead tendons at least once per 18 months. One tendon from each group may be kept unchanged, the remaining tendons shall be selected on a random but representative basis so that the entire population of tendons within the groups are examined. e) In addition to any other reports which may be required, a special report describing the results of the tendon examinations performed during the reporting period shall be submitted to the NRC every 18 months. Basis for Specification SR 5.2.2 The corrosion protection provided for the PCRV prestressing components is considered to be more than adequate to assure that the required prestressing forces are sustained throughout the operational life of the plant. The details of the corrosion protection system are described in Section 5.6.2.5 of the FSAR. Sampling tendon tube atmosphere for products will provide a secondary check on the adequacy of the corrosion pro- tection provided for the stressing tendons. Fort St. Vrain #1 Technical Specifications Amendment # Page 5.2-7 IVisual and liftoff examinations of tendon assemblies will provide additional assurance that the prestressing system has not degraded by checking the corrosion protection and integrity of the anchor assemblies and tendon wires. Specification SR 5.2.3 - Tendon Load Cell Surveillance a) Checks on the possible shift in the load cell reference points for representative load cells shall be performed at the end of the first calendar year after initial prestressing and within 120 days prior to initial power operation. Additional checks shall be conducted at five calendar year intervals thereafter. b) The load cell alarm circuit between the Data Acquisition System Room and the Control Room shall be functionally tested annually to assure that the operator in the Control Room is alerted when tendon load settings are exceeded. SR 5.2.3.b shall be implemented per ISI Criterion A. Basis for Specification SR 5.2.3 The PCRV tendons apply the force required to counteract the internal pressure. Therefore, they are the PCRV structural components most capable of being directly monitored and of indicating the capability of the vessel to resist internal pressures. Since the relation between UNITED SLATES .r. � NUCLEAR REGULATORY CO:.7.;I;SION ‘k„ - I REGION IV k-�''I'I```I' " 611 RYAN PLAZA DRIVE. SUITE 1000 Rio a° ARLINGTON. TEXAS 76011 • • es Docket: 50-267 JUL 18 ES4 nth ttmily� pm. • oECErJ s 84 fi Mr. 0. R. Lee, Vice President JUL 4 �� Electric Production Public Service Company of Colorado r•REELEr, COLD, P.O. Box 840 Denver, Colorado 80201 Dear Mr. Lee: Your June 22, 7984, response on the applicability of fire protection requirements for the Fort St. Vrain Station (FSV) contains a number of items which require clarification. Our main concern is your proposed schedule for reaching compliance with the regulations. As we understand your schedule, you will require another year to complete your evaluations, in addition to any time we may require to respond to your various partial submittals. We feel that an additional year to evaluate the need for modifications is unwarranted and that the evaluations should be completed within the next 6 months. This is especially important in light of the fact that these evaluations were required to be completed more than 3 years ago. In order to aide you in expediting your review, we recommended that interim information be provided to NRC for review; it was never our intent that your efforts be held in abeyance while awaiting our input. We continue to encourage interim submittals and recognize that some effort may be inefficiently utilized if a disagreement develops on proper evaluation methods , but we cannot allow the completion of this evaluation to linger. In addition, we remain willing to meet with members of your staff for frequent, informal working sessions to further expedite your-evaluations. These meetings can be arranged through the Project Manager and can be held at our offices, your facility, or our Headquarters offices, depending on the nature of the specifics to be discussed. Please provide a schedule within 30 days of the date of this letter which will ensure completion of your evaluations within a 6-month period. We also have the following specific comments on Attachment 2 to your letter: 1. The second sentence under "Applicability" should be deleted since it incorrectly infers that all existing and newly constructed plant areas are, and/or would be, acceptable per BTP 9. 5-1. This is not in accordance with the requirements of 10 CFR 50.48. 2. The "Background" section is unnecessary and misleading and should be deleted. 3. In Section III.A. , the term "congested cable areas" must be clearly defined as provided in our earlier guidance. Mr. 0. R. Lee -2- 4. In Section III. B. , a definition of what is meant by "no fuel damage" and a statement that no unmonitored radiological releases will occur is needed. 5. A definite schedule is required for converting the G and J wall sprinkler systems to automatic in Section IV.A. 6. In Section IV. D. , the main turbine generator is considered an off-site power source; this should be explained. 7. In Section IV. I. , only those pipes and valves which are water-filled can be considered undamaged by a fire. 8. The discussion in Section IV.J. is confusing and should be deleted. If a criteria other than that contained in Appendix R is being proposed, a clear discussion of the differences is required in an exemption request. 9. Section V is misleading and should be deleted. The regulations (10 CFR 50. 12) provide the criteria for requesting exemptions. When the above concerns/comments are resolved and incorporated into Attachment 2, we would accept it as fulfilling the guidance for ensuring compliance with Section III.G. 3. of Appendix R. We request that this effort be completed within 30 days of the date of this letter. If you have any questions on this subject, please contact the Project Manager, P. Wagner, at (817) 860-8127. Since this reporting requirement relates solely to FSV, OMB clearance is not required under P. L. 96-511. Sincerely, t • 4. AtL.w... ._ Eric H. Johnson, Chief Reactor Project Branch 1 cc: C. K. Millen Chairman, Board of County Commissioners Senior Vice President of Weld County, Colorado Public Service Company Greeley, Colorado 80631 of Colorado P. 0. Box 840 Regional Representative Denver, Colorado 80201 Radiation Programs Environmental Protection Agency 1860 Lincoln Street Denver, Colorado 80203 Mr. 0. R. Lee -3- David Alberstein, 14/159A Don Warembourg GA Technologies , Inc. Nuclear Production Manager San Diego, CA 92138 Public Service Company of Colorado P. 0. Box 368 J. K. Fuller, Vice President Platteville, Colorado 80651 Public Service Company of Colorado Albert J. Hazle, Director Radiation Control Division Radiation Control Division P. 0. Box 840 Department of Health Denver, Colorado 80201 42.10 East 11th Avenue Denver, Colorado 80220 G. L. Plumlee NRC Senior Resident Inspector Kelly, Stansfield & O' Donnell P. O. Box 640 Public Service Company Building Platteville, Colorado 80651 Room 900 550 15th Street Denver, Colorado 80202 Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 cojoi REG4<S UNITED STATES W� ' NUCLEAR REGULATORY COMMISSION n m 3 REGION IV F � 611 RYAN PLAZA DRIVE. SUITE 1000 'Po - �° ARLINGTON,TEXAS 76911 w...• VEC® It JUL 1 7 1984 0 �1�Oakes pyf�s Docket: 50-267 �l I tiflL 2 g I K&4 ,..gc&teL Public Service Company of Colorado `• QQ ATTN: 0. R. Lee, Vice President Electric Production P.O. Box 840 Denver, Colorado 80201 Dear Mr. Lee: In response to your June 1, 1984, request, we are herein returning the copy of the 1983 INPO Evaluation Report of the Fort St. Vrain Station. This report was provided for our internal use by your letter dated January 19, 1984. We appreciate the opportunity to have reviewed this report, compare the INPO findings to those we have made, and note the similarities. Sincerely, lOtikte e. 04, Philip C. Wagner, Senior Project Manager, Reactor Projects Branch 1 Enclosure: 1983 INPO Report Public Service Company of Colorado -2- cc: w/o Enclosure C. K. Millen Chairman, Board of County Commissioners Senior Vice President of Weld County, Colorado Public Service Company Greeley, Colorado 80631 of Colorado P. 0. Box 840 Regional Representative Denver, Colorado 80201 Radiation Programs Environmental Protection Agency David Alberstein, 14/159A 1860 Lincoln Street GA Technologies, Inc. Denver, Colorado 80203 P. 0. Box 85608 San Diego, CA 92138 Don Warembourg Nuclear Production Manager Public Service Company of Colorado P. 0. Box 368 J. K. Fuller, Vice President Platteville, Colorado 80651 Public Service Company of Colorado Albert J. Hazle, Director P. 0. Box 840 Radiation Control Division Denver, Colorado 80201 Department of Health 4210 East 11th Avenue Denver, Colorado 80220 G. L. Plumlee NRC Senior Resident Inspector Kelly, Stansfield & O'Donnell P. 0. Box 640 Public Service Company Building Platteville, Colorado 80651 Room 900 550 15th Street Denver, Colorado 80202 Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 D. W. Warembourg, Nuclear Production Manager Fort St. Vrain Nuclear Station P.O. Box 368 Platteville, Colorado 80651 J. Gahm, Quality Assurance Manager (same address) Hello