ML20247E230

Forwards Rev 7 to Updated FSAR for Fort St Vrain Unit 1

ML20247E230
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/21/1989
From:	Crawford A PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247E233	List: ML20247E230
References
P-89271, NUDOCS 8907260120
Download: ML20247E230 (23)

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' P.O. Box 840 ' Denvar CO B0201- 0340 f' A. Clegg Crawford Vice President l Nuclear Ope ations j July 21, 1989 F rt St. Vrain i C Unit No. 1 P 89271 U. S. Nuclear Regulatory Commission 1 ATTN:. Document (9ntrol Desk l Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Fort St. Vrain Updated FSAR, Revision 7 Gentlemen: Encloied is one (1) signed original and ten (10) additional copies of Revision 7 to the Updated Final Safety Analysis Report (Updated FSAR) .i for Fort St. Vrain (FSV) which h u been prepared and is being submitted in'accordance with 10CFR50, Section 50.71'(e); 'This revision inclu6es the effects of changes made to the facility and piocedures as described in the Updated FSAR; safety evaluations performed by PSC, either in support of licerse amendments or in support 'of. conclusions that changes did not involve en unreviewed safety question;.and analys6s of new safety issues performed by Or on behalf of PSt. at Cormnission request. -l Brief descriptions of the principal changes or additions to affected sections and appepriice of the Updated FSAR, Revision 7, are included in the attachment. 16CFR50.71(e)(2)(ii)requiresthatthissubm5ttal identify changes niade under the provisions of 10CFRED.59 but not previousTy submitted to tie Commission. All changes reflected in Revision 7 ef the Updated FSAR, that were made under the provisions of 20CFR50.59, are identified in the 1989 10CfR50.59 annual report (Reference 1) or previnus 10CFR50.69 annual reports. NRC Generic Letter 86-10 (Reference 2) states that c licensee may include the Fire Protection Prograa Plan (FPPP) itt the Updated FSAR upon approval by the NRC. The NRC has issued a Safety Evaluation kN i Report (Reference 3) approving FSV's FPPF. Therefore, in accordante r with Reference 1, the FPPP has been incorporated into the FSAR by refersnce in FSAR Section 9.12. U 89 7260120.e90721 l PDR ADOCK 0500026_< K FDC u_= t - _.

P-89271 o Page 2 Jely 21, 1989 . Section 11.1 has been updated based ofi the cr;nnitment in Reference 4. This revision is based on the core support flaor leakage rate. The IJ Craining Program in Section 12.2 has been revised based on Reference 5. Appesdix B has been revised based <m Rsferences 6, 7, and 8 to reflect FSV's record storage. If you have any questions or comments, please r.ontact Mr. M. H. Holmes at {303) 480-0950. Very truly yours, l d4AH p A. Clegg Crawford j Vice President i Nuclear Operations ACC/BRD:emm Attcchment Enclosure cc: Regional Administrator, Regioc l'? Attention: Mr. T..F. Westerman, Chief Projects Section B (with one copy of Revision 7 to the Updated FSAR) s Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain (with one copy of Revision 7 to the Upcated FSAR) 1 2 ) r l

e-- ~ P-89273 1 e

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July 21, 1989 1 i ,.i '. Keferences for P-89271 l I i 1.. PSC 1.etter Brey to NRC, dated July 2h 1989 (P-89255) l 2. NRC GeneHe Letter 86-10, dated April 24, 1986 (G-86227) 3. NRC Letter Heitner to Williams, dated May 18, 1989 (G-891BS) 4. PSC Letter Williams to NRC, iated October 20,1988(P-88312) 5. PSC Letter Williams to R C, dated April 21,1989'(P-89107) 6. NRC Letter Heitner to Wi'lliams, dated September 2,1988 (G-88370) 7. PSC Letter Williams to NRC, dated November 4, 1988 (P-88396) 8. LRC Letter Callan to Williams, dated Febrgary 15,1989 (G-89058) = - _ - __.- _ - _

~ r l UNITED STATES OF AMERICA { NUCLEAR REGULATORY COMMISSION In the Matter ) 1 ) { Public Service Cottpany of Colorado Docket No. 50-267 [ Fort St-Vra'ir, Unit No. 1 l AFFIDAVIT l l A. Clegg Crawford, being first duly sworn, deposes and says: 4 That he is Vice President, Nuclear Operations, of Pub 1<ic Sen ice Company cf Colorado, the L.icensee ~ herein, that he has read the information presented in the attached letter and knows the contents thereof, and that the statements and matters set forth therein bre true and correct to the best of his knowledge, information and belief. / &btf A. Clegg Crawford Vice President Nuclear Operetions STATE OF COLORADO ) ) COUNTY OF DENVER ) t Subscribe and sworn to before me, a Notary Public on this 21st day of July , 19 89 k ilh a Onww Notary Public My conunission expires January 6 _, 19_93, L__-___-__

n i P-89271 - Attach.nent July 2), 1989 Page 1 of 5 l Description of Principal Changes l Incorporated in Revision 7 of l the Updated FSAR Section 1 Referred to a hilC' Safety Evaluation on modifications made to safety ~ related systems and equipment in Building 30. Added a discussiott of the seismic qualifications of Building 10 and the n1b thru structure. Updated text, figures end tables related to the reanalysas of the 10CFR50.43 EG equipment qualificati;m prnfiles and tha inclusion of a Fixed High Teinperature SLRDIS 1 rip. Section 2 Revised figure to show. location of a new natural gas well. Added I d figures to show the elevation discharge curves for the flood hazards which could occur by the S. Platte River. Section 3 1 Changed the time the orifice valve can withstand the maximum 1 temperature e>perienced from a 30 minute 10FC to a 90 minute 10FC. Added a discussion on the design differences for the replacement . control rods used in the 1989 replacement. Provided clarification of a primary coolant bypass flowpath around the Control Roo Drive and Orificing Assembly (CRD0A). Added a discussion of helium purge flow j cooling for the CRDOA. Added a section to discuss the reliability of j the control rod drive rod position indication instrumentation. l l Section 4 l Added a clarification that using condensate reduces the potential for cavitation due to its lower temperature compared to fecdd ter. Added i discussions on monitoring circulator shaft assembly wobble and selected circulator auxiliaries for trending circulator performance. A6ded a discussion on the addition and operation of a third turbine water removai nump (Pump JC). Added an additional discussion on the circulator s team / water drain control scheme. Updated Plant Protective System (PPS) setpoints based on Amen iment 60 to. the Facility Operating License. Added a discussion on aiding moisture removal from the PCRV under atmospheric pressure conditions during non-power operation by admitting stear to the reheater section. Clarified that auto-start of the water turbine drive is a PPS function. l 1

.p i v P-89271 -Attachment ' July 21, 1989-o Page 2 of 5-Section 5 ) Claritied contr31 systcm functions upon a circulator tri). Added 'i discussions on the ~s1gniticance of the. minimum permissible trip. 'j setpaints of the steam generator and helium circulator penetration j interspace overpressure relief rupture discs and relief valves as ' documented in Amendment 60 to the Facility Operating License. Mded a discussion on core support floor cooling with leaking liner cooling tubes'and the limits on is01ating those leaking tubes, p 'Section 6 Provided a clarification on the HEPA filter elements in the reactor building exhaust regarding manufacturing conformance and added the HEPA filter unit rating of 19,000 cfm. Revised referenced PPS-instrumentation 'setpoints as a result of Amendment 60 to the Facility Operating License. Corrected applicable date of ANSI B31.7 to 1968 (draft). Added a' discussion on the significance of the-minimum permissible trip retpoint of the PCRV overpressure relief rupture discs and relief valves. Section 7 Corrected the listing of the reserve shutdown system as part of the PPS. Added a discussion that the automatic start of the water turbine drive it a PPS function. Added a new section and a table addressir.g the PPS trip setpoint reevaluation methodology and a new section discussing those parameters which required nett accident analyses. Revised all applicable ttbles (some reformatted), figures and text relative to the new PPS setpoint reevaluations as approved in Amendment 60 'to the Facility Operating License. Added a discussion that the use of an external test signal calibrated to a traceable NBS standard may be used in lieu of an internal generated test signal during surveillan:e testing as approved in Amendment 58 to the Facility ' Operating License. Revised accident environment parameters as a result of the reanalyses of the 10CFR50.49 equipment qualification profiles. Clarified discussion of those accide.nts evaluated for determining i neutron flux detector decalibration factors. Added a discussion on the time allowed to reset the neutron flux trip setpoints for control rod runbacks or power reduction events as approved in Amendment 66 to the Facility Operating License. Added a discussion on the requirements for covering all process and moisture instrument penetrations. Revised SLRDIS text and applicable tables and figures to include the addition of a fixed high temperature trip as a result i a.--.-

P-89271 -l Attachment i July 21, 1989 I Page 3 of 5 of the 10CFR50.49 reanalyses and Amendment 68 to 'the Facility J . Operating License. i Added a discussion on the addition of a single dedicated CRT located -in the Control Room to aid the operators during transient and 1 accident conditions following e scram. Section 8 Added

a. discussior,on the electrical system disturbance encountered on April 2 and 3,1986 as a result of a severe snowstorm.

Added a discussion or..the station batteries' configuration during a W.cery I charge. -Provided clarification that the loads supplied by the standby diesel generators are for an orderly reactor shutdown. Provided a di'cussion on the requirement to manually shed selected DC s loads at specified times from the station batteries to ensure a 4 hour service discharge. S_ection 9 LAdded a discussion on the fuel shipping casks licensing provisions, terms and conditions for their configuration and quality assurance . controls. Added a discussion on the pialocks used to secure the reactor building crane. Deleted text that ' stated that radioactive impurities could not enter the Re1ium Storage System. Provided clarification on filling the P[RV with helium from the helium trailers. Added a discussion en isolating cooling tubes in the core support floor sidewall. Added the reactor shutdown requirement for loss of hydraulic pressure in one hydraulic loop. Tievised the Fire Protection rection to reference the NRC approved Fire Protection Program Plan as a single source containing all the fire protection coramitments. Section 10 Added discussions ste. ting that other chemicals besides hydrazine can be used to further remove oxygen. Revised the backup auxiliary boiler flow rating. Added a discussion on the adequacy of the condensate cooldown from 63.2% reactor power in the event of a loss of outside electric power and turbine trip.

P-89271' j L Attachment July 21, 1989 Page'4'of 5 { l Section 11 l l Added a discussion on bypassing of the feitad metal-filter for core I support floor vent filter F6302 due to flow restrictions. Revised. the discussion on tbc core support floor leakage rate in reaching 10CFR20 MPC limits. Section 12 incorporated thiclear Operations organizational chances. Added a discussior P ceceiving.INP0 accreditation of operator training programs. Op' lated list of-Level O procedures. .Provided clarification, un the FSV RERP organization responsibilities. Updated PORC/NFSC membership lists.as a result of the Nuclear Operations' reorganization. Section 14 Provided clarification on heliam flow rates achiavable during cooling with one water-turbine driven circulator on unboosted condensatt and on boosted fire water. Added a discussion and applicable figures on additional analyses performed to evaluate closed loop shutdown cooling with condensate, using the EES section cof one steam generator, one water-turbine driven circulator and the service water cooled Decay Heat Removal Exchanger following a 40 minute 10FC from 83.2% reactor power. Revised PPS setpoints and accident discussions, analysis and figuras based on Amendment 60 to the Facility Operating License. Added a discussion on redundancy requirements for equipment to mitigate DBA-2. Provided a clarification that the helium circulator operatinn could be interrupted by a SLROIS actuation'. Clarified operation of the reactor building louvre system following PCRV.depressurization and the fact that no t.redit'is taken for this system in equipment qualification or mitigating radiological: consequences.

F-P-89271 Attachment = July 21, 1989 T Page 5 of S '~ s Appendix A. Incorporated NRC SER reference on the acceptability-of the-performance of Fuel Test Elenent 2 (FTE-2). Updated PSC's commitments on the corrective actions to minimize stress corrosion cracking within the helium circulators. Appendix B Incorporated the Nuclear Operations' reorganhstion. Added text to address the use of a Technical Equivalency Assessil.ent (TEA) within the FSV Design Control System. Added.a subsection to addrest the provisions and conformances of the Records Storage Building. Appendix C i Provided clarification and section cross-referencing that auto-start of a circulator on its water turbine drive is a PPS function. Appendix 0 Removed the reference to high reheat steam temperature, high reheat steam pressure, and high core outlet temperature as loop shutdown signals. Added new Figure. 0.3-55 to include graphical depiction of vary 1 rig control rod bulk densities and their impact on compression of control reds during a loss of forced circulation event. Appendix E Added the provision that the use of metal or elastomer o-ring gaskets are acceptable for use on the primary closure of the helium circulators. Appendix F Revised figure to show location of Meteorological Tcwer. Appendix G Corrected equipment numbers on list of essential componentr,. 2-_

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