ML062650224

Vermont Yankee Hearing - Staff Exhibit 5, NRR Review Standard for Extended Power Uprates, RS-001, Rev. 1

ML062650224
Person / Time
Site:	Vermont Yankee
Issue date:	12/31/2003
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Byrdsong A T
References
50-271-OLA, Entergy-Staff-5, RAS 12300 RS-001, Rev 0
Download: ML062650224 (4)

Text

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DOCKETED USNRC SEP 19" PM 3: 48 pt I,,:~~ T11 -  ;

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.PROD. &UTILFA 5o-.HO-*0L OFFICE OF U[CLEAR REACTOR REGULATION REVIEW STANDARD FOR EXTENDED POWER UPRATES APPROVED BY: .l ,

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La. 1XLMflIU, LMUCULUF Division of iUcensing Project'Managementlms. NuCLEAR EBautufRycoI 1 rVM Office of Nuclear Reactor Regulation iewL M, wALt, tJcrav,..-/m(,,.

&ta , . 4e.4 Onv b;*yApp!lcant/Licensee Intervenor NFIC taff Other CONTACT: Moh rammed A. Shualbl, NRR RAl SAIlr* J

, A" mas4@nrc.g~ov RS-001, Revision 0 DECEMBER 2003 lemCV taf7 CC Y_ 0- 0,;2_

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RS-001, REVISION 0 REVIEW STANDARD FOR EXTENDED POWER UPRATES TAbLE OF CONTENtS PURPOSE BACKGROUND GUIDANCE SECTION 1 - PROCEDURAL GUIDANCE 1.1 - Processing Extended Power Uprate Applications Figure 1.1 EPU Process Flow Chart SECTION 2 - TECHNICAL REVIEW GUIDANCE 2.1 - Reviewing Extended Power Uprate Applications Matrix i - Materials and Chemical Engineering Matrix 2 - Mechanical and Civil Engineering Matrix 3- Electrical Engineering Matrix 4 - Instrumentation and Controls Matrix 5 - Plant Systems Matrix 6 - Containment Review Considerations Matrix 7 - Habitability, Filtration, and Ventilation Matrix 8 - Reactor Systems Matrix 9 - Source Terms and Radiological Consequences Analyses Matrix 10 - Health Physics Matrix 11 - Human Performance Matrix 12 - Power Ascension and Testing Plan Matrix 13 - Risk Evaluation SECTION 3 - DOCUMENTATION OF REVIEW 3.1 - Documenting Reviews of Extended Power Uprate Applications 3.2 - Boiling-Water Reactor Template Safety Evaluation Insert 1 - Materials and Chemical Engineering Insert 2 - Mechanical and CMI Engineering Insert 3 - Electrical Engineering Insert 4 - Instrumentation and Controls Insert 5 - Plant Systems Insert 6 - Containment Review Considerations Insert 7 - Habitability, Filtration, and Ventilation Insert 8 - Reactor Systems Insert 9 - Source Terms and Radiological Consequences Analyses Insert 10 - Health Physics Insert 11 - Human Performance Insert 12 - Power Ascension and Testing Plan Insert 13 - Risk Evaluation 3.3 - Pressurized-Water Reactor Template Safety Evaluation Insert 1 - Materials and Chemical Engineering Insert 2- Mechanical and Civil Engineering insert 3 - Electrical Engineering Insert 4 - Instrumentation and Controls Insert 5 -.Plant Systems Insert 6 - Containment Review Considerations Insert 7 - Habitability, Filtration, and Ventilation Insert 8 - Reactor Systems Insert 9 - Source Terms and Radiological Consequences Analyses Insert 10-- Health Physics Insert ii - Human Performance Insert 12 - Power Ascension and Testing Plan Insert 13 - Risk Evaluation SECTION 4 - INSPECTION GUIDANCE 4.1 - Inspection Requirements DECEMBER 2003

- A MATRIX 12 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Power Ascension and Testing Plan Power Aseenslon and Testing Ai VPU9 I9P1 14.2.1' Entire Section 2.12 2.12 EMCB Draft Rev. 0 EMVEB Dec. 2002 IROB SPLW 8PS5 5 5~

SRXI3 I - .1 I a

• The staff Is currently finalizing SRP Section 142-1. While this SRP Section Is being finalized, the staff will continue to use the version Issued for Interim use and public comment In December 2002. Once finalized, the staff wll use the newversion.

MATRIX 12 OF SECTION 2.1 OF RS-001, REVISION DECEMBER 20(

2.12 Power Ascension and Testing Plan 2.12.1 Approach to EPU Power Level and Test Plan Regulatory Evaluation The purpose of the EPU test program Is to demonstrate that SSCs will perform satisfactorily In service at the proposed EPU power level. The test program also provides additional assurance that the plant will continue to operate In accordance with design criteria at EPU conditions. The NRC staff's review Included an evaluation of: (1) plans for the Initial approach to the proposed maximum licensed thermal power level, Including verification of adequate plant performance, (2) transient testing necessary to demonstrate that plant equipment will perform satisfactorily at the proposed Increased maximum licensed thermal power level, and (3) the test program's conformance with applicable regulations. The NRC's acceptance criteria for the proposed EPU test program are based on 10 CFR Part 50, Appendix B, Criterion XI, which requires establishment of a test program to demonstrate that SSCs will perform satisfactorily In service.

Specific review criteria are contained In SRP Section 14.2.1.

Technical Evaluation

[insert technical evaluation. The technical evaluation should (1) clearly explain why the proposed changes satisfy each of the requirements In the regulatory evaluation and (2) provide a clear link to the conclusions reached by the NRC staff, as documented In the conclusion section.]

Conclusion The staff has reviewed the EPU test program, Including plans for the Initial approach to the proposed maximum licensed thermal power level, transient testing necessary to demonstrate that plant equipment will perform satisfactorily at the proposed Increased maximum licensed thermal power level, and the test program's conformance with applicable regulations. The staff concludes that the proposed EPU test program provides adequate assurance that the plant will operate In accordance with design criteria and that SSCs affected by the proposed EPU, or modified to support the proposed EPU, will perform satisfactorily in service. Further, the staff finds that there Is reasonable assurance that the EPU testing program satisfies the requirements of 10 CFR Part 50, Appendix B, Criterion XI. Therefore, the NRC staff finds the proposed EPU test program acceptable.

INSERT 12 FOR SECTION 3.2 - BWR TEMPLATE SAFETY EVALUATION DECEMBER 2003