ML20207B126: Difference between revisions

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| number = ML20207B126
| number = ML20207B126
| issue date = 07/14/1986
| issue date = 07/14/1986
| title = Advises That Intention to Follow Util QA Procedures,Using Modified Version of VIPRE-01 Instead of EPRI Developed Vipre Code,Per 860701 Ltr,Acceptable.Dnbr Limit of 1.17 for WRB-1 Correlation in Nspnad 8102 Document Should Be Added
| title = Advises That Intention to Follow Util QA Procedures,Using Modified Version of VIPRE-01 Instead of EPRI Developed Vipre Code,Per ,Acceptable.Dnbr Limit of 1.17 for WRB-1 Correlation in Nspnad 8102 Document Should Be Added
| author name = Diianni D
| author name = Diianni D
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = TAC-57644, TAC-57645, NUDOCS 8607170434
| document report number = TAC-57644, TAC-57645, NUDOCS 8607170434
| title reference date = 07-01-1986
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 3
| page count = 3
| project = TAC:57644, TAC:57645
| stage = Other
}}
}}


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==Dear Mr. Musolf:==
==Dear Mr. Musolf:==


By letter dated July 1,1986 you informed the NRC of your intention to follow the Northern States Power Company's (NSP's) quality assurance (Q/A) procedures which include assigning NSP's designations to the modified version of the VIPRE-01 code that is used in the refueling analysis for the Prairie Island Nuclear Generating Plant Unit Nos. 1 and 2. Our safety evaluation report issued on May 30, 1986 required you to follow the EPRI Q/A procedures for code modifications such that a consistent configuration would exist in the EPRI developed VIPRE code. Since you will use NSP's designation in your modified version of VIPRE-01 which is disassociated from the EPRI developed VIPRE-01 code, we find your intention of following your own Q/A procedures acceptable. However, any changes to the VIPRE-01 code that significantly changes the final results will require staff review and approval prior to use in a licensing application.
By {{letter dated|date=July 1, 1986|text=letter dated July 1,1986}} you informed the NRC of your intention to follow the Northern States Power Company's (NSP's) quality assurance (Q/A) procedures which include assigning NSP's designations to the modified version of the VIPRE-01 code that is used in the refueling analysis for the Prairie Island Nuclear Generating Plant Unit Nos. 1 and 2. Our safety evaluation report issued on May 30, 1986 required you to follow the EPRI Q/A procedures for code modifications such that a consistent configuration would exist in the EPRI developed VIPRE code. Since you will use NSP's designation in your modified version of VIPRE-01 which is disassociated from the EPRI developed VIPRE-01 code, we find your intention of following your own Q/A procedures acceptable. However, any changes to the VIPRE-01 code that significantly changes the final results will require staff review and approval prior to use in a licensing application.
It would be desirable to add the DNBR limit of 1.17 for the WRB-1 correlation in the NSPNAD 8102 document for the acceptance criterion for each accident to avoid confusion with the DNBR limit of 1.3 for the W-3 correlation. However, since Appendix F of NSPNAD 8102 has clearly identified the DNBR limit of 1.17 for the WRB-1 correlation and you have committed to incorporate this limit to the acceptance criteria in the next revision to NSPNAD-8102 we find Revision 4 to NSPNAD 8102 as presented is acceptable.
It would be desirable to add the DNBR limit of 1.17 for the WRB-1 correlation in the NSPNAD 8102 document for the acceptance criterion for each accident to avoid confusion with the DNBR limit of 1.3 for the W-3 correlation. However, since Appendix F of NSPNAD 8102 has clearly identified the DNBR limit of 1.17 for the WRB-1 correlation and you have committed to incorporate this limit to the acceptance criteria in the next revision to NSPNAD-8102 we find Revision 4 to NSPNAD 8102 as presented is acceptable.
Sincerely,
Sincerely,

Latest revision as of 01:50, 6 December 2021

Advises That Intention to Follow Util QA Procedures,Using Modified Version of VIPRE-01 Instead of EPRI Developed Vipre Code,Per ,Acceptable.Dnbr Limit of 1.17 for WRB-1 Correlation in Nspnad 8102 Document Should Be Added
ML20207B126
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 07/14/1986
From: Diianni D
Office of Nuclear Reactor Regulation
To: Musolf D
NORTHERN STATES POWER CO.
References
TAC-57644, TAC-57645, NUDOCS 8607170434
Download: ML20207B126 (3)
v • d • e


Text

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JUL 141986 .

Docket Nos. 50-282/306 Mr. D. M. Musolf, Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall Midland Square, 4th Floor Minneapolis, Minnesota 55401

Dear Mr. Musolf:

By letter dated July 1,1986 you informed the NRC of your intention to follow the Northern States Power Company's (NSP's) quality assurance (Q/A) procedures which include assigning NSP's designations to the modified version of the VIPRE-01 code that is used in the refueling analysis for the Prairie Island Nuclear Generating Plant Unit Nos. 1 and 2. Our safety evaluation report issued on May 30, 1986 required you to follow the EPRI Q/A procedures for code modifications such that a consistent configuration would exist in the EPRI developed VIPRE code. Since you will use NSP's designation in your modified version of VIPRE-01 which is disassociated from the EPRI developed VIPRE-01 code, we find your intention of following your own Q/A procedures acceptable. However, any changes to the VIPRE-01 code that significantly changes the final results will require staff review and approval prior to use in a licensing application.

It would be desirable to add the DNBR limit of 1.17 for the WRB-1 correlation in the NSPNAD 8102 document for the acceptance criterion for each accident to avoid confusion with the DNBR limit of 1.3 for the W-3 correlation. However, since Appendix F of NSPNAD 8102 has clearly identified the DNBR limit of 1.17 for the WRB-1 correlation and you have committed to incorporate this limit to the acceptance criteria in the next revision to NSPNAD-8102 we find Revision 4 to NSPNAD 8102 as presented is acceptable.

Sincerely,

/s/

Dominic C. Dilanni, Project Manager Project Directorate #1 Division of PWR' Licensing-A cc's: See Next Page "

860717o434 e60714 PDR ADOCK 05000282

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Office: PM/ PAD #1 PARS PD/ PAD #1 Surname:* DDilanni/tg

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  • Glear Date:- 07/11/86 07/11/86 07/14 /86

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