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 | | 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 | |||
}} | }} | ||
| Line 18: | Line 21: | ||
{{#Wiki_filter:- | {{#Wiki_filter:- | ||
y.. | y.. | ||
JUL 141986 | 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 | ||
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:== | ==Dear Mr. Musolf:== | ||
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. | |||
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. | 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, | ||
/s/ | |||
Dominic C. Dilanni, Project Manager Project Directorate #1 Division of PWR' Licensing-A cc's: See Next Page | Dominic C. Dilanni, Project Manager Project Directorate #1 Division of PWR' Licensing-A cc's: See Next Page 860717o434 e60714 PDR ADOCK 05000282 | ||
860717o434 e60714 PDR | *SEE PREVIOUS CONCURRENCE P | ||
PDR Office: | |||
Office: PM/ PAD #1 | PM/ PAD #1 PARS PD/ PAD #1 Surname:* DDilanni/tg | ||
* CBerlinger | * CBerlinger | ||
* Glear Date:- | * Glear Date:- | ||
07/11/86 07/11/86 07/14 /86 i | |||
a e | a e | ||
Distribution Copies: | Distribution Copies: | ||
C Docket Files'- | C Docket Files'- | ||
NRC POR Local PDR PAD #1 r/f PAD #1 p/f TNovak, Actg. DD NThompson, DHFT ELD EJordan BGrimes JPartlow Glear PShuttleworth ACRS (10) | NRC POR Local PDR PAD #1 r/f PAD #1 p/f TNovak, Actg. DD NThompson, DHFT ELD EJordan BGrimes JPartlow Glear PShuttleworth ACRS (10) | ||
)}} | |||
Latest revision as of 22:37, 6 December 2024
| ML20207B126 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| 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) | |
Text
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y..
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
- SEE PREVIOUS CONCURRENCE P
PDR Office:
PM/ PAD #1 PARS PD/ PAD #1 Surname:* DDilanni/tg
- CBerlinger
- Glear Date:-
07/11/86 07/11/86 07/14 /86 i
a e
Distribution Copies:
C Docket Files'-
NRC POR Local PDR PAD #1 r/f PAD #1 p/f TNovak, Actg. DD NThompson, DHFT ELD EJordan BGrimes JPartlow Glear PShuttleworth ACRS (10)
)