ML20024A890: Difference between revisions
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DPR-42 and 60. Also attached is one copy of the License Amendment class determination and a check in the amount of $4,400.00 for the amendment fee. | Northern States Power Company 414 Ncollet Mall Minneapohs. Minnesota 55401 Telephone (612) 330 5500 June 24, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request dated June 24, 1983 LOCA Analvsis Attached are three originals and 37 conformed copies of a request for a change of Technical Specifications, Appendix A, of Operating Licenses | ||
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DPR-42 and 60. | |||
Also attached is one copy of the License Amendment class determination and a check in the amount of $4,400.00 for the amendment fee. | |||
This submittal proposes changes to Section 3.10 of the Prairie Island Technical Specifications resulting from a new LOCA analysis performed by Exxon Nuclear Corporation. Additional information will be submitted by July 29, 1983 which will discuss the effect of the increase in peak pellet exposure to 55 GWD/MTU on off-site doses. | This submittal proposes changes to Section 3.10 of the Prairie Island Technical Specifications resulting from a new LOCA analysis performed by Exxon Nuclear Corporation. Additional information will be submitted by July 29, 1983 which will discuss the effect of the increase in peak pellet exposure to 55 GWD/MTU on off-site doses. | ||
This analysis has corrected the error found in the previous LOCA analysis (see Licensee Event Report 83-001/01T-0 dated February 18, 1983). The self imposed 17. Fq reduction (compensating for the error) will no longer bc used following approval of this amendment. | This analysis has corrected the error found in the previous LOCA analysis (see Licensee Event Report 83-001/01T-0 dated February 18, 1983). The self imposed 17. Fq reduction (compensating for the error) will no longer bc used following approval of this amendment. | ||
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%b David Musolf Manager-Nuclear Support Services QOPj l | |||
DMM/TMP/ dab l | |||
cc: Regfona1 Admin-III, NRC | |||
/} O NRR Resident Inspector, NRC MPCA fg Attn: J W Ferman i cM* | |||
Qe,*g{ W Attachments 8307010144 830624 PDR ADOCK 05000 P}} | |||
Latest revision as of 00:39, 21 December 2024
| ML20024A890 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/24/1983 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20024A891 | List: |
| References | |
| NUDOCS 8307010144 | |
| Download: ML20024A890 (1) | |
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Northern States Power Company 414 Ncollet Mall Minneapohs. Minnesota 55401 Telephone (612) 330 5500 June 24, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request dated June 24, 1983 LOCA Analvsis Attached are three originals and 37 conformed copies of a request for a change of Technical Specifications, Appendix A, of Operating Licenses
~
DPR-42 and 60.
Also attached is one copy of the License Amendment class determination and a check in the amount of $4,400.00 for the amendment fee.
This submittal proposes changes to Section 3.10 of the Prairie Island Technical Specifications resulting from a new LOCA analysis performed by Exxon Nuclear Corporation. Additional information will be submitted by July 29, 1983 which will discuss the effect of the increase in peak pellet exposure to 55 GWD/MTU on off-site doses.
This analysis has corrected the error found in the previous LOCA analysis (see Licensee Event Report 83-001/01T-0 dated February 18, 1983). The self imposed 17. Fq reduction (compensating for the error) will no longer bc used following approval of this amendment.
Exhibit A describes the proposed change, reason for change, and safety evaluation. Exhibit B contains the revised Appendix A pages. Exhibit C, Prairie Island Units 1 and 2 limiting break LOCA-ECCS analysis using EXEM/PWR XN-NF-83-38, contains the technical justification for the proposed changes.
l l
l
%b David Musolf Manager-Nuclear Support Services QOPj l
DMM/TMP/ dab l
cc: Regfona1 Admin-III, NRC
/} O NRR Resident Inspector, NRC MPCA fg Attn: J W Ferman i cM*
Qe,*g{ W Attachments 8307010144 830624 PDR ADOCK 05000 P