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3, o, w,,,,,, Southem Nudear Operating Company g';Sgt June 3, 1992 N souNm e ecac z | 3, o, w,,,,,, Southem Nudear Operating Company g';Sgt June 3, 1992 N souNm e ecac z | ||
swem Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant larae Break LOCA PCT Penalty Associated with LOCA+SSE Gentlemen: | swem Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant larae Break LOCA PCT Penalty Associated with LOCA+SSE Gentlemen: | ||
By letter dated July 31, 1990, Alabama Power Company forwarded WCAP-12659, | By {{letter dated|date=July 31, 1990|text=letter dated July 31, 1990}}, Alabama Power Company forwarded WCAP-12659, | ||
" Alabama Power Joseph M. Farley Unit 2 Increas J Steam Generator Tube Plugging _ and Reduced Thermal Design Flow L; censing Report," in support of increasing the steam generator tube plagging limit to an average of 15%. | " Alabama Power Joseph M. Farley Unit 2 Increas J Steam Generator Tube Plugging _ and Reduced Thermal Design Flow L; censing Report," in support of increasing the steam generator tube plagging limit to an average of 15%. | ||
Included in that WCAP on page 4.10 was a conservative 50*F large break LOCA PCT penalty for the combined effects of a LOCA+5SE. | Included in that WCAP on page 4.10 was a conservative 50*F large break LOCA PCT penalty for the combined effects of a LOCA+5SE. | ||
By letter _ dated November 18, 1990, Alabama Power Company forwarded WCAP-12763, " Steam Generator Tube Collapse Considerations," documenting the slides used in a meeting with the NRC Staff on November 7, 1990. In that letter, a commitment was made to update the large break LOCA PCT penalty discussed in WCAP-12659 on completion of the leak-before-break (LBB) analysis for Unit 2. A similar commitment was made for Unit 1 in a January 14, 1991 letter. | By letter _ dated November 18, 1990, Alabama Power Company forwarded WCAP-12763, " Steam Generator Tube Collapse Considerations," documenting the slides used in a meeting with the NRC Staff on November 7, 1990. In that letter, a commitment was made to update the large break LOCA PCT penalty discussed in WCAP-12659 on completion of the leak-before-break (LBB) analysis for Unit 2. A similar commitment was made for Unit 1 in a {{letter dated|date=January 14, 1991|text=January 14, 1991 letter}}. | ||
The LBB analysis was forwarded to the NRC on January 28, 1991. By letter dated Augus. 12, 1991, the Staff issued its safety evaluation report for LBB. | The LBB analysis was forwarded to the NRC on January 28, 1991. By letter dated Augus. 12, 1991, the Staff issued its safety evaluation report for LBB. | ||
By letter dated Septemoer 10, 1991, Alabama Power Company forwarded WCAP-13064, "J. M. Farley Nuclear Plant Units 1 and 2 Response to NRC Request for Additional Information on Steam Generator Flow Area Reduction due to Combined LOCA and SSE Loads." This WCAP provided a Farley specific | By letter dated Septemoer 10, 1991, Alabama Power Company forwarded WCAP-13064, "J. M. Farley Nuclear Plant Units 1 and 2 Response to NRC Request for Additional Information on Steam Generator Flow Area Reduction due to Combined LOCA and SSE Loads." This WCAP provided a Farley specific | ||
_ analysis which provided the basis for reducing- the previous 50'F penalty to 6*F. | _ analysis which provided the basis for reducing- the previous 50'F penalty to 6*F. | ||
In conjunction with the steam generator tube support plate alternate plugging criteria, by letter dated November 13, 1991, Alabama Power Company forwarded WCAP-12871, Revision 1, "J. M. Farley Units 1 and ? SG Tube Plugging Criteria for ODSCC at Tube Support Plates." Section 11.0, " Steam Line Break and Combined Accident Considerations," contains the latest analysis performed by Westinghouse. This analysis, based on a Model 51 tube support plate crush test, results in no penalty for tube collapse as a result of the LOCA+SSE. This analysis is also contained in Revision 2 of WCAP-12871 submitted by letter dated February 20, 1992. | In conjunction with the steam generator tube support plate alternate plugging criteria, by {{letter dated|date=November 13, 1991|text=letter dated November 13, 1991}}, Alabama Power Company forwarded WCAP-12871, Revision 1, "J. M. Farley Units 1 and ? SG Tube Plugging Criteria for ODSCC at Tube Support Plates." Section 11.0, " Steam Line Break and Combined Accident Considerations," contains the latest analysis performed by Westinghouse. This analysis, based on a Model 51 tube support plate crush test, results in no penalty for tube collapse as a result of the LOCA+SSE. This analysis is also contained in Revision 2 of WCAP-12871 submitted by {{letter dated|date=February 20, 1992|text=letter dated February 20, 1992}}. | ||
9206090203 920603 / | 9206090203 920603 / | ||
PDR ADOCK 05000348 [8i P PDR | PDR ADOCK 05000348 [8i P PDR | ||
-* U. S. Nuclear' Regulatory Commission Pa9e two By letter dated March 11, 1992, the Staff forwarded the safety evaluation report 7for VANTAGE-5. This evaluation contained a 6*F penalty for the LOCA+SSE issue. | -* U. S. Nuclear' Regulatory Commission Pa9e two By {{letter dated|date=March 11, 1992|text=letter dated March 11, 1992}}, the Staff forwarded the safety evaluation report 7for VANTAGE-5. This evaluation contained a 6*F penalty for the LOCA+SSE issue. | ||
Contrary to the commitment in the November 18, 1990 and January 14, 1991 | Contrary to the commitment in the November 18, 1990 and {{letter dated|date=January 14, 1991|text=January 14, 1991 letter}}s, Southern Nuclear does not intend to update WCAP-12659 or WCAP-12694. Revised analyses have been documented in WCAP-13064 and WCAP-12871, Revisions 1 and 2. Since these WCAPs have been submitted to the Staff, Southern Nuclear sees no need to update WCAP-12659 or WCAP-12694. | ||
If there are any questions, please advise. | If there are any questions, please advise. | ||
Respectfully submitted, SOUTHERN NUCLEAR OPEri.!"G COMPANY | Respectfully submitted, SOUTHERN NUCLEAR OPEri.!"G COMPANY | ||
. Woodard JDW/ REM: map d.1 cc: Mr. S. D. Ebneter Mr. S. T. Hoffman. | . Woodard JDW/ REM: map d.1 cc: Mr. S. D. Ebneter Mr. S. T. Hoffman. | ||
Mr. G. F. Maxwell v a - --ww r w>>- e -}} | Mr. G. F. Maxwell v a - --ww r w>>- e -}} | ||
Revision as of 01:08, 24 September 2022
| ML20101C403 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/03/1992 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9206090203 | |
| Download: ML20101C403 (2) | |
Text
.-
Scutnern &cear Opoeno Company ,
Post CMee Box 1295 l
. Barregham, Akhma 35201 I
. T,9ephone 205 068 5086 m
3, o, w,,,,,, Southem Nudear Operating Company g';Sgt June 3, 1992 N souNm e ecac z
swem Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant larae Break LOCA PCT Penalty Associated with LOCA+SSE Gentlemen:
By letter dated July 31, 1990, Alabama Power Company forwarded WCAP-12659,
" Alabama Power Joseph M. Farley Unit 2 Increas J Steam Generator Tube Plugging _ and Reduced Thermal Design Flow L; censing Report," in support of increasing the steam generator tube plagging limit to an average of 15%.
Included in that WCAP on page 4.10 was a conservative 50*F large break LOCA PCT penalty for the combined effects of a LOCA+5SE.
By letter _ dated November 18, 1990, Alabama Power Company forwarded WCAP-12763, " Steam Generator Tube Collapse Considerations," documenting the slides used in a meeting with the NRC Staff on November 7, 1990. In that letter, a commitment was made to update the large break LOCA PCT penalty discussed in WCAP-12659 on completion of the leak-before-break (LBB) analysis for Unit 2. A similar commitment was made for Unit 1 in a "NL-90-3123, Forwards Supplemental Info to 901026 Application for Amend to License NPF-2 Re RTD Bypass Elimination & Steam Generator Tube plugging.[[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Assessment for RCS Piping Also Encl|January 14, 1991 letter]].
The LBB analysis was forwarded to the NRC on January 28, 1991. By letter dated Augus. 12, 1991, the Staff issued its safety evaluation report for LBB.
By letter dated Septemoer 10, 1991, Alabama Power Company forwarded WCAP-13064, "J. M. Farley Nuclear Plant Units 1 and 2 Response to NRC Request for Additional Information on Steam Generator Flow Area Reduction due to Combined LOCA and SSE Loads." This WCAP provided a Farley specific
_ analysis which provided the basis for reducing- the previous 50'F penalty to 6*F.
In conjunction with the steam generator tube support plate alternate plugging criteria, by letter dated November 13, 1991, Alabama Power Company forwarded WCAP-12871, Revision 1, "J. M. Farley Units 1 and ? SG Tube Plugging Criteria for ODSCC at Tube Support Plates." Section 11.0, " Steam Line Break and Combined Accident Considerations," contains the latest analysis performed by Westinghouse. This analysis, based on a Model 51 tube support plate crush test, results in no penalty for tube collapse as a result of the LOCA+SSE. This analysis is also contained in Revision 2 of WCAP-12871 submitted by letter dated February 20, 1992.
9206090203 920603 /
-* U. S. Nuclear' Regulatory Commission Pa9e two By letter dated March 11, 1992, the Staff forwarded the safety evaluation report 7for VANTAGE-5. This evaluation contained a 6*F penalty for the LOCA+SSE issue.
Contrary to the commitment in the November 18, 1990 and "NL-90-3123, Forwards Supplemental Info to 901026 Application for Amend to License NPF-2 Re RTD Bypass Elimination & Steam Generator Tube plugging.[[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Assessment for RCS Piping Also Encl|January 14, 1991 letter]]s, Southern Nuclear does not intend to update WCAP-12659 or WCAP-12694. Revised analyses have been documented in WCAP-13064 and WCAP-12871, Revisions 1 and 2. Since these WCAPs have been submitted to the Staff, Southern Nuclear sees no need to update WCAP-12659 or WCAP-12694.
If there are any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPEri.!"G COMPANY
. Woodard JDW/ REM: map d.1 cc: Mr. S. D. Ebneter Mr. S. T. Hoffman.
Mr. G. F. Maxwell v a - --ww r w>>- e -