ML20057F473
| ML20057F473 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/07/1993 |
| From: | Gamberoni M Office of Nuclear Reactor Regulation |
| To: | Alan Anderson NORTHERN STATES POWER CO. |
| References | |
| GL-88-11, GL-92-01, GL-92-1, TAC-M83499, TAC-M83500, NUDOCS 9310180057 | |
| Download: ML20057F473 (5) | |
Text
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October 7, 1993 d
Docket Nos.:
50-282 plSTRIBUTION:
and 50-306 Docket File C.Jamerson NRC & Local PDRs OGC Mr. Roger 0. Anderson, Director PD31 Rdg File ACRS (10)
Licensing and Management Issues J. Roe M.Gamberoni Northern States Power Company J.Zwolinski D. Mcdonald 414 Nicollet Mall W. Dean S.Sheng Minneapolis, Minnesota 55401 B.Jorgensen,RIII J.Strosnider
Dear Mr. And rson:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - LICENSEE'S RESPONSE TO GENERIC LETTER 92-01, REVISION 1 (TAC NOS. M83499 and M83500)
By letter dated July 6, 1992, Northern States Power submitted its response to Generic Letter (GL) 92-01, Revision 1, " Reactor Vessel Structural Integrity,"
for the Prairie Island Nuclear Generating Plant, Units 1 and 2.
The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations," regarding reactor vessel structural integrity. Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
l The staff has completed a preliminarv review of your response to GL 92-01, Revision 1, for Prairie Island Units 1 and 2.
Enclosed is a request for additional information (RAI) which is needed to complete the review. We request a response to this RAI within 45 days of receipt of this letter.
If you have any questions concerning the enclosed RAI please contact me on (301) 504-3024.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Original Signed By:
Marsha Gamberoni, Project Manager l
Project Directorate III-l Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
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October 7, 1993 Docket Nos.:
50-282 and 50-306 Mr. Roger 0. Anderson, Director Licensing and Management Issues Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
Dear Mr. Anderson:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - LICENSEE'S RESPONSE TO GENERIC LETTER 92-01, REVISION 1 (TAC NOS. M83499 and M83500)
By letter dated July 6, 1992, Northern' States Power submitted its response to Generic Letter (GL) 92-01, Revision 1, " Reactor Vessel Structural Integrity,"
for the Prairie Island Nuclear Generating Plant, Units 1 and 2.
The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations," regarding l
reactor vessel structural integrity. Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The staff has completed a preliminary review of your response to GL 92-01, Revision 1, for Prairie Island Units 1 and 2.
Enclosed is a request for additional information (RAI) which is needed to complete the review. We request a response to this RAI within 45 days of receipt of this letter.
If you have any questions concerning the enclosed RAI please contact me on (301) 504-3024.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Ifodu kAC Marsha Gamberoni, Project Manager Project Directorate III-l Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
RAI cc w/ enclosures:
See next page
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4 Mr. Roger 0. Anderson, Director Prairie Island Nuclear Generating Northern States Power Company Plant cC:
J. E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.
Washington DC 20037 Mr. E. L. Watzl, Site General Manager Prairie Island Nuclear Generating Plant Northern States Power Company 1717 Wakonade Drive East Welch, Minnesota 55089 Lisa R. Tiegel Assistant Attorney General Environmental Protection Division Suite 200 520 Lafayette Road St. Paul, Minnesota 55155 U.S. Nuclear Regulatory Commission Resident Inspector Office 1719 Wakonade Drive East Welch, Minnesota 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Jeff Cole, Auditor / Treasurer Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 Octoter 1993 A
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i RE0 VEST FOR ADDITIONAL INFORMATION REGARDING GL 92-01. REVISION 1 i
PRAIRIE ISLAND 1 Ouestion 2a in GL 92-01 The response indicates that the lowest initial upper shelf energy (USE) value for the beltline welds in both units is 87 ft-lb. The corresponding value i
from the pressurized thermal shock (PTS) submittal dated January 10, 1986, is 78.5 ft-lb (from the surveillance weld).
Resolve this discrepancy and provide the basis for the single value to be reported. Also provide the calculation i
and all data needed to obtain the 42% decrease in the end-of-life (E0L) USE i
value stated in the response.
If the updated E0L USE is below 50 ft-lb, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.
Question 2b in GL 92-01 The response reports the initial RT,37 value for the beltline weld as -13 F.
The corresponding value from the pressure / temperature submittal dated October 28, 1988, is 0 F.
Resolve this discrepancy and provide the basis for the single value to be reported.
The response reports the chemical composition for the beltline weld as 0.13%
copper, but the nickel content is not known (from the surveillance weld). The corresponding values in the PTS submittal dated January 10, 1986, are 0.14%
copper and 0.17% nickel. Resolve this discrepancy and provide the basis for the values of copper and nickel content to be reported.
The response reports the chemical composition for the forging D (heat number 21887/38530) as 0.06% copper and 0.71% nickel. The corresponding values from the PTS submittal dated January 10, 1986, are 0.07% copper and 0.66% nickel.
Resolve this discrepancy and provide the basis for the values of copper and nickel content to be reported.
PRAIRIE ISLAND 2 Ouestion 2a in GL 92-01 The same RAI that appears under the heading " Question 2a in GL 92-01" for Prairie Island 1 applies to this plant.
Question 2b in GL 92-01 The response reports the initial RT,3, from the PTS submittal dated January "
values for the forgings C and D as 14 F and -2.2 F.
The corresponding values 1986, are -4 F and -6 *F.
Resolve this discrepancy and provide the basis for the initial RT,33 values to be reported.
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The response reports the chemical composition for the beltline weld as 0.082%
copper and 0.072% nickel (from the surveillance weld). The corresponding values from the PTS submittal dated January 10, 1986, are 0.09% copper and 0.13% nickel. Resolve this discrepancy and provide the basis for the values of copper and nickel content to be reported.
The response reports two sets of chemical compositions for forging C (heat number 22829) and forging D (heat number 22642): Appendix B indicates a chemical composition of 0.070% copper, 0.750% nickel for forging C and 0.080%
copper, 0.725% nickel for forging 0; Appendix D indicates 0.075% copper, 0.75%
j nickel for forging C, and 0.085% copper, 0.70% nickel for forging D.
Specify and provide justification for the selection of the chemical compositions, which will be used in future 4RT, and AUSE calculations for these two forgings.
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