ML20196J535
| ML20196J535 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/02/1999 |
| From: | Lyon C NRC (Affiliation Not Assigned) |
| To: | Richard Anderson NORTHERN STATES POWER CO. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1199, NUDOCS 9907070328 | |
| Download: ML20196J535 (5) | |
Text
i&WC k UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20606-0001 g%
f July 2, 1999 i
Mr. Roger O. Anderson, Director Nuclear Energy Engineering Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT-RESPONSE TO THE i
REQUEST FOR ADDITIONAL INFORMATION ON GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO. MA1199)
Dear Mr. Anderson:
On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity," to holders of nuclear operating licenses. In issuing the GL the staff required addressees to:
(1) identify, collect, and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of FederalRegulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to 10 CFR Part 50.
On August 17,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessments for Monticello.
The staff evaluated your response and provided its conclusion on December 9,1996. However, since the time of the staff's closure letter, the Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B&W) Owners Group have each submitted additional data regarding g
i the alloying chemistries of beltline welds in CE-and B&W-fabricated vessels. The additional alloying data were submitted in Topical Reports CE NPSD-1039, Revision 2, CE NSPD-1119, l
Revison 1, for CE-fabricated RPV welds, and BAW-2325, Revision 1, for B&W-fabricated RPV welds. In addition, Chicago Bridge and Iron (CB&l) boiling-water reactor data were submitted in
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Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that additional information was necessary relative to the structural integrity assessments for your Q
plants. On June 29,1998, the staff issued a request for additional information (RAI) in regard to
.7 the alloying chemistries of beltline welds, your assessment of surveillance data for your facility, and pressure-temperature (P-T) limits for Monticello. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative % the chemistries provided in the applicable topical report, and j
provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds I
on the structural integrity assessments for your facility rela h
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PDR ADOCK 05000263 i
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l R.O. Andersoi 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for Monticello.
. You provided your response to the staffs RAI for Monticello on September 17,1998. As a result of the staffs review of your responses to GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.
The new database diskettes are posted on the world-wide-web at a location that is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structural integrity asseraments. Future submittals on P-T limits or l
upper-shelf energy should reference the most current information.
j This closes the staffs efforts in regard to TAC No. MA1199. The staff appreciates your efforts in regard to this matter.
i Sincerely, CAF-Carl F. Lyon, Project Manager, Section 1 Project Directorate Ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-263 cc: See next page i
)
J l
1
.,, b Mr. Roger O. Anderson, Director J
Northem States Power Company Monticello Nuclear Generating Plant cc:
J. E. Silberg, Esquire Shaw, Pittman, Potts and Trowbndge Commissioner
. 2300 N Street, N. W.
Department of Public Service Washington DC 20037 121 Seventh Place East Suite 200 U.S. Nuclear Regulatory Commission St. Paul, Minnesota 55101-2145 Resident inspedor's Offee 2807 W. County Road 75 Adonis A. Nebiett Monticello, Minnesota 55362 Assistant Attomey General Office of the Attorney General Plant Manager 445 Minnesota Street Monticello Nuclear Generating Plant Suite 900 ATTN: Site Licensing St. Paul, Minnesota 55101-2127 Northem States Power Company 2807 West County Road 75 Site General Manager Monticello, Minnesota 55362-9637 Monticello Nuclear Generating Plant ATTN: Site Licensing Robert Nelson, President Northern States Power Company Minnesota Environmental Control 2807 West County Road 75 3
d Citizens Association (MECCA)
Monticello, Minnesota 55362-9637 1051 South McKnight Road St. Paul, Minnesota 55119 Commissioner Minnesota Pollution Control Agency
)
520 Lafayette Road St. Paul, Minnesota 55119 Regional Administrator, Region lil
' U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois-60532-4351 Commissioner of Health Minnesota Department of Health 717 Delaware Street, S. E.
Minneapolis, Minnesota 55440 Douglas M. Gruber, Auditor / Treasurer Wright County Govemment Center 10 NW Second Street Buffalo, Minnesota 55313 AprH 1999 l
E_
R.O. Anderson July 2, 1999 S0.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensings and H to 10 CFR 50, as applicable to the licensing basis for Monticello.
You provided your response to the staff's RAI for Monticello on September 17,1998. As a result of the staff's review of your responses to GL 92-01, Rev.1, Supp.1, and the Supp.1 RAl, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.
The new database diskettes are posted on the world-wide-web at a location that is linked to the NRC home page (http://www.ntc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits or upper-shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC No MA1199. The staff appreciates your efforts in regard to this matter.
Sincerely, Original signed by.
Carl F. Lyon, Project Manager, Section 1 I
Project Directorate 111 Division of Licensing Project Management i
Office of Nuclear Reactor Regulation 1
Docket No. 50-263 cc: See next page DISTRIBUTION:
Docket File PUBLIC OGC PD3-1 Reading C. Thomas /C. Craig R. Lanksbury, Rlll A.D. Lee ACRS DOCUMENT NAME: G:\\PDill-1\\MONTICEL\\LTRA1199
- Memo dtd 6/20/99 To receive a copy of this document, Indicate in the box C= Copy w/o attachment /endosure E= Copy wtth attachment / enclosure N e No copy OFFICE PM:LPD3 E LA:LPD3 E
SC:MCEB SC:LPD3 f
Flyon [
CJamersoh KWichman*
CCraih NAME DATE
'T / 2.
/99 1/ ~ 9- /99h 6 /20 /99 l/ dM/99 OFFICIAL RECORD COPY
l R.O. Anderson July 2, 1999 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensings and H to 10 CFR 50, as applicable to the licensing basis for Monticello.
You provided your response to the staffs RAI for Monticello on September 17,1998. As a result of the staffs review of your responses to GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.
The new database diskettes are posted on the world-wide-web at a location that is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID a, ) acceptable for your plant. No additional information is necessary with regard to the structural integrity astessments. Future submittals on P-T limits or upper-shelf energy should reference the most curre.7t information.
This closes the staffs efforts in regard to TAC No. MA i199. The staff appreciates your efforts in regard to this matter.
l Sinceraly, Oritinal signed by:
Carl F. Lyon, Project Manager, Section 1 Proioct Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation j
Docket No. 50-263 cc: See next page DISTRIBUTION:
Docket File PUBLIC OGC PD3-1 Reading C. Thomas /C. Craig R. Lanksbury, Rill A.D. Lee ACRS DOCUMENT NAME: G:\\PDill-1\\MONTICEL\\LTRA1199
- Memo dtd 6/20/99 To recorve a copy of the document Indicate in the bos C= Copy w/o attachment /enclosoro E= Copy with attachment / enclosure N = No copy OFFICE PM:LPD3 E LA:LPD3 E
SC:MCEB SC:LPD3 O
Flyon [
CJamersoh/KWichman*
CCraik NAME DATE 7/ 2
/99 1/ 9- /99[]
6/20 /99 l/ d$\\/99 OFFICIAL RECORD COPY