ML20210A631

Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2

ML20210A631
Person / Time
Site:	Calvert Cliffs
Issue date:	07/06/1999
From:	Dromerick A NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
References
TAC-MA0532, TAC-MA0533, NUDOCS 9907220162
Download: ML20210A631 (4)

Text

_

1. ~go UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION

.. 7. -E WASHINGTON, D. C. 20555 Tuly 6, 1999

(.....

Mr. Charles H. Cruse Vice President, Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 -

SUBJECT:

CLOSURE OF TAC NOS. MA0532 AND MA0533 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL '

INTEGRITY," FOR CALVERT CLIFFS NUCLEAR FOWER PLANT, UNIT NOS.1 AND2 .

Dear Mr. Cruse:

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 of the GL to l

' (i) identify, collect and report any new data pertinent to the analysis of structuralintegrity of the reactor pressure vessels (RPVs) at their nuclear plants, and i

(2) to 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 Federal Regulatlons (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code of FederalRegulations (Appendic d 10 CFR Part 50). g $

on July 24,1995, 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 Calvert Cliffs Nuclear Power Plants. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its concluelon relative to your response on August 1,1996. 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 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 NPSD-1119,  !

Revision 1, for CE fabricated RPV welds, and BAW-2325, Revision 1, for B&W f abricated RPV '

welds. In addition, Chicago Bridge and Iron (CB&l) BWR data were sikmitted in Topical 9 Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that ,

additionalinformation was necessary relative to the structural integrity assessments for your /,0\ ,

plants. On April 3,1998, the staff issued a request for additional information (RAl) in regard to d the alloying chemistries of beltline welds, your assessment of surveillance data for your f acility, J pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments for the Calvert Cliffs Nuclear Power Plants. 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 to the chemistries provided in the applicable topical report, and i

9907220162 990706 PDR ADOCK 05000317 P PDR i

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C. CrusG) provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing bases for your plants.

You provided your response to the staff's RAI for Calvert Cliffs Nuclear Plants on July 1,1998.

As a result of the staff's review of your responses to GL 92-01, Revision 1, 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 which 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 1,1953, we will j assume that the data entered into the RVID are acceptable for your plant. No additional l information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy (USE) should reference the most current information.

. This closes the staff's efforts in regard to TAC Nos. MA0532 and MA0533. The staff appreciates your efforts in regard to this matter.

Sincerely, 1 I

original signed by: ]

Alexander W. Dromerick , Sr. Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 l

cc: See next page DISTRIBUTION:

Docket File PUBLIC PDI-1 R/F S. Bajwa S. Little A. Dromerick A. Lee OGC ACRS M. Oprendek, RGNI DOCUMENT NAME: G:\PDI-1\CC1-2\9201cise.wpd To receive a copy of this document indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attadiment/ enclosure "N" - No copy ,

OFFICE PDI-1/fMJ 4 /)\ l PDI-1/LA nG l PDI-1/SC /3 ql b -l ,

NAME ADromdM .k Mc '" SL1ttle M V SBa 9a 8 " W j _

DATE 07/ 'I /99 07/9 /99 07/4 /99 07/ /99 i OFFICIAL RECORD CQPY

.. 1 C. Cruse provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing bases for your plants.

You provided your response to the staff's RAI for Calvert Oliffs Nuclear Plt.nts on July 1,1998.

As a resu;t of the staff's review of your responses to GL 92-01, Revision 1, 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 which 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 commnnts by September 1,1999, we will assume that the data entered into the RVID are acceptabL, for your plant. No additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy (USE) should reference the most current information.

This closes the t .aff's efforts in regard to TAC Nos. MA0532 and MA0533. The staff appreciates your efforts in regard to this matter.

Sincerely, sq W DY Alexander W. Dromerick , Sr. Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 cc: See next page

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y Calvert Cliffs Nuclear Power Plant .

Unit Nos.1 and 2 President Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806

~ James P. Bennett, Esquire Counsel Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre ,

Baltimore, MD 21203 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire .

Shaw, Pittman, Potts, and Trowbridge Patricia T. Birnie, Esquire i 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Bruce S. Montgomery, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatell 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, TN 37411-4017 Resident inspector U.S. Nuclear Regulatory l Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean, Manager Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401

, Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 I

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