ML20056F008

Forwards Request for Addl Info Needed to Complete Review of Licensee Response to Rev 1 to GL 92-01, Reactor Vessel Structural Integrity

ML20056F008
Person / Time
Site:	Calvert Cliffs
Issue date:	08/09/1993
From:	Mcdonald D Office of Nuclear Reactor Regulation
To:	Denton R BALTIMORE GAS & ELECTRIC CO.
References
GL-88-11, GL-90-01, GL-90-1, TAC-M83446, TAC-M83447, NUDOCS 9308250399
Download: ML20056F008 (6)

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f WASHINGTON, D.C. 20555-0001 August 9, 1993 Docket Nos. 50-317 and 50-318 Mr. Robert E. Denton Vice President - Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702

SUBJECT:

RESPONSE TO GENERIC LETTER (GL) 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY." CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT N0. 1 (TAC NO. M83446) AND UNIT NO. 2 (TAC N0. M83447)

The purpose of this letter is to request additional information related to the subject GL. The subject GL was issued on March 6, 1992, to compile information necessary to confirm that licensees and permit holders satisfy the requirements for ensuring reactor vessel integrity. In the GL, the staff requested responses to three questions. These three questions requested that information be provided regarding: 1) Appendix H to 10 CFR Part 50;

2) Appendix G to 10 CFR Part 50; and 3) commitments made in responses to GL 88-11.

By letter dated June 30, 1992, Baltimore Gas & Electric Company responded to GL 92-01, Revision 1, by providing the information requested in the Required Information portion of the GL. The staff has completed its initial review of you: response and has determined that additional information is needed.

Enclosed is a request for additional information (RAI). We request that BG&E respond to the RAI within 60 days from receipt of this letter.

The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, " Reactor Vessel Structural Integrity, 10 CFR 50.54(f)." The estimated average number of burden hours is 200 person hours for each addressee's response. This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.

NBC FRE CEM CM IY 9308250399 930809 PDR ADOCK 05000317 P PDR .

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Mr. Roaert E. Denton August 9, 1993 This action is covered by the Office of Management and Budget Clearance Number  ;

3150-0011, which expires June 30, 1994.

Sincerely, m

D iel G. Mcdonald, Senior Project Manager '

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page i

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I Mr. Robert E. Denton Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 cc:

Mr. Michael Moore, President Mr. Joseph H. Walter Calvert County Board of Engineering Division Commissioners Public Service Commission of 175 Main Street Maryland Prince Frederick, Maryland 20678 American Building 231 E. Baltimore Street D. A. Brune, Esquire Baltimore, Maryland 21202-3486 General Counsel Baltimore Gas and Electric Company Kristen A. Burger, Esquire P. O. Box 1475 Maryland People's Counsel Baltimore, Maryland 21203 American Building, 9th Floor 231 E. Baltimore Street Jay E. Silberg, Esquire Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Patricia T. Birnie, Esquire Washington, DC 20037 Co-Director Maryland Safe Energy Coalition Mr. G. L. Detter, Director, NRM P. O. Box 33111 Calvert Cliffs Nuclear Power Plant Baltimore, Maryland 21218 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-47027 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 287 St. Leonard, Maryland 20685 4

Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue Tawes State Office Building B3 Annapolis, Maryland 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 2

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_ Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 92-01, REVISION 1 for ease of referencing, each question is related to the corresponding question in Generic Letter (GL) 92-01.

CALVERT CLIFFS 1 (TAC NO. M83446)

Question 2a in GL 92-01 The response to GL 92-01 indicates that the initial upper-shelf energy (USE) values for lower shell course welds 3-203 A, B, C are not known.

Either provide the initial Charpy USE for each beltline weld or provide the initial Charpy USE and analysis from welds that were fabricated using l the same vendor, fabrication time frame, fabrication process, and I material specification to demonstrate that all beltline welds will meet the USE requirements of Appendix G,10 CFR 50. If this cannot be provided, then submit an analysis which demonstrates that lower values of l

USE will provide margins of safety against fracture equivalent to those.

required by Appendix G of the ASME Code.

The unirradiated USE values provided in the response to GL 92-01 for the surveillance materials (plate D-7206-3 and weld 9-203) differ from the values provided in surveillance report BMI-1280 (see table below).

Resolve this discrepancy.

Material GL 92-01 initial USE BMI-1280 initial USE D-7206-3 112 ft-lb 138 ft-lb 9-203 158 ft-lb 160 ft-lb CALVERT CLIFFS 2 (TAC No. M83447)

Question 2a in GL 92-01 The response to GL 92-01 indicates that the initial USE values for lower shell course welds 2-203 A, B, C are not known. Either provide the initial Charpy USE for each beltline weld or provide the initial Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds wil! meet the USE requirements of Appendix G, 10 CFR 50. If this cannot be provided, 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.

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O The unirradiated USE values provided in the response to GL 92-01 for the surveillance materials (plate D-9807-2 and weld 9-203) differ from the values provided in surveillance report SwRI-7524 (see table below).

Resolve this discrepancy.

Material GL 92-01 initial USE SwRI-7524 initial USE D-7206-3 115 ft-lb 146 ft-lb 9-203 125 ft-lb 137 ft-lb r

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Mr. Robert E. Denton August 9, 1993

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This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.  :

Sincerely,  ;

Original Signed By:

Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1 Division of. Reactor Projects - I/II ,.;

Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional  :

Information i cc w/ enclosure:  :

See next page j i

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