ML20057F478

Requests Addl Info Re Response to GL 92-01,rev 1, Reactor Vessel Structural Integrity,10CFR50.54(f), for Plants

ML20057F478
Person / Time
Site:	Byron, Braidwood, Zion  File:ZionSolutions icon.png
Issue date:	10/12/1993
From:	Assa R Office of Nuclear Reactor Regulation
To:	Farrar D COMMONWEALTH EDISON CO.
References
GL-92-01, GL-92-1, TAC-M83443, TAC-M83444, TAC-M83446, TAC-M83447, TAC-M83744, TAC-M83745, NUDOCS 9310180062
Download: ML20057F478 (9)

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UNITED STATES NUCLEAR REGULATORY COMMISSION o

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October 12, 1993

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Docket Nos. 50-295, 50-304 STN 50-454, STN 50-455 and STN 50-456, STN 50-457 Mr. D. L. Farrar Manager, Nuclear Regulatory Services Conrnonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515

SUBJECT:

RESPONSE TO GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY, 10 CFR 50.54(f)," ZION STATION, UNITS 1 AND 2, BYRON STATION, UNITS 1 AND 2, BRAIDWOOD STATION, UNITS 1 AND 2 (TAC NOS. M83744, M83745, M83443, M83444, M83446, AND M83447)

The subject Generic Letter (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 CFR Part 50, (2)

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

By letter dated July 2,1992, Commonwealth Edison Company (CECO) 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 your response and has determined that additional information is needed.

Enclosed is a request for additional information (RAI). We request that the response to the RAI be provided within 45 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.

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 1400]g' ybw n;p g gyFf* M M b

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i Mr. D. L. Farrar d the time required to implement actions required by the regulations. This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.

Sincerely, Origir,al Siped Ey:

Ramin R. Assa, Acting Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page DISTRIBUTION:

Docket File NRC & Local PDRs PDIII-2 r/f J. Roe J. Zwolinski J. Dyer C. Moore R. Assa C. Shiraki J. Stang OGC ACRS (10)

B. Clayton RIII D. Mcdonald 14 B 2 B. Elliott Lh:PkII-2 0FC PM:PDIII-2 PM:PDIII-21 D:PDIII-2 NAME bbORE RASSAh CSHIRAKI b JDYER M h/})/93 10 /11/93 10 / tM93

/0//493

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/ /93 DATE

/Ed/NO

[YES/)i0 YESkO)

YES/N0 YES/NO COPY (YES)/NO E

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Mr. D. L. Farrar cc:

Mr. William P. Poirier U. S. Nuclear Regulatory Commission Westinghouse Electric Corporation Byron / Resident Inspectors Office Energy Systems Business Unit 4448 North German Church Road Post Office Box 355, Bay 236 West Byron, Illinois 61010-9750 Pittsburgh, Pennsylvania 15230 Ms. Lorraine Creek Joseph Gallo, Esquire Rt. 1, Box 182 Hopkins and Sutter Manteno, Illinois 60950 888 16th Street, N.W., Suite 700 Washington, D.C.

20006 Mrs. Phillip B. Johnson 1907 Stratford Lane Regional Administrator Rockford, Illinois 61107 U. S. NRC, Region III 799 Roosevelt Road, Bldg. #4 Douglass Cassel Esquire.

Glen Ellyn, Illinois 60137 17 East Monroe Street, Suite 212 Chicago, Illinois 60603 Hs. Bridget Little Rorem Appleseed Coordinator Chairman 117 North Linden Street Will County Board of Supervisors Essex, Illinois 60935 Will County Board Courthouse Joliet, Illinois 60434 Mr. Edward R. Crass Nuclear Safeguards and Licensing George L. Edgar Division Newman & Holtzinger, P.C.

Sargent & Lundy Engineers 1615 L Street, N.W.

55 East Monroe Street Washington, D.C.

20036 Chicago, Illinois 60603 Commonwealth Edison Company U. S. Nuclear Regulatory Commission Byron Station Manager Resident Inspectors Office 4450 North German Church Road Rural Route #1, Box 79 Byron, Illinois 61010 Braceville, Illinois 60407 Illinois Dept. of Nuclear Safety Mr. Ron Stephens Office of Nuclear Facility Safety Illinois Emergency Services 1035 Outer Park Drive and Disaster Agency Springfield, Illinois 62704 110 East Adams Street Springfield, Illinois 62706 Commonwealth Edison Company Braidwood Station Manager Robert Neumann Rt. 1, Box 84 Office of Public Counsel Braceville, Illinois 60407 State of Illinois Center 100 W. Randolph, Suite 11-300 Chairman, Ogle County Board Chicago, Illinois 60601 Post Office Box 357 Oregon, Illinois 61061

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Mr. D. L. Farrar CC:

Michael I. Miller, Esquire Mr. Joe Bauer, NLA Sidley and Austin Nuclear Regulatory Services One First National Plaza Commonwealth Edison Company Chicago, Illinois 60603 Executive Towers West III, Suite 500 1400 OPUS Place Dr. Cecil Lue-Hing Downers Grove, Illinois 60515 Director of Research and Development Metropolitan Sanitary District Attorney General of Greater Chicago 500 South 2nd Street 100 East Erie Street Springfield, Illinois 62701 Chicago, Illinois 60611 Phillip Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Mayor of Zion Zion, Illinois 60099 U.S. Nuclear Regulatory Commission Resident Inspectors Office 105 Shiloh Blvd.

Zion, Illinois 60099 EIS Review Coordinator Environmental Protection Agency Region V 230 S. Dearborn Street Chicago, Illinois 60604 i

i ENCLOSURE l

REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 92-01 i

ZION 1 f

Ouestion 2a in GL 92-01 The response to GL 92-01 indicates that the end of license (E0L) upper shelf-energy (USE) for limiting beltline weld WF-70 will fall below the screening criterion of 50 ft-lbs. NRC is currently reviewing a USE equivalent margins analysis for Zion 1 and 2 which covers level A & B conditions. A B&WOG report for levels C & D (BAW-2178P) is also being reviewed by NRC. The licensee i

should confirm that the combination of these two topical reports will be used as the licensing basis to demonstrate that all beltline welds will meet the USE requirements of Appendix G to 10 CFR Part 50.

Ouestion 2b in GL 92-01 The. response to GL 92-01 shows an unirradiated RT of +18'F for weld WF-70.

References I and 2 indicate that the unirradiatediT,,, for WF-70 is 0*F while Reference 3 cites a value of -56'F.

Explain this discrepancy and provide one value of unirradiated RT,oy for WF-70.

Provide the basis for the reported j

value.

The response to GL 92-01 does not contain Ni and P contents, or the r

unirradiated upper shelf energy for forging ANA 102.

Provide this information.

l References 1.

Letter from D. R. Muller (USNRC) to L. Farrar (Ceco), " Zion Nuclear Power Station, Units 1 and 2--Material Properties for Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events, r

10 CFR 50.61," May 7, 1987.

2.

Memorandum from J. E. Richardson (USNRC) to D. R. Muller (USNRC), " Zion Station Units 1 and 2--Copper Content of Reactor Vessel Beltline Welds for PTS Evaluation," January 28, 1988.

3.

Letter from T. W. Simpkin (Ceco) to T. E. Murley (USNRC), " Zion Station Units 1 and 2, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events - 10 CFR 50.61, Response to NRC Request for Additional Information," September 1,1993.

ZION 2 t

Ouestion 2a in GL 92-01 l

The response to GL 92-01 indicates that the EOL USE for limiting beltline weld i

SA-1769 will fall below the screening criterion of 50 ft-lbs. NRC is currently reviewing a USE equivalent margins analysis for Zion, Units I and 2, which covers level A & B conditions. A B&WOG report for levels C & D (BAW-2178P) is also being reviewed by NRC.

The licensee should confirm that the combination of these two topical reports will be used as the licensing j

e

. basis to demonstrate that all beltline welds will meet the USE requirements of Appendix G to 10 CFR Part 50.

The response to GL 92-01 shows unirradiated upper shelf energy values for limiting beltline plates B8029-1, C4007-1, and 8006-1 that do not match those given in Table 4-4 of WCAP-12396:

Material GL 92-01 WCAP-12396 B8029-1 91 81 C4007-1 91 94 88006-1 91 89 Explain this discrepancy, and provide one value each for the unirradiated upper shelf energy for these materials.

Provide the bases for the reported values.

The response to GL 92-01 does not provide a v lue of unirradiated upper shelf energy for forging ZV 3855.

Provide unirradiated USE data and pro.jected USE at EOL for this forging.

If the unirradiated Charpy USE for this forging is not available, provide the unirradiated Charpy USE and analysis from a forging that was fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that the forging will meet the requirements of Appendix G to 10 CFR Part 50.

rwestion 2b in GL 92-01 The response to GL 92-01 shows an unirradiated RT of +18'F for weld WF-70.

References 1and2indicatethattheunirradiatediT for WF-70 is 0*F while Reference 3 cites a value of -56*F.

Explain this discrepancy, and provide one er value of unirradiated RT, for WF-70.

Provide the basis for the reported value.

The response to GL 92-01 provides an unirradiated RT of 5*F for welds SA-1769andWF-29,whileinTable4-4ofWCAP-12396UIeunrradiatedRT.,

i values for these welds are given as 0*F.

Explain this discrepancy, and provide one value each for the unirradiated RT., for these welds.

Provide the bases for the reported values.

In the response to GL 92-01 a fluence value for the lower shell to dutchman circumferential weld WF-154 was not provided.

The E0L fluences for the other Zion, Unit 2, beltline materials were obtaing frog Reference 1.

Provide the EOL fluence for weld WF-154 if it exceeds 10 n/cm.

Reference M. J. DeVan, et al, "B&W Owners Group Response to Generic Letter 92-01,"

BAW-2166, Babcock and Wilcox, Lynchburg, Virginia, June 1992.

i.

l.,

i BRAIDWOOD 1 & 2 Question 2a in GL 92-01 The response to GL 92-01 indicates that the unirradiated USE for limiting beltline weld WF-562 is 70 ft-lbs, whereas 78 ft-lbs is the reported unirradiated USE for this weld in WCAP-12685. Resolve this discrepancy and

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report one value for the unirradiated USE for weld WF-562.

Provide the basis for the value reported.

i The response to GL 92-01 provided unirradiated USE data for weld WF-562 and the upper shelf forging.

beltline materials were not provided:However, unirradiated USE data for the following the upper circumferential weld, and the lower circumferential weld.the lower shell t

Provide unirradiated USE data and projected USE at E0L for the three aforementioned materials.

If the unirradiated Charpy USE for these materials is not available, provide the unirradiated Charpy USE and analysis from welds and-forgings that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that the forgings and welds will meet the requirements of Appendix G to 10 CFR Part 50.

If this can not 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.

BYRON 1 Ouestion 2a in GL 92-01 The response to GL 92-01 shows that the unirradiated USE for limiting beltline weld WF-336 is 78 ft-lbs.

WCAP-11651 reports USE values of 77 ft-lbs in Table 4-3 and 74 ft-lbs in Table 5-5 for weld WF-336.

Provide one value for the unirradiated USE for weld WF-336.

There are no unirradiated USE data provided for beltline welds WF-501 and WF-472.

Provide unirradiated USE data and projected USE at EOL for these welds.

If the unirradiated Charpy USE for these welds is not available, provide the unirradiated Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that the welds will meet the requirements of Appendix G to 10 CFR Part 50.

If this can not 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.

Question 2b in GL 92-01 The response to GL 92-01 indicates two chemical compositions for circumferential weld WF-336 that differ significantly.

Provide one chemical composition for weld WF-336 and the basis for that composition.

_4_

There are discrepancies between the unirradiated RT values reported in the response to GL 92-01 and Reference (1) for forging Id3J218 and weld WF-501:

Material GL 92-01 Reference 1 Forging 123J218 30*F 20*F Weld WF-501 0*F 10*F Explain this discrepancy and provide one value each for unirradiated RT, for these materials.

Provide the bases for the reported values.

Reference Letter from G.L. Alexander (Ceco) to H.R. Denton (USNRC), " Zion Station, Units 1 and 2; Byron Station Units 1 and 2; Braidwood Station Units 1 and 2; Pressurized Thermal Shock," January 17, 1986.

~

BYRON 2 Ouestion 2a in GL 22-01 The response to Gl M-01 shows an unirradiated USE of 72 ft-lbs for limiting -

beltline weld WF-U i ehich is listed as the surveillance weld. The unirradiated USE f:< !his weld is reported in WCAP-12431 as 80 ft-lbs in Table 4-4 and 67 ft-lbs m ;able 5-5.

Explain this discrepancy and provide one value for the unir 2diated USE to characterize the subject weld.

Provide the basis for the value reported.

The response to GL 92-01 indicates that the upper circumferential (WF-562) and lower circumferential (WF-614) welds are in the beltline. However, no unirrar

?d USE data are provided. Provide unirradiated USE data and projected USE at E0L for these welds.

If the unirradiated Charpy USEs for these welds are not available, provide the unirradiated Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that the welds will meet the requirements of Appendix G to 10 CFR Part 50.

If this can not 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.

Question 2b in GL 92-01 The response to GL 92-01 contains two chemical compositions for weld WF-447.

Provide one chemical composition and provide the basis for that composition.

1

o Mr. D. L. Farrar the time required to implement actions required by the regulations.

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

Sincerely, Orifnal s'enxi Ey:

Ramin R. Assa, Acting Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page DISTRIBUTION:

Docket File NRC & Local PDRs PDIII-2 r/f J. Roe J. Zwolinski J. Dyer C. Moore R. Assa C. Shiraki J. Stang OGC ACRS (10)

B. Clayton RIII D. Mcdonald 14 B 2

-B.

Elliott Lk:PhJII-2 0FC PM:PDIII-2 PM:PDIII-21 D:PDIII-2 NAME N0bRE RASSAh CSHIRAKI b JDYER M

\\D!)/93 10/11/93 to / t}493

/0//b/93

/ /93

/ /93 DATE

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COPY (YES'/NO

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