ML16131A466

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Requests Addl Info to Complete Review Re Plant Response to GL 92-01,rev 1
ML16131A466
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 10/08/1993
From: Wiens L
Office of Nuclear Reactor Regulation
To: Hampton J
DUKE POWER CO.
References
GL-92-01, GL-92-1, TAC-M83734, TAC-M83735, TAC-M83736, NUDOCS 9310190059
Download: ML16131A466 (4)


Text

October 8, 1993 Docket Nosy 50-269, 50-270 and 50-287 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679

Dear Mr. Hampton:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING OCONEE RESPONSE TO GENERIC LETTER 92-01, REVISION 1 (TAC NOS. M83734, M83735, AND M83736)

The NRC staff is reviewing your response to Generic Letter (GL) 92-01 for Oconee Units 1, 2, and 3. We find that further information, as indicated in the enclosure, is required to complete our review. Your response to the enclosed questions is requested within 45 days of the date of this letter. If you have any questions regarding this matter, I may be contacted at (301) 492-1495.

This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

Sincerely, Original signed by Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -

I/II Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/enclosure:

See next page DISTRIBUTION:

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Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:

Mr. A. V. Carr, Esquire Mr. M. E. Patrick Duke Power Company Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.

Mr. Alan R. Herdt, Chief Washington, DC 20005 Project Branch #3 U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum 101 Marietta Street, NW. Suite 2900 Babcock & Wilcox Atlanta, Georgia 30323 Nuclear Power Division Suite 525 Ms. Karen E. Long 1700 Rockville Pike Assistant Attorney General Rockville, Maryland 20852 North Carolina Department of Justice Manager, LIS P. 0. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. G. A. Copp Licensing - ECO50 Senior Resident Inspector Duke Power Company U. S. Nuclear Regulatory Commission P. 0. Box 1006 Route 2, Box 610 Charlotte, North Carolina 28201-1006 Seneca, South Carolina 29678 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County Walhalla, South Carolina 29621

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE LICENSEE RESPONSE TO GENERIC LETTER 92-01 FOR OCONEE UNITS 1, 2, AND 3 The licensee's response to Generic Letter (GL) 92-01 is contained in the Babcock & Wilcox report, BAW-2166, "B&W Owners Group Response to Generic Letter 92-01," June 1992. Based on the review of BAW-2166, the staff has the following comments and requests for additional information under Questions 2.a and 2.b in GL 92-01:

OCONEE 1 (TAC No. M83734)

1.

The licensee reported unirradiated upper shelf energy (USE) for limiting materials only. Provide unirradiated USE for all beltline materials.

2.

The heat number for the weld wire of weld SA-1073 is indicated as 1P0962 in Table 5 of BAW-2166; however, Table 1 of BAW-1500 indicates the heat number as 1P9062. Explain the discrepancy and provide the correct weld wire heat number for SA-1073.

3.

Table 5 of BAW-2166 indicates that the heat number of weld WF-9 is 72245. However, in BAW-1511P and BAW-1543 reports, weld WF-9 is not included under heat number 72245. Resolve the discrepancy, confirm the heat number for the weld wire of weld WF-9, and identify whether WF-9 is in the beltline region where the neutron fluence at end of life is greater than 1.OE17 n/cm2 Also, Weld WF-9 is listed in Tables 4, 7, and 10 but not in Table 3 of BAW-2166. Resolve the discrepancy.

4.

The GL 92-01 response indicates that the USE at end of license for weld SA-1229 will fall below the screening criterion of 50 ft-lb. The staff is reviewing two topical reports by Babcock & Wilcox owners group (B&WOG) on USE equivalent margin analysis regarding beltline welds with low USE values for Levels A and B (BAW-2192P) and for Levels C and D (BAW-2178P). The licensee should confirm if these two topical reports will be used as its licensing bases to demonstrate that all beltline welds in the Oconee Unit 1 reactor vessel will meet the USE requirements of Appendix G, 10 CFR 50.

OCONEE 2 (TAC No. M83735)

1.

The licensee reported unirradiated USE for limiting materials only.

Provide unirradiated USE for all beltline materials.

2.

The 92-01 response indicates that the USE at end of license for weld WF 25 will fall below the screening criterion of 50 ft-lb.

The licensee should confirm if the two aforementioned B&WOG topical reports, BAW 2192P and BAW-2178P, will be used as its licensing bases to demonstrate that all beltline welds in the Oconee Unit 2 reactor vessel will meet the USE requirements of Appendix G, 10 CFR 50.

-2 OCONEE 3 (TAC No. N83736)

1.

The licensee reported USE for limiting materials only. Provide unirradiated USE for all beltline materials.

2.

There is no copper content reported for lower belt forging 4680 in Table 7 of BAW-2166. Provide the copper content and its bases.

3.

The GL 92-01 response indicates that the unirradiated USE at end of license for weld WF-67 will fall below the screening criterion of 50 ft lb. The licensee should confirm if the two aforementioned B&WOG topical reports, BAW-2192P and BAW-2178P, will be used as its licensing bases to demonstrate that all beltline welds in the Oconee Unit 3 reactor vessel will meet the USE requirements of Appendix G, 10 CFR 50.