ML18003A304
| ML18003A304 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/29/1978 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7812130383 | |
| Download: ML18003A304 (16) | |
Text
Carolina Power &'ight Company
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November 29, 1978 Mr. James P. O'Reilly, Director Nuclear Regulatory Commission Region II 101 Marietta Street, NW Atlanta, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NOS. 1, 2, 3 AND 4 DOCKET NOS. 50-400, 50-401, 50-402, AND 50-403
'NRC IE BULLETIN 78-12
Dear Mr. O'Reilly:
Your letter of September 29, 1978 transmitted IE Bulletin 78-12 concerning reactor pressure vessel weld material.
We have been working with our NSSS vendor, Westinghouse, to provide a response to the request for information contained in the Bulletin.
We understand from Westinghouse that they have been working with the NRC to clarify the requirements of the subject bulletin.
The clarification was necessary due to the number of reactor vessels involved, the sheer volume of the records, and the potential adverse impact on the vendor shops if the data requested were provided without limitation.
Westinghouse has informed us that their discussions with the NRC revealed that other NSSS suppliers and reactor vessel vendors had given the NRC similar feedback.
As a result of the feedback received on the subject bulletin, the NRC recently indicated to Westinghouse that the bulletin will be clari-fied in the near future to allow more time for the utilities to respond (currently estimated to be 8 to 10 months) and to permit a more structured and limited response.
It had been our understanding that the NRC had intended to issue a letter by November 17, explaining that there are ongoing discussions with the NRC and with vendors on the best approach to resolve the weld wire concerns, and that the 60-day requirement would be waived.
We have now been informed that the NRC staff is considering a revised bulletin.
336 Fayettevitte Street
~ P. O. Box 1551
~ Raleigh, N. C. 27602 f8'4
aran P y r
Mr. James P. O'Reilly November 29, 1978 In view of the evident uncertainty in the response requested, we are requesting a 60-day extension for response to IE Bulletin 78-12.
In the event this bulletin is revised or reissued, and a new response date established, we will comply with that schedule.
Yours very truly, M. A. McDuffie Senior Vice President Engineering
& Construction MAM/1c cc:
U.
S. Nuclear Regulatory Commission Office of Inspection
& Enforcement Division of Reactor Operations Inspection Washington, D.
C.
20555
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303
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In Reply Refer To:
RII:JPO 50-325, 50-324 50-400, 50-401 50-402, 50-403 50-261
<OV 24 197e Carolina Power and Light Company ATTN:
Hr. J.
A. Jones Executive Vice President Engineering, Construction and Operation 336 Fayetteville Street Raleigh, North Carolina 27602 Gentlemen:
Enclosed is a supplement (IE Bulletin No.78-12A) to IE Bulletin No. 78-12 which requires action by you with regard to your power reactor facility(ies) with an operating license or a construction permit.
I Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978
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ames P. O'Reilly D
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Carolina Power and Light Company cc wlencl:
A. C. Tollison, Jr.
Plant Manager Box 458 Southport, North Carolina 28461 R. Parsons, Pro5ect Manager Shearon Harris Nuclear Power Plant P. 0.
Box 101 New Hill, North Carolina 27562 R. B. Starkey, Plant Manager P. 0.
Box 790 Hartsville, South Carolina 29550
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 24, 1978 IE Bulletin No.78-12A ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 2978, and the two documents should. be considered together.
Bulletin 78-3.2 described the use of weld wire that failed to meet all specified chemical properties in welds of twelve identified reactor pressure vessels.
Use of the atypical weld material in vessel weldments causes them to have higher than normal. nil-ductility transition temperature characteristics which. in turn requires more conservative pressure/tempera-ture operating limits.
Bulletin 78 12 was issued for the purpose of verifying that similar atypical weld. material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabrication.
Recognizing that the scope of the record review required is extensive and time consuming, and to assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being modified.
Action To Be Taken By Licensees and Permit Holders:
For all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having atypical weld material1:
The twelve nuclear units identified as having possible atypical pressure vessel weldments are:
Three Mile Island Unit Nos.
1 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No. l, Oconee Unit No. 3, Rancho Seco Unit No. 1, Midland Unit No. 1, Quad Cities Unit No. 2, Browns Ferry Unit No. 3., Turkey Point Unit No.
4 and Zion Unit Nos. 1 and 2.
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IE Bulletin No.78-12A November 24, 1978 1.
Provide all information available on weld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items 1c, ld, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.)
This information may be provided to NRC through the vessel manufacturers or suppliers as appropriate to prevent duplication of data.
'I 2.
Correlation of specific heat, lot or batch to specific weldments in specific vessels is not required at this time.
(Last sentence of Item 2c, Bulletin 78-3.2.)
- However, each licensee is required to Verify that the weld materials information provided to the NRC under Item Z does in fact cover each reactor vessel for which the licensee is responsible.
3.
Responses to item 3. above shall be submitted in writing within
&20 days of the date of this Bulletin supplement.
Reports should be submitted to the Director of the appropriate NRC Regional Office and y, copy should be forwarded to the U.S. Nuclear Regulatory Coapnj,ssgon, Office of Xnspection and Enforcement, Division of geyctor Construction Inspection, Washington, D.C.
20555.
Approyed by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
2 Weld material information submitted will be evaluated by NRC.
Requests for further information will be dependent upon results of these evalua-tions.
Additgonal requests or instructions will be issued following these evaluations.
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IE Bulletin No. 78-l2A Date:
November 24, l978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject No.
Date Issued Issued To 78-Ol 78-O2 Flammable Contact-Arm Retainers in G.E.
CR120A Relays Terminal Block Qualification 1/16/78 1/30/78 All Power Reactor Facilities vith an OL or CP All Power Reactor Facilities with an OL or CP 78-o3 78-O4 78-o5 78-o6 78-O7 Potential Explosive Gas Mature Accumula-tions Associated with BWR Qffgas System Operations Environmental Quali-fication of Certain
/tern 'Mounted Limit Switches Inside Reactor Containment Malfunctioning of Circuit Breaker Auxiliary Contact gechanism-General Model CRl05X
'Defective Cutler-
- Hsmmer, Type M Relays With DC Coils Protection afforded by Air-Line Respirators and Supplied-Air Hoods 2/8/78 2/21/78 4/14/78 5/3l/78 6/12/78 All BWR Power Reactor Facilities with an OL or CP All Power Reactor
'Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities vith an OL or CP All Power Reactor Facilities with an OL, all class E and F
Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees Enclosure l Page 1 of 2
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IE Bulletin No.78-12A November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Sub) ect No.
Date Issued Issued To 78-08 Radiation Levels from
'Fuel Element Transfer Tubes BWR Drywell Leakage Paths Associated with.
Inadequate D~ell Closures.
6/12/78 6/Z4/78 All Power and Research Reactor Facilities with a Fuel Element transfer tube and an OL.
All BWR Power Reactor Facilities with an OL or CP 78-ZO Bergen-Paterson Qdrauli,c Shock Suppressor Accumulator Spring Coils Examination of Mark I Containment Torus Welds 6/27/78 7/21/78 All BWR Pover Reactor Facilities with an OL or CP BWR Power Reactor Facilities for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee
/typical Weld Material 9/29/78
$m Pesctqr Pressure gessel Welds
'Failures in Source Heads 3.0/27/78 of Koy-Ray, Inc,, Gauges Models 7050,
- 7050B, 7051 7Q51B, 7060,
- 7060B, 7061 and 7061B All Paver Reactor Facilities with an OL or CP All General and Specific Licensees with Kay-Ray Gauges Page 2 of 2
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