ML20003H978

Application for Amend to License DPR-57,consisting of Proposed Changes to App a Tech Specs Table 4.6-1 for Examination Requirements of ASME Section XI Category B Reactor Pressure Vessel Welds.Class III Fee Encl

ML20003H978
Person / Time
Site:	Hatch
Issue date:	04/28/1981
From:	Widner W GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20003H979	List: ML20003H978 ML20003H980
References
TAC-43820, NUDOCS 8105080275
Download: ML20003H978 (2)

Text

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, 333 Pm1mcet Avenue AWa Geoq a 30308 Ten hono 404 526 E526 Yalcg teess Pc-t 0 t ce Oc= 4545 Aranta Gma a 30302 GeorgiaPower April 28, 1981 tm soonem ewrm system o Present and General Manager

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U. S. Nuclear Regulatory Comission fJ 0\

Office of Nuclear Reactor Regulation Washington, D. C. -4 g [

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OPERATING LICENSE DPR-57 /A% /'

e EDWIN I. HATCH NUCLEAR PLANT UNIT 1 p

INSERVICE INSPECTION TECHNICAL SPECIFICATIONS Gentlemen:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59 (c)(1), Georgia Power Company hereby proposes an amendment to the Unit 1 Technical Specifications (Appendix A to the Operating License). The proposed amendment will incorporate revised sp=cifications for the examination requirements for ASME Section XI Category B reactor pressure vessel (RPV) welds during the first 5-year inspection interval. Enclosed is the proposed change to the Technical Specifications.

The propostd change to the Technical Specifications is submitted for emergency relief from the first 5-year inspection interval requirements as identified in Technical Specifications Table 4.6-1. While compiling the Five-Year Inservice Inspection Report (per Technical Specification 4.6.K) it was noted that the RPV bottom head welds had not been examined as required by Technical Specifications for the first 5-year inspection interval. The commitment was made in the report submitted to NRC Region II to perform the examinations during the 1981 maintenance / refueling outage if radiation levels permitted. In addition, the NRC Hatch Project Manager was notified and advised that the examinations had not been performed and that emergency relief from Technical Specifications might be required if radiation levels prohibited examination.

Radiation surveys of the RPV bottom head area have been made during the maintenance / refueling outage currently in progress. The radiation exposure (5 man-Rem estimated) that examination team personnel would receive in performing the examination of one (1) RPV bottom head circumferential weld and four (4) meridonal welds prohibits their examination. The examinations would have to be performed using manual ultrasonic techniques as sJitable mechanized ultrasonic examination techniques do not currently exist for the examination of the RPV bottom head welds. It should be noted that the welds were examined during the pre-service inspection revealing no rejectable indications.

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U. S. tOclear Regulatory Commission Office of Nuclear Reactor Regulation April 28,1981 Page Two Although the proposed Technical Specification changes would delete the examination requirement 'for ASME Category B welds during the first 5-year inspection interval, they would still be required to be examined by the end of the 10-year inspection interval. Examination of ASME Category B welds at or near the end of the 10-year inspection interval is allowed by ASME Section XI Code, IWA-2400 and Table IWB-2500. In addition, examination of the RPV bottom head welds at the end of the 10-year inspection interval will allow adequate time for the development of RPV bottom head mechanized ultrasonic examination techniques.

As previously stated, the proposed changes to the Unit 1 Technical Specifications is being submitted for emergency relief. .You are respectfully requested to review, approve, and respond to the proposed change by May 11, 1981.

The Plant Review Board and Safety Review Board have reviewed the proposed change to the Unit 1 Technical Specifications and have concluded that no changes in plant operation with the ASME Category B weld inspection requirements as revised by this submittal are required to maintain existing margins of safety for the reactor pressure vessel. Thus, the proposed change to the Technical Specifications does not increase the probability of occurrence or consequences of a previously analyzed accident or malfunction of equipment important to safety, nor has the possibility of a previously unanalyzed accident or malfunction of equipment been created. Margius of safety have not been decreased.

As discussed in Attachment 1, the - proposed change to the Unit 1 Technical Specifications has been evaluated to be a single Class III amendment. Enclosed as the amendment fee is a check for $4,000.00.

W. A. Widner states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf uf Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER COMPANY l

By: M// 7# w W. A. Widner u/

W Sworn to and subscribed before me

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is 28th day of April, 1981.

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Attachments xc: M. Manry R. F. Rogers, III Director, NRC Region II l