ML20137M531

SER Supporting 850718 & 1127 Requests for Reconsideration of Relief from Requirements of Section XI of ASME Code Re Exam of Supports on ASME Piping

ML20137M531
Person / Time
Site:	Hatch
Issue date:	01/21/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20137M512	List: ML20137M507 ML20137M531
References
TAC-60203, NUDOCS 8601280295
Download: ML20137M531 (4)

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SAFETY EVALUATION BY OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RECONSIDERATION OF DENIED RELIEF REQUEST FROM FIRST TEN-YEAR INSERVICE INSPECTION REQUIREMENTS GEORGIA POWER COMPANY HATCH NUCLEAR PLANT UNIT 1 DOCKET NO. 50-321 DIVISION OF BWR LICENSING I INTRODUCTION Technical Specification 3.6.k for the Hatch Nuclear Power Plant Unit I requires that inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g) except'where specific written relief has been granted by the Commission.

We have reviewed Georgia Power Company's (GPC/ licensee) first ten year interval inservice inspection program and GPC letter dated July 18, 1985.

The GPC letter requested relief for Hatch Unit 1 from certain requirements of the 1980 ASME Code Section XI with Addenda through Winter 1980. We provided a Safety Evaluation (SE) on September 11, 1985, in which we concluded that some of the relief requests should be granted, some conditionally granted and others denied where the necessary findings of impracticality could no,t be made.

By letter dated November 27, 1985, the licensee provided additional information and requested reconsideration of one of the relief requests denied previously.

GPC has implemented at Hatch Unit 1, effective January 1, 1984, an inservice inspection program based on the 1980 ASME Code Section XI with Addenda through Winter 1980. Prior to this time, inservice inspections at the plant were performed in accordance with earlier editions of the Code.

Specifically for the first 40 month inspection period the inspections were performed in accordance with the 1971 Edition of the Code with Addenda through

! Summer 1972. For the second 40 month inspection period, the inservice inspections were performed in accordance with the 1974 Edition of the Code with Addenda through Summer 1975.

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In order to complete the first ten year inservice inspection interval at Hatch

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Unit 1, the licensee has requested that a previously denied relief request be reconsidered on the basis of information supplied by letter of November 27, 1985.

II RELIEF REQUESTS Relief is requested from examining supports on ASME Class 1 lines, 2-inch nominal pipe diameter and less, during the completion of the Hatch Unit No. 1 first 10 year interval. Also, supports on ASME Class 2 and 3 lines 4-inch nominal pipe diameter and less will not be examined.

III CODE REQUIREMENT IWF-2510 of the 1980 Edition of ASME Section XI requires that visual examinations be completed on these supports of components, that are required to be examined under IWB, IWC, or IWD.

III 1. Class 1 Components Supports The 1974 Code requires that 25 percent of the welded attachments be examined each 10 year interval. The 1980 Code does not require the examination of support components less than 5/8-inch thick; however, 100 percent of the required examinations must be completed in the 10 year interval.

III 2. Class 2 Component Support The 1974 Edition of the Code requires that a sufficient number of attachment welds be examined in a multiple-stream system such that the total number of welds examined over the 40 year life of the plant is equal to one of the multiple streams of the system. For a single-stream system, 100 percent of the required examinations be performed over the life of the plant. The 1980 Edition does not require the examination of attachment welds less than 3/4-inch thick; however, 100 percent of the required examinations must be completed in each 10 year interval. This scope of examinations has been used i

since January 1,1984, pursuant to the GPC letter dated August 12, 1983 to the NRC.

III 3. Class 3 Component Support Per IWF-2510 of the 1980 Code, component supports selected for visual examinations shall be the supports of those components required to be examined per IWD of the Code. There are no actual examinations performed on Class 3 piping as in Class 1 and 2, only hydrostatic tests.

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IV LICENSEE'S BASIS FOR REQUESTING RELIEF IV 1. Licensee's Examination for Class 1 and 2 Per IWF-2510 of the 1980 Code, component supports selected for visual examination shall be the supports of those components required to be examined per IWB of the Code. For Hatch Unit 1 liquid lines less than 2.21-inches I.D.

and steam lines less than 4.29-inches I.D. are not required to be examined.

IV 2. Class 2 Piping Welds examined (RHR, ECCS, and CHR Systems) 10 CFR 50.55a requires the extent of the examination for these welds to be determined by the 1974 Edition of the Code. This requirement was met as well as selecting high stress and terminal end welds to be more compatible with the 1980 Edition. The 1974 Edition exemptions related to " pressure and temperature" (IWC-1220(a)) and " size" (IWC-1220(d)) were not applied to these welds. Instead, piping welds greater than 1-inch were selected per the 1974 Edition, and will be examined by surface or volumetric means, as appropriate, to the first closed manual or power-actuated isolation valve unless that line has a particular safety function.

IV 3. Remaining Class 2 Piping Welds examined As permitted in 10 CFR 50.55a, GPC elected to select the remaining Class 2 piping welds per the 1974 Edition of the Code. In addition, high stress and terminal- end welds were chosen for compatibility with the 1980 Edition.

IV 4. Licensee's Examination for Class 3 Component supports will be visually examined on all components greater than 4-inches in diameter. In addition, component supports on piping 4-inches and smaller will be examined if that piping provides safety-related cooling water to an ECCS or RHR Pump (including CHR).

V EVALUATION The licensee has analyzed the extent, scope and methods of examination of component supports in the 1974 through 1980 Codes with Addenda. The proposed lines to be examined are a reasonable interpretation of the piping required to be examined by the 1980 Edition with Addenda through Winter 1980 of the Code with Addenda through Winter 1980.

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4 VI CONCLUSION Based upon the above evaluation, the staff concludes that the piping to be examined, the extent of the examination, and the method of examination will provide reasonable assurance of the structural integrity of the component i supports. Therefore, the request for relief should be granted. The staff further concludes that granting relief from the specific code requirements is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest considering the burden that could result if they were imposed upon the facility.

Principal Contributor: B. Turovlin Dated: January 21, 1986

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