ML20235S873

Safety Evaluation Re First 10-yr Interval Inservice Insp Program.Relief Granted from Exam & Testing Requirements of ASME Code & Alternate Methods Imposed Through Document

ML20235S873
Person / Time
Site:	Fermi
Issue date:	10/06/1987
From:	Office of Nuclear Reactor Regulation
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ML20235S866	List: ML20235S863 ML20235S873 ML20235S883
References
NUDOCS 8710090167
Download: ML20235S873 (4)

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kQ CEGO s . # o,, UNITED STATES

! n NUCLEAR REGULATORY COMMISSION

, { ;E WASHING TON, D. C. 20555 l

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM DETROIT EDISON COMPANY FERMI-2 DOCKET NO. 50-341

1.0 INTRODUCTION

The Technical Specifications for the Fermi-2 plant state that the surveillance requirements for inservice inspection and testing of 3 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, 2 and 3 components shall be applicable as follows: j l Inservice Inspection of ASME Code Class 1, 2 and 3 components shall be l performed in accordance with Section XI of the ASME Code and applicable l Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Coramission pursuant to 10 CFR 50, 1 Section 50.55a(g)(6)(i).

i Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2 and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth

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in the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first ten year. interval shall comply with the requirements in the latest edition and addenda of Section XI of l

the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date j twelve months prior to the date of issuance of the operating license, subject to the limitations and modifications listed therein. The components (including supports) may meet the requirements set forth in  !

subsequent editions and addenda of the ASME Code incorporated by reference '

in 10 CFR 50.55a(b) subject to the limitations and modifications listed l therein. '

Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance to an examination requirement of Section XI of the ASME Code is impractical for its facility, information is submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and impose alternative requirements as it determines are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed.

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4 g On April 2, 1987, the Detroit Edison Company (the licensee) submitted the first ten year Interval Inservice Inspection. Program Plan (Revision 0, Change 2) for the Fermi-2 plant, to meet the requirements of the 1980 Edition, Winter 1981 Addenda, except that the extent of examination for Class 2 piping welds will be determined by the 1974 Edition, Summer 1975 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code. The NRC staff and its- contractor, Idaho National Engineering Laboratory (INEL),

have evaluated the first ten year Interval Inservice Inspection Program Plan, and the information related to the requests for relief from certain

. ASME Code requirements which the licensee determined to be impractical to perform at the Fermi-2 plant during the first ten year. inspection interval.

2. 0 EVALUATION The Inservice Inspection Program Plan was evaluated for (a) compliance with the appropriate ASME Code edition, (b) acceptability of the examination sample, (c) exclusion criteria and (d) compliance with the Commission's augmented inspection programs., The requests f8r relief from the requirements of INEL.Section XI of the ASME Code were reviewed and evaluated by our contracto The INEL Technical Evaluation Report (TER), EGG-SD-7782, August, 1987, is attached. The TER includes an evaluation of the Inservice Inspection Program Plan and the requests for relief from Section XI requirements. The NRC staff has reviewed the. TER and concurs with the evaluation an mendation, except in the case of the reactor vessel welds, Category B-A.

The review procedure for the by the staff examination at this time. of the reactor vessel welds is under l A summary of the evaluation and the determination made by the NRC staff in regard to the licensee's relief requests is shown in Table 1.

3.0 CONCLUSION

We conclude that relief granted from the examination and testing require-ments of the ASME Code, and the alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structural integrity, and that granting this relief from ASME 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 were interestonconsidering imposed the burden that could result if the requirements the Fermi-2 plant.

Date: October 6, 1987 l Principal Contributor: F. Litton i

Attachment:

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