ML18037A520
| ML18037A520 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/20/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18037A514 | List: |
| References | |
| NUDOCS 9310260372 | |
| Download: ML18037A520 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555.0001 Enclosure SAF U
0 E OFF C
OF NUC A
R ACTO R GULATION OF THE SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN FOR TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 2 DOCKET NUMBER 50-260
- 1. 0 INTRODUCTION Technical Specification (TS) 4.6.G. 1 Browns Ferry Nuclear Plant (BFN), Unit 2>
states that inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components shall be
= performed in accordance with Section XI of the ASME Boiler and Pressure Vesse]
Code and applicable Addenda as required by 10 CFR 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and
- safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
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 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 each 10-year interval comply with the requirements in the latest edition-and addenda of Section XI of the ASME Code incorporated by reference ta.'10 CFR 50;55a(b) on the date twelve months prior to'the start of the 120-month inspection interval, 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 therein.
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME 9310260372 PDR ADOgK 05000260 P
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Code requirement.
After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i),
the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, 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.
The Tennessee Valley Authority (TVA, the licensee) prepared the Second 10-Year Interval Inservice Inspection (ISI) Program Plan for Browns Ferry Nuclear Plant, Unit 2, Revision 1, to meet the'equirements of the 1986 Edition of Section XI of the ASHE Boiler and Pressure Vessel Code, with the following exception.
The extent of examination for Examination Category B-J welds is determined by the requirements of the 1974 Edition, through Summer 1975
- Addenda, as permitted by 10 CFR 50.55a(b).
The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), evaluated the Second 10-Year Interval Inservice Inspection Program Plan for Browns Ferry Nuclear Plant, Unit 2, through Revision 1, including additional information related to this program and requests for relief from certain ASHE Code requirements.
- 2. 0 EVALUATION The ISI Program Plan has been evaluated for (a) application of the correct Section XI Code edition and addenda, (b) compliance with examination and test
.requirements of Section XI, (c) acceptability of the examination
- sample, (d) compliance with prior ISI commitments made by the licensee, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from certain Section XI Code requirements deemed impractical by the licensee.
Based on this evaluation, the staff has determined that the licensee's ISI Program Plan is acceptable and in compliance with 10 CFR 50.55a(g)(4).
The ISI program description and information submitted by the licensee, including requests for code relief, have been evaluated by INEL and documented in Technical Evaluation Report (TER)
EGG-HS-10725 dated Hay 1993.
The staff concurs with and adopts the findings and recommendations contained in the subject TER.
- 3. 0 CONCLUSION The staff concludes that the Second 10-Year Interval Inservice Inspection Program Plan for Browns Ferry Nuclear Plant, Unit 2, through Revision 1, is acceptable and complies with 10 CFR 50.55a(g)(4) and TS 4.6.G. l.
In addition, the staff also concludes with respect to Request for Relief No. ISI-2-1, the requirements of the ASHE code are impractical, and that relief from the code requi rements may be granted. as requested.
The relief granted is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Principal Contributor:
Tom K. HcLellan Date:
October 20, 1993
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