ML20246P940

Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp Program

ML20246P940
Person / Time
Site:	Brunswick
Issue date:	05/10/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246P927	List: ML20246P923 ML20246P940 ML20246P967
References
NUDOCS 8905220314
Download: ML20246P940 (2)

Text

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, ) wasmucrow, o. c. 20sse SAFETY EVALUATION BY THE OFFICE OF NUCLEAR PEACTOR REGULATION.

RELATED TO THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM'-

CAROLINA POWER F. LIGHT COMPANY, et al.

i BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324-

1.0 INTRODUCTION

The Technical Specification for the Gruswick Steam Electric Plant. Units 1 and 2 states that following start of commercial operation inservice inspection of ASME Code Class 1, ~2 and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves 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, Section 50.55a(g), except I where specific written relief has been granted by the Commission pursuant to 10 CFR 50 Section 50.55a(g)(6)(1).

Pursuant to 10 CFR 50.55a(g)(4) ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, ev. cept 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. In addition, inservice examination of components and systems pressure tests conducted during the second ten-year interval shall comply with the requirements in the' latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.554(b) on the date twelve months prior to the start of the second ten-year 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 detemines that conformnce to an examination requirement of Section XI of the ASME Code is not practical for his facility, information is submitted to the Cosmiission 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)(1), 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.

8905220314 890510 PDR ADOCK 05000324 Q PDC i

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The Carolina Power & Light Company (the Ifcensee) prepared the Second Ten-Year Interval Inservice Inspection Program Revision 1, for the Brunswick Steam Electric Plant, Units 1 and 2, to meet the requirements of the ASE Boiler and Pressure Vessel Code,Section XI,1980 Edition, including Winter 1981 Addenda, except that the extent of examination for Code Class 2 piping welds was determined by ASME Code Case N-408,

" Alternative Rules for Examination c,f Class 2 Piping,Section XI, Division 1." The second ten-year interval began on July 10, 1986, and ends on July 10, 1996.

The program was evaluated by the staff and their contractor. Idaho National Engineering Laboratory, for a) compliance with the appropriate ASME Code Section XI Edition and Addenda, b) acceptability of the examination sample, c) exclusion criteria, and d) compliance with augmented and/or other examination comitments identified during the licensing process.

2.0 EVALUATION The determination addressed by the Licensee in the Second Ten-year Interval Inservice Inspection Program, Revision 1, and to the staff's request for additional information that certain ASME Code,Section XI, requirements were impractical to perform at Brunswick Steam Electric Plant, Units 1 and 2, were evaluated. A summary of our evaluation is shown in Table 1. The detailed evaluation and review is attached in the reports. EGG-ESM-7914 and EGG-ESM-7915, from our contractor, Idaho National Engineering Laboratory; and the staff agrees with and adopts the conclusions in the referenced reports.

3.0 CONCLUSION

We conclude from our evaluation that the Second Ten-year Interval Inservice Inspection Program for the Brunswick Steam Electric Plant Units 1and2,isacceptableandincompliancewith10CFR50.55a(g}(4).

We detemined that certain ASME Code Section XI examination requirements are impractical to perform at the Brunswick Steam Electric Plant, Units 1 and 2. Relief is granted from ASME Code Section XI requirements for request numbers RR-1, RR-3, RR-4, RR-5, RR-6, and RR-7. Pursuant to 10 CFR 50.55a(g)(6)(1), such relief 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 that could result if the requirements were imposed on the facility. The staff is in the process of reviewing the examination requirements for the reactor pressure vessel and relief is not granted for request number RR-2, category B-A, circumferential shell welds.

Principal Contributor: F.B. Litton Dated: May 10, 1989

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