ML20244D031

Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan

ML20244D031
Person / Time
Site:	Vermont Yankee
Issue date:	06/07/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20244D026	List: ML20244D025 ML20244D031
References
NUDOCS 8906160051
Download: ML20244D031 (10)

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wAsMNGTON, D. C. 20585 I y...o J ATTACHMENT' L

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION'

, a THESECONDTEN-YEARINTERVALINSERVICEINSPECTIONPROGRAMPLdN i ei

' VERMONT YANKEE NUCLEAR POWER CORPORATION VERM0HT YANKEE NUCLEAR' POWER STATION DOCKET NO.: 50-271;

1.0 INTRODUCTION

Technical Specification 4.6.E for 'the Vermont Yankee' Nuclear Power' Station states that the surveillance. requirements for Inservice-InspectionJand Testing;of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

Class 1, 2, and 3 components shall be applicable as follows: Inservice 5Inspec-tion of ASME Code Class-1, 2, and.3 components shall be performed in accordance. '

with Section XI of the ASME Code and-applicable Addenda as required by -

10 CFR 50.55a(g), except'where specific written relief has been granted by. the Commissionpursuantto-10CFR50.55a(g)(6)(1).

Pursuantto10CFR50.55a(g)(4),;ASMECodeClass1,2,and3. components (includ-ing 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 exami-nation of components and system pressure tests conducted during the second ten ' i year interval shall comply with the requirements in the latest edition and addenda i of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b). on the date twelve months prior to the start of the 120-month inspection-interval. ,

i 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. i

~

L Pursuantto10CFR50.55a(g)(5),if.the.licenseedeterminesthatconformancewith I

l an examination requirement of Section XI.of the ASME Code is not practical for; his facility, information shall be submitted to the Consnission in support of that determination and a request made for relief from the ASME Code re After evaluation of the determination, pursuant- to 10 CFR 50.55a(quirement.g)(6)(1),

Commission may grant relief and may impose alternative requirements.that are determined to be authorized by law, 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.

PDC 'O

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2-The Licensee, Vermont Yankee Nuclear Power Corporation, has prepared the Vermont Yankee Nuclear Power Station Second' Ten-Year. Interval:Inse'rvice . Inspection (ISI)

. Program Plan,' Revision 9, through Amendment 1. to meet the requirements of- the 1980 Edition, Winter 1980 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code with.the followi_ng exceptions: :(a).the. extent of examination for Code Class 1 piping welds has been determined by the 19741 Edition'.through Summer.

-1975 Addenda as permitted by 10.CFR 50.55a(b) and (b) the extent:of examination of. Class 2 piping welds.has been determined by ASME. Code Case. N-408 as ' allowed-by Regulatory. Guide '1.147. The staff, with technical assistance from its Con-tractor, Idaho National Engineering Laboratory (INEL), has evaluated the Second' Ten-Year Interval Inservice Inspection Program Plan,-Revision 9; .through Amendment'.1,. additional information related to the_ plan, and.the requests for relief from certain ASME Code requirements determined to be= impractical for Vermont Yankee Nuclear Power Station during the second inspection interval.

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 impractical Section XI Code requirements. The staff has determined that the. Licensee's ISI Program Plan reflects compliance with the requirements listed above. The infor-mation provided by the Licensee in support of requests for relief from impractical requirements has been evaluated and the bases for granting relief from those requirements are documented in the attached INEL Technical Evaluation Report EGG-MS-8215. We concur with'the findings and recommendations contained in the subject report. Table 1 presents a summary of the reliefs requested and the 4 status of the requests as determined by the staff. '!

3.0 CONCLUSION

The staff concludes that the Vermont Yankee Nuclear Power Station Second Ten-Year  ;

Interval Inservice Inspection Program Plan, Revision 9, through Amendment 1, with i the additional information provided and the specific written relief constitute  !

thebasisforcompliancewith10.CFR50.55a(g)andTechnical' Specification 4.6.E j and is therefore acceptab?e.

Principal Contributor j D. Jackson

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