ML20244A722
| ML20244A722 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/11/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244A713 | List: |
| References | |
| NUDOCS 8904180162 | |
| Download: ML20244A722 (9) | |
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ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN l
COP 910NWEALTH EDISON COMPANY BYRON NUCLEAR POWER STATION, UNIT 1 DOCKET NO.: 50-454'
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1.0 INTRODUCTION
Technical Specification 4.0.5 for the Byron Nuclear Power Station, Unit 1, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASME) Boiler and Pressure -
l Vessel Code Class 1, 2, and 3 components shall be applicable as follows:
Inservice Inspection of ASME Code. Class 1,.2, and 3 components shall be perfor-ced in accordance with Section XI'of the ASME Code and applicable Addenda as requi' red by 10 CFR 50, Section 50.55a(g), eynept where specific written relief has been granted by the Comission 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 (inclu-ding 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, geome-try, and saterials 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 the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date 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 ar3d addenda of the ASME Code incorporated by referencein10CFR50.55a(b)subjecttotheIfmitationsandmodifications l
listed therein.
Pursuantto10CFR50.55a(g)(5),ifthelicenseedeterminesthatconformance 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 deta: ruination and a request made for relief from the ASME Code req ment. Afterevaluationofthedetermination,pursuantto10CFR50.55a(g(6)
(i), the Commission may grant relief and may impcse 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.
On February 6,1986, Commonwealth Edison Company (the Licensee) submitted the FirstTen-YearIntervalInserviceInspection(ISI)ProgramPlan, Revision 1, for the Byron Nuclear Power Station, Unit 1, to meet the requirements of the j
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1980 Edition, Winter 1981 Addenda of-Section XI of the ASME Boiler and Pressure Vessel Code, except that Class 2 pip)ing welds in the Emergency Core Coolin were selected / exempted based upon the 1974 Edition, Summer 1975 Addenda as required by 10 CFR 50.55a(b). 'The staff, with technical assistance from its Contractor, Idaho National Engineering Laboratory (INEL), has evaluated the First Ten-Year Interval Inservice Inspection Program Plan, Revision 1, additio-pal information related to the plan, and the requests for relief from certain ASME Code requirements determined to be impractical to perform at the Byron Nuclear Power Station, Unit 1, during the first inspection interval.
j 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 re utrements of Section XI, (c) acceptability of the examination sample,
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(d compliance with commitments made by the Licensee prior to plant operation, (e correctness of the application of system or component examination exclusion criteria,and(f)adequateinformationinsupportofrequestsforrelieffrom impractical Section XI Code requirements. The staff has determined that the Licensee's ISI Program Plan reflects compliance with the Nguirements listed above with the exception of the examination sample and the application of exclusion criteria. As discussed in Sections 2.2.2 and 2.2.3 of the INEL Technical Evaluation Report (TER) attached, the Containment Spra) estem is
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completely exempted from ISI examinations based on the pressure / temperature exemption criteria contained in IWC-1220(b) of Section XI of the ASME Code.
Paragraph 10 CFR 50.55a(b)(2)(iv) requires that ASME Code Class 2 piping welds in the RHR, ECC, and CHR systems shall be examined. These systems should not be completely exempted from inservice volumetric examination based on Section XI exclusion criteria contained in IWC-1220. Later editions and addenda of the Code do not permit the pressure / temperature exclusion for RHR, E.CC, and CHR systems.
Also, the Licensee has incorrectly exempted two integrally welded attachments to Code Class 2 pressure boundaries. Although the Licensee's basis for exemp-tion is the absence of additional static or dynamic loads on the piping from which the connecting component support has been removed, these welds and their heat-affected zones should receive the Code-required surface examination 1
because these welds, which penetrate the piping pressure boundary, and their j
heat.affected zones remain on the Class 2 pressure retaining piping.
To make the ISI Program Plan acceptable for implementation, the Licensee should submit a docketed commitment to delete the pressure / temperature exclusion for Class 2 welds in the RHR, ECC, and CHR systems from the ISI Program Plan, perform volumetric examinations of an acceptable sample of the Class 2 welds in the Containment Spray System, and perform the Code-required surface examination of the two incorrectly exempted integrally welded attachments to Class 2 pressure boundaries as discussed in the TER.
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The information provided by the License in support of requests for relief from imptsetical requirements has been evaluated and the bases for granting relief from those requirements are documented in the INEL TER attached. We concur with', and adopt, the findings and recommendations contained in the TER.
. Table 1 presents a summary of the reliefs requested and the status of the requests as determined by the staff.
3.0 CONCLUSION
i The staff concludes that the Byron Nuclear Power Station, Unit 1, First Ten-Year Interval Inservice Inspection Program Plan, Revision 1,[with the additional information provided and the specific written relief excluding NR-3, NR-12 (in part), CR-2, and SR-1 for which relief is denied] constitute the.basisforcompliancewith10CFR50.55a(g)andTechnicalSpecification 4.0.5 and is therefore acceptable provided that the Licensee submits an acceptable docketed response to the items discussed in Sections 2.2.2 and 2.2.3 of the INEL TER with regard to deleting the pressure / temperature exclusion for Class 2 welds in the RHR, ECC, and CHR systems from the ISI Program Plan, performing volumetric examinations of an acceptable sample of Class 2 piping welds in the Containment Spray System, and performing the Code-required surface examination of the Code Class 2 integrally welded attachments. With res 10 CFR 50.22a(g)(6)(1)pect to the reliefs granted pursuant to
, the staff has determined that the requirements 01 the code are impractical and, based on the alternatives imposed, relief is authorized ay law, 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.
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