ML20236D185

Safety Evaluation Accepting Util 870602 Rev 2 to First 10-yr Interval Inservice Insp Program

ML20236D185
Person / Time
Site:	River Bend
Issue date:	10/20/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236D168	List: ML20236D165 ML20236D185 ML20236P711
References
TAC-62971, TAC-64826, NUDOCS 8710280059
Download: ML20236D185 (5)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION f'"  ;

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SAFETY EVALUATION BY THE 0?FICE OF NUCLEAR REACTOR REGULATION ,

ON THE-FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM r GULF STATES UTILITIES COMPANY RIVER BEND' STATION UNIT 1 DOCKET NO.: 50-458 INTRODUCTION The Technical Specifications for the River Bend Station Unit 1 states that the surveillance requirements for inservice inspection and testing of Arrerican Society of Mechanical Engineers (ASME) Boiler and Pressure 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 performed in accordance with Section XI of the ASME Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2 and 3 components (includirig supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME i 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 regulat. ions require that inservice examination of components and systems aressure tests conducted during the first ten year interval shall comply wit 1 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 tothedateofissuanceoftheoperatinglicense,subjecttothelimitations 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 to an examination requirement of Section XI of the ASME Code is not practical for the 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 i 50.55a(g)(6)(i), the Commission may grant relief and impose alternative i requirements as it determines are authorized by law and will not endanger life l cr 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  !

t result if the requirements were imposed. l 1 i Gulf States Utilities Company, the licensee, prepared the River Bend Station i 4

• 3 Unit 1 First Ten-Year Interval Inservice Inspection (ISI) Program Plan, 1

I a 8710280059 871020 1 PDR ADOCK 05000458 G PDR

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through Revision 2, to meet'the requirements of the 1980 Edition, Winter 1981 3 Addenda (80W81)ofthe-ASME'CodeSectionXIexceptthattheextentof-

[ examination for Code Systems and Emergency Class Core 2 piping (welds in Residual Heat Removal (RHR)'EC Cooling I Edition through Summer 1975 Addenda (74575). The first inspection interval -l began June 16, 1986 and ends June 16, 1996.  ;

The information in the River Bend Station Unit 1 First Ten-Year Interval ISI l Program, through Revision 1, submitted July 16, 1986 was reviewed including '

the requests fer relief from the ASME Code Section XI requirements which the licensee has determined to be impractical. The review was performed using the Standard Review Plan, NUREG-0800, "Section 5.2.4, " Reactor Coolant Boundary l Inservice Inspections and Testing, and Section 6.6, " Inservice Inspection of Class 2 and 3 Components." In a letter dated January 21, 1987, the staff-requested additional information that was required in order to complete the review of the ISI Program. The requested information was provided and the licensee in letters dated '

Ravision February 27, 2 of1987, the ISI Program March was submitted 10, 1987, and June 2,by'1987.

The staff, with technical assistance from its contractor, Idaho National Engineering Laboratory, has evaluated the first Ten-Year Interval Inservice InspectionProgramandadditionalinformationrelatedtothejustification

.for the relief from certain ASME Section XI Code requirements determined to ,

be impractical to perform at the River Bend Station Unit 1 during the inspection interval, j i

EVALUATION  :

The ISI Program was evaluated for (a) compliance with the appropriate ASME 1 1

Codeeditionandaddendum,)(b)acceptabilityoftheexaminationsample,(c) exclusion criteria, and (d compliance with ISI related commitments identified during the review for the Operating License. The requests for relief from the requirements of Section XI of the ASME Code were reviewed and evaluated by our Contractor, INEL. The Technical Evaluation Report (TER)

EGG-SD-7669, July, 1987, is attached. The TER includes an evaluation of the 1 ISI Program Plan and the requests for relief from Section XI requirements. The staff has reviewed the TER and concurs with the evaluation and recommendation Category.B-A. The procedure except in the case of for the examination the reactor of these welds vessel is underwelds,iew rev by the NRC staff at this time. -

A summary of the relief requests evaluated and the determinations made by the staff is shown in Table 1, 1

CONCLUSION We conclude that reliefs granted from the examination and testing requirements

( and alternate methods imposed through this document give reasonable assurance of the piping and com)onent pressure boundary and support structural integrity, that granting relief aecause of ASME Code requirement impracticality is "5

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. .l authorized by law and will not endanger life or property, or the common 1

• ' defense and security, and is otherwise in the public interest considering ']

the. burden that could result if they were imposed on the River Bend Station i Unit 1. .

l Principal Contributor: F. Litton Dated: -October 20, 1987 y l

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Status of Relief Requests l l

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Examination

" Category Description Status Number i 6

RR0012A, Rev.'2 B-A Reactor Pressure Vessel Not Granted  :

Item B.l.12 Longitudinal Shell Weld RR00128, Rev. 2 B-D Reactor Pressure Vessel Granted Item 83.90 Nozzle-to-Vessel Welds RR0012C, Rev. 2 B-A Reactor Pressure Vessel Not Granted Item B1.11 Circumferential Shell Welds i RR00120, Rev. 2 B-A Reactor Pressure Vessel Not Granted Item Bl.11 Shell-to-Bottomhead Welds RR0012E, Rev. I B-A Reactor Pressure Vessel Not Granted <

Item 81.40 Top-Head-to-Flange Weld RR0012F, Rev. 1 B-H Reactor Pressure Vessel Granted Item B8.10 Support Skirt Attachment Weld RR0012G, Rev. 1 F-A Reactor Pressure Vessel Granted Support Skirt-to-Base  !

Plate, Base Plate Seam and l Bolting Ring Welds RR0012H, Rev. I B-A Reactor Pressure Vessel Not Granted i Item 81.22 Bottom Head Meridional I Welds l RR0004, Rev. 2 B-0 Peripheral CRD Housing Granted Item 814.10 Bolting for CRD Housing B-G-2 and In-Core Housings Item B7.10 RR0001, Rev. 2 B-J Pressure Retaining Circum- Granted Item 89.11 ferential Welds in Class 1 Piping RR0006, Rev. 2 B-J Pressure Retaining Granted Item B9.11 Dissimilar Welds in Class 1 Piping RR0007, Rev. 2 B-J Pressure Retaining Welds Granted Items 89.11 in Class 1 Piping and 89.12 4

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. Table 1 Status of Relief Requests 4

Examination i Number Category Description Status f i

RR0008, Rev. 2 B-J Pressure Retaining Welds Granted

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Item 89.11 in Class 1 Piping i RR0013, Rev. 2 B-J Pressure Retaining Circum- Granted Items 89.11 ferential and Longitudinal and 89.12 Welds in Class 1 Piping RR0014 Rev. 2 B-J Pressure Retaining Circum- Granted Items B 9.21 ferential and Branch Pipe  !

and B0.31 Connection Welds in )

Class 1 Piping j RR0009, Rev. 2 B-L-2 Class 1 Pump Casings Granted and B-M-2 and Valve Bodies j Items B12.10 '

and'B12.50 RR0005A, Rev. 2 B-K-L Integral Welded Granted Items B10.10 Attachments for Class 1 1 and 810.20 Piping and Pumps RR0011, Rev. 2 C-A Pressure Retaining Head Granted l Item C1.20 Circumferential Welds in i and C-8 Class 2 Vessels, and  !

Item C2.21 Pressure Retaining Nczzle-and C2.22 to-Shell Welds and Nozzle Inside Radius Sections in i Class 2 Vessels RR0010, Rev. 3 C-F Pressure Retaining Granted l Item C5.11 Circumferential Welds I in Class 2 Piping i RR0003, Rev. 3 C-G Pressure Retaining Welds Granted Item C6.10 in Pumps RR00058, Rev. 2 C-C Integral Welded Attachments Granted Items C3.10 for Class 2 Vessels and Piping 1

RR0015 IWA-2600 Requirement for Establish- Withdrawn and IWA-2641 mnt of a System for Layout

, of Reference Points on  ;

Center Line of Class I and : i Welds l

• RR0016, Rev. 1 Appendix III Notches in Ultrasonic Granted Article III-3000, Examination Calibration '

Tat,le III-3430-1 Blocks

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