ML20237B461

Safety Evaluation Granting Relief from Exams & Testing Requirements & Alternate Methods from First 10-yr Interval Inservice Insp Program

ML20237B461
Person / Time
Site:	Hope Creek
Issue date:	12/11/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237B442	List: ML20237B440 ML20237B461 ML20237B470
References
NUDOCS 8712160279
Download: ML20237B461 (4)

Text

._ _

. SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PUBLIC SERVICE ELECTRIC & GAS COMPANY HOPE CREEK GENERATING STATION DOCKET NO.: 50-354 The Technical Specifications for the Hope Creek Generating Station state that the surveillance requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows: 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 where specific written relief has been granted by the Comission pursuant to 10 CFR 50, Section50.55a(g)(6)(1).

Pursuant to 10 CFR 50.55alg)(4), ASME Code Class 1, 2 and 3 components I (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, i geometry and materials of construction of the components. The regulations '

require that inservice examination of components and systems 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 i meet the requirements set forth in subsequent editions and addenda of the ASME i 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 examinati.on requirement of Section XI of the ASME Code is not practical for his facility, infomation is submitted to the Commission in support of that determination and and a request made for relief from the ASME Code i

requirements. After evalaution 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.

8712160279 871211 PDR ADOCK 05000354 G PDR

- - __ _ ____ _ ___ ____ _ a

, \

The Public Service Electric and Gas Company, the licensee, prepared the Hope Creek Generating Station ISI Program, Long Term Plan, First Ten-year Interval Revision 0, to the requirements of Section XI, ASME Code,1983 Edition, including Summer 1983 Addenda, except that the requirements of Code Case N-408 will be used for the examination of Class 2 piping welds in the residual heat removal, emergency core cooling, and containment heat removal systems.

The evaluation of the Inservice Inspection Program is contained in the TER prepared by the Idaho National Engineering Labnratory, EGG-SD-7829. The first interval began on December 29, 1986, and ends December 29, 1996.

The information in the Hope Creek Generating Station Inservice Inspection Program, Long Term Plan, First Ten-year Interval, Revision 0, dated June, 1987, was reviewed, including the requests for relief from the Section XI, ASME Code, requirements, which the licensee determined to be impractical. The review was perfonned using the Standard Review Plan, NUREG-0800, Section 5.2.4, " Reactor Coolant Boundary Class 2 and 3 Components," and Section 6.6, l " Inservice Inspection of Class 2 and 3 Components". Additional information l was requested and provided by the licensee to clarify the examination i requirements of the program.

The staff, with technical assistance from its contractor, Idaho National Engineering Laboratory, has evaluated the First Ten-Year Interval Inservice Inspection Program and additional information related to the justification for the relief from certain ASME Section XI Code requirements determined to be impractical to perform at the Hope Creek Generating Station during the inspection interval.

EVALUATION -

The ISI Program was evaluated for (a) compliance with the appropriate ASME Code edition and addenda, (b) acceptability of the examination sample, (c) exclusion criteria, and (d) compliance with ISI related commitments identified during the review for the Operating License. The request for relie' 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-7829 is attached. The TER includes an evaluation of the 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 except in the case of the reactor vessel welds, Category B-A. The procedure for the examination of these welds is under review by the regulatory staff at this time.

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

l l

[ . .

F CONCLUSION l

l' We conclude that' relief granted from the examination and testing requirements j

and alternate methods imposed through this document give reasonable assurance l

L of the piping and component pressure boundary and support structural integrity, that granting relief because of ASME Code requirement impracticality is authorized

' by law and will- not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result .if they were imposed on the Hope Creek Generating Station.

S I

l

TABLE 1

. STATUS OF RELIEF REQUESTS Examination Number Category Description l Status 3.1.1.1 B-A Reactor Pressure Vessel Not Granted Items Bl.30 and Shell-to-Range and B1.40 Head-to-Flange Welds 3,1.1.2 B-A Reactor Pressure Vessel Not Granted Items Bl.11 and Circumferential Shell B.1.12 and Longitudinal Shell Welds 3.1.1.3 B-A Reactor Pressure Vessel Not Granted Items Bl.21 and Circumferential Head B1.22 and Meridional Head Welds 3.1.1.4  : Reactor Pressure Vessel Granted hen: B3.90 Noz71e-to-Vessel Welds 3.1.1.5 B-D Reactor Pressure Vessel Granted Item B3.100 Nozzle Inside Radius 3.1.1.6 B-G-1 Reactor Pressure Vessel Granted Item B6.40 Flange Ligaments 3.1.1.7 B-H Reactor Pressure Vessel Granted Item B8.10 Stabilizer Bracket Welds 3.1.4.1 B-J Class 1 Piping Systems Granted Item B9.11 Pressure Retaining ,

Circumferential Welds '

3.1.4.2 B-J Class 1 Piping Systems Granted Item B9.31 Pressure Retaining Branch Connection Welds 3.1.4.3 B-K-1 Class 1 Piping Systems Granted Item B10.10 Integrally Welded Attachments 3.2.1.1 C-8 RHR Heat Exchanger Granted Item C2.22 Nozzle Inside Radius 3.2.3.1 C-G Class 2 Pump Casing Granted Item C6.10 Welds Pressure Retaining I

3.5.3.1 F-C Inservice Visual Granted Examination of Mechanical and I Hydraulic Snubbers f i

.e _ _ ___-__________________O

_