ML20235U556

Forwards Region I Portion of Safety Evaluation & SALP Input Accepting Util Tech Spec Change Request 146 Re Leakage Testing of Primary Coolant Sys Pressure Isolation Valves

ML20235U556
Person / Time
Site:	Oyster Creek
Issue date:	10/06/1987
From:	Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Varga S Office of Nuclear Reactor Regulation
References
TAC-65640, NUDOCS 8710140136
Download: ML20235U556 (6)

Text

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OCT 6 1987 Docket No. 50-219-MEMORANDUM FOR: Steve A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation.

FROM:- William F. Kane, Director Division of Reactor Projects Region I

SUBJECT:

LICENSING ACTION REVIEW FOR OYSTER CREEK NUCLEAR GENERATING STATION REGARDING THE PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES TECHNICAL SPECIFICATION CHANGE (TAC N0. 65640)

Region I has completed the review of that portion of the 'GPU Nuclear Corporation Technical Specification Change Request No. 146 for Oyster Creek Nuclear Generating Station relating to leakage testing of the Primary Coolant System Pressure Isolation Valves.

Based on this review,- and as statec' in the enclosed Safety Evaluation, we have determined that the licensee's Techn.:a1 Specification change is acceptable and recommend its approval.

This action ' completes the work to be performed by Region I for TAC No. 65640.

The principal technical reviewer for this licensing action was John G. Hunter, Division of Reactor Safety.

Sincerely, Original Signed By:

William F. Kane, Director Division of Reactor Projects

Enclosures:

1. Safety Evaluation

2. Revised T.S. Page 4.3-2

3. SALP Input cc w/encls:

B. Boger, AD, RGI Reactors, NRR J. Stolz, Director, PDI-4, NRR A. Dromerick, SPM, PDI-4, NRR CONTACT:

B. Hillman 488-5315

~~ilCIAL RECORD COPY OL TAC 65640 - 0001.0.0 01goM $h 9 9/2/87

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W.- Kane, DRP S. Collins, DRP R. Blough, DRP W.-Johnston, DRS L Bettenhausen, DRS P. Eapen, DRS J. Hunter, DRS

.D. Caphton, DRS

.. B. Hillman, DRP I Resident Inspector l'

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. TO PROVISIONAL FACILITY OPERATING LICENSE NO. DPR-16 GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 Introduction The April. 20,1981,' Order for Modification of License Concerning Primary Coolant System Pressure Isolation Valves required the licensee to implement Technical. Specifications (TS) to perform periodic leak testing.of the Primary Coolant System Pressure Isolation Valves. The TS requirements for test frequency. imposed by the April.20, 1981, Order were derived from the Franklin Research Center report TER-C5257-252 (Rev. 1). The test frequency criteria in the' report, however, included a recommendation for. leak testing,'"...each time  ;

any check valve may have moved from the fully closed position..." which was not incorporated into the TS requirements imposed by the April 20, 1981, Order.

This inconsistency was' identified during NRC' inspection 50-219/85-36 when.the Core Spray' System air operated check valves (classified as Primary Coolant System Isolation Valves in the TS) had been exercised twice without subsequent leakage. testing. The licensee's TS 4.3-G did not include the requirement for  ;

leak testing after each Primary Coolant System Pressure Isolation Valve movement.

In response to the above NRC inspection concern, by letter dated June 19, 1987, GPU Nuclear Corporation submitted Technical Specification Change Request No.146 to Provisional Operating License No. DPR-16 to amend the facility's TS

'to require leak rate testing after each primary coolant system pressure isolation valve movement. This SE addresses the additional proposed testing.

Proposed Changes The proposed change is to add "...whenever a valve is moved whether by manual

-actuation or due to flow conditions...." to Technical Specification 4.3-G, to leak test the primary coolant system pressure isolation valves.

Review Criteria / Requirements (1) Order for Modification of License Concerning Primary Coglant System Pressure Isolation Valves (w/ attachments), April 20, 1981.

OFFICIAL ~ RECORD COPY OL TAC 65640 - 0003.0.0 9/2/87

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! Evaluation The additional requirement for leakage testing of the Primary Coolant System i Pressure Isolation Valves after each movement of the valves will provide I confidence that the valves are properly seated. The change will also make the Oyster Creek Nuclear Generating Station Technical Specifications consistent with the test frequency criteria in TER-C5257-252 (Rev. 1) which formed the basis of.the. April 20, 1981, Order imposing the original leak test requirements. Based upon the above, the staff finds the licensee's proposed 1 amendment to be acceptable.

Environmental Consideration Thi's amendment involves a chaage in a surveillance requirement. The staff has determined that the amendment involves no significant increase in the amounts,

'and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a pro-posed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amend-ment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

Conclusion We have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Date:

Principal Contributor: John G. Hunter, III, Division of Reactor Safety, RGI J

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l OFFICIAL RECORD COPY OL TAC 65640 - 0003.1.0 10/06/87 l

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Enclosure 2

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• G. ' Primary Coolant Systcm Pressure Isolation Val'ves

*- -5 specification

1. Periodic' leakage testing (a) on each valve listed in table 4.3.1 shall be accomplished prior to exceecing 600 psig reactor pressure every time the plant is placea in tne colo snutoown condition for refueling, eacn time tne plant is placed in a colo snutcown concition for 72 hoars if testing has not been accomplished in the preceeding 9 months,'whenever the valve is movea wnether by manual actuation or due to flow conditions, and after returning the valve to service after maintenance, repair or replacement work is performea.

H. Reactor Coolant System Leakage

1. Unidentified leakage rate shall be calculated at least once every 4 nours.

2. Total leakage rate (icentified and unidentified) snali a calculated at least once every 8 nours.

3. A channel calibration of the primary containment sump flow integrator and the primary containment eauipment drain tank flow integrator shall be conducted at least once per 18 montns.

i Bases:

Numerous data are available relating integrated flux and tne change in Nil-Ductility Transition Temperature (NDTT) in various steels. Tne base metal has been demonstrated to be relatively insensitive to neutron irradiation (see expectea NOT cnanges in FDSAR Table IV-1-1, and Figures IV-2-0 and IV-2-10). Tne most conservative cata has been usea in Specification 3.3. The integratea flux at the vessel wall is calculated from core pnysics cata and will be measurea using flux monitors installec inside the vessel. The measurements of the neutron flux at the vessel wall will be used to check and if necessary correct, the calculateo cata to determine an accurate flux. From this a conservative NOT temperature qan be determined. Since no shift will occur until an integrated flux of 10 l' nyt is reached, the confirmation can be made long before an NDTT shif t would occur.

The inspection program will reveal problem areas should they occur, before a leak develops. In aadition, extensive visual inspection for leaks will be made on critical systems. Oyster Creek was designed and constructed prior to

(*) To satisf y ALARA requirements, leakage may be measured indirectly (as ,

from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the methoo is capable of demonstrating valve compliance with the leakage criteria.

• NRC Orcer cated April 20, 1981 Correctec: 1/28/So

-0YSTER CREEK 4.3-2 Amenoment: 82. 97 a

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P-- Enclosure.3

.SALP INPUT

'0yster Creek Nuclear Generating Station

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Facility:.

Docket No.: 50-219 TAC No. 65640 Functional Area: Licensing Activity

Management' Involvement and Control in Assuring Quality 0 The licensee's .. management ' demonstrated their involvement in controlling and '

assuring quality. by. their agreement with .the inspectur's concerns

-(50-219/85-36) regarding the leak test frequency'of the Core" Spray System air operated : check valves and their prompt decision to initiate a Technical Specification ' change; to address the concern. The. change demonstrates _ a

' willingness to perform additional work for the sake.of conservatism.

Rating: Category 1-Approach to' Resolution of Technical Issues from a Safety Standpoint The licensee. clearly understood the issue raised by the inspector and readily agreed . that the additional leak test frequency requirement for the Primary

- Coolant System Pressure Isolation Valves was a more conservative and prudent practice, i

. Rating: Category 1 Responsiveness to NRC Initiatives

The licensee was very responsive and in agreement with the inspector's concerns and- initiated acceptable resolutions through the Technical Specification

. process.

Rating: Category 1 Overall Rating: Category 1 L

OFFICIAL RECORD COPY OL TAC 65640 - 0007.0.0 09/02/87 a____________ .)