ML20217N723
| ML20217N723 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/02/1998 |
| From: | Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | |
| Shared Package | |
| ML20217N721 | List: |
| References | |
| NUDOCS 9803090163 | |
| Download: ML20217N723 (5) | |
Text
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l l+;&gf fg 1-This License Amendment Request is submitted by North Atlantic Energy Service Corporation pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
Section 1 Introduction and Safety Assessment for Proposed Change Section 11 Markup of Proposed Change
. Section 111 Retype of Proposed Change Section IV Determination of Significant Hazards for Proposed Change Section V Proposed Schedule for License Amendment issuance and EffectivenessSection VI Environmentalimpact Assessment Swom and Subscribed befo rA ^y me this l
day o
.1998 Ted C. Feigenbaug
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C Notary Public Executive Vice President and Chief Nuclear Officer l
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9003090163 980302 i
PDR ADOCK 05000443 4
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i Section 1 Introduction and Safety Assessment for the Proposed Changes Page1 J
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- INTRODUCTION AND SAFETY ASSESSMENT OF PROPOSED CHANGES A.
Introduction License Amendment Request (LAR) 97-06 proposes changes to Seabrook Station Technical Specifications (TS) 4.8.1.1.2a, 4.8.1.1.3, Table 4.8-1 and TS 4.8.1.2, as authorized by NRC Generic Letter (GL) 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators." The proposed changes will revise the frequency for performance of specific surveillances and delete the requirements contained in the current Technical Specifications for accelerated testing whenever the number of valid test failures associated with the Emergency Diesel Generators (EDGs) is met or exceeded. In addition, the special requirements for reporting valid or l
invalid EDG failures will be deleted.
B.
Safety Assessment of Proposed Changes GL 94-01 specifies that licensees must commit to implement within 90 :ays of issuance of ths license amendment a maintenance program for monitoring and maintaining CDG performance that is consistent with the provisions of 10 CFR 50.65, " Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," and the guidance contained in Regulator" Guide (RG) 1.160, " Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."
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The basis for License Amendment Request 97-06 is North Atlantic's implementation of the Maintenance Rule Program in accordance with the provisions of 10 CFR 50.65, Regulatory Guide (RG) 1.160, and NUMARC 93-01," Industry Guide for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."
As of July 10,1996, structures, systems, and components (SSCs) that have been determined to be within the scope of the Maintenance Rule have been designated as either status (a)(2) or (a)(1), as delineated in 10 CFR 50.65. North Atlantic's maintenance rule program establishes specific performance criteria for each SSC. Reliability and unavailability performance criteria have been assigr. d to risk significant and j
standby safety-related non-risk significant SSCs. Other in-scope SSCs have been assigned appropriate reliability and/or plant level performance criteria. SSCs that are determined to not meet the established performance criteria are designated as (a)(1) and are subject to action plans, goal setting, and goal monitoring. Performance of(a)(1) SSCs is compared to the established goals. When it is determined that the performance goals have been achieved, a SSC may be returned to the normal performance monitoring (a)(2) status.
The maintenance rule program is subject to formal periodic assessment to ensure that: (1) SSCs performance criteria remains appropriate; (2) reliability and unavailability are properly balanced; (3) industry experience is effectively used; and (4) the program for removal of equipment from service supports safe plant operation.
With regard to the EDGs, these components and the associated support systems are risk significant and standby safety-related. Both EDGs have demonstrated acceptable performance and are currently designated as (a)(2). The experience to date, applying the Maintenance Rule Program to the EDGs, has proven to be positive. Risk informed decisions concerning the benefits of maintenance and time out of service has maintained highly reliable EDGs with unavailability consistent with the assumptions in the PRA.
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The deletion of TS Table 4.8-1, " Diesel Generator Test Schedule," and revision of the surveillance requirement frequency for TS 4.8.1.1.2a (by deleting the reference to TS Table 4.8-1 and requiring the surveillance to be performed at least once every 31 days) will result in the test frequency to no longer be dependent on the number of previous failures. Therefore, there would be no increased tuting I
requirements.
The deletion of TS 4.8.1.1.3 and reference to TS 4.8.1.1.3 contained in TS.4.8.1.2, will remove the -
requirement for special reporting of valid or invalid EDG failures. North Atlantic will continue to notify the NRC of significant EDG failures in accordance with the provisions of 10 CFR 50.72 and 50.73.
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Section II Markup of Proposed Changes i
The attached markups reflects the currently issued revision of the Technical Specifications listed below. Pending Technical Specifications or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed markup.
The following Technical Specifications are included in the attached markup:
Technical Specification Title Page(s)
SR - 4.8.1.1.2a.
A.C. Sources - Operating 3/48-3 SR - 4.8.1.1.3 A.C. Sources - Operating 3/4 8-9 Table 4.8-1 Diesel Generator Test Schedule 3/4 8-10 l
SR - 4.8.1.2 A.C. Sources - Shutdown 3/4 8-11
- Index - Table 4.8-1 Limiting Conditions for Operation viii and Surveillance Requirements Page 4