ML20009B871

Forwards Responses to NRC Request for Addl Info Needed for Completion of NRC Review of SER Open Items & NUREG-0737, Items I.C.7 & II.K.3.22

ML20009B871
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/15/1981
From:	Mccaffrey B LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.7, TASK-2.K.3.22, TASK-TM SNRC-594, NUDOCS 8107170272
Download: ML20009B871 (9)

Text

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<w-s LONG ISLAND ! IGHTING COMPANY

, 1 SHOREHAM NUCLEAR POWER STATION

,v,..g,,_.._ . P.O. DOX 618. NORTH COUNTRY ROAD + WADING RIVErt. N.Y.11792 July 15, 1981 SNRC-594 Mr. Harold R. Denton Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 , ,\gs.i!I f (jh

" JUL 1 G 1981 > r I

SHOREHAM NUCLEAR POWER STATION - Unit 1 c3 '*****'

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Docket No. 50-322 p b

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Dear Mr. Denton:

Enclosed herewith are sixty (60) copies of LILC0 resopnses to specific NRC concerns which were previously identified as requiring additional information to complete NRC review. Attachment A provides a list of the specific responses included.

If you require additional information or clarification, please do not hesitate to contact this office.

Very truly yours,

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B. R. McCaf e Manager, Project Engineering Shoreham Nuclear Power Statior Enclosures cc: J. Higgins 6k 8107170272 810715 PDR ADOCK 05000322 E PDR FC-8935

. o Attachment A Additional information is provided for the following items:

1. SER Open Item No. 4 - Safety Related Snubbers which will be listed in the Tables of STS 3/4.7.9.

2. SER Open Item No. 48 - High Energy Line Breaks

3. SER Open Item No. 55 - Q-List

4. NUREG-0737 Item I.C.7 - NSSS Vendor Review of Procedures

5. NUREG-0737 Item II.K.3.22 - Automatic Switchover of Reactor Core Isolation Cooling System Suction.

SNPS Item #4 - Safety Related Snubbers which will be listed in the Tables of STS 3/4.7.9.

Prior to. installation, all safety related snubbers are operation- ~~

ally stroked to determine that they are not frozen, seized or jammed. Upon completion of installation, all snubbers are inspected to assure that'there are no visual signs of damage, impaired opdr-ability and that snubber location, orientation, position setting and configuration are according to dasign drawings and specification.

< Each snubber is checked to assure that adequate swing clearance is previded and that structural connections are installed correctly.

These inspections ar's performed in accordance with Construction Procedure CIP 6.2 and Quality Control Procedure O.C. 11.4. After inspection, each snubber is wrapped and protected from damage in accordance with site instructions. No more than 6 months prior to system preoperational testing, snubbers are unwrapped and visually inspected for_ signs of damage, impaired operability and adequate-swing clearance in accordance with Startup Procedure CG 000.36.

Fluid level and leakage are not applicable to Shoreham as hydraulic snubbers are not cmployed in any safety related systems.

The snubber thermal movements for those systems that have operating temperatures in excess of 2500F will be verified during the Startup Test phase under STP-811- " System Thermal Expansion Test Procedure".

j This includes verification of the expected snubber thermal movements and swing clearances. Discrepancies or inconsistencies will be dis-positioned prior to proceeding to the next test placeau. A prelim-inary list of the snubbers is attached. The final 3.ist will be included in the station technical specification.t.

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July 14, 1981

1. 48 HIGH ENERGY LINE BREAKS The applicant will supplement the high energy line break __.,

analysis (Appendix 3C) to specifically include the consequential effects as related to non-safety grade control systems. The present analysis does not take credit for non-safety' grade control

{ systems to demonstrate reactor shutdown capability. The 1

purpose of this analysis is to determine if the pipe break event affects any non-safety grade control system in such a manner as to worsen the event and, if so, to confirm shutdown 1 .

l capability and that the event is bounded by Chapter 15 analyses.

The pending supplemental analysis will be provided by September 30, 1981.

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.. 7-Open Item SS - Q List _

Item A. Conduit and Cable Trays and their supports in installations containing Class IE cables arid other installations whose failure during a seismic event may damage safety-related items. _ .

LILCO Response _.,

The replacement or modification of conduit, cable trays and their supports is controlled by the Station Modification Program or Station Maintenance Work Request Program. Each of these programs is delineated and controlled by approved station procedures. The Operational Quality Assurance (0QA) organization is an integral part of each program from both a review and audit standpoint. Routine inspections are made by Operations field personnel as part of normal plant rounds. Pertinent information is logged by Operations Personnel in accordance with approved procedures. The 0QA Organization will apply the pertinent portions of the QA Program by auditing the implementation of the above mentioned procedures.

Item B. Main Steam Isolation Valves Leakage Control System LILCO Response Modification or maintenance of the main steam isolation valve leakage control system will be conducted in accordance with the Station Modification or Station Maintenance Work Request Programs. Each of these programs is delineated in and controlled by approved station procedures. Main Steam Isolation Valves Leakage Control System is contro'.'-d by the station tech-nical specifications. The 0QA Ogranization is an integral part of each program from both a review and audit standpoint. The 0QA Organization will apply the pertinent portions of the QA Program by auditing the implemen-tation of these procedures and station compliance with technical specifications.

Item C. Various Radiation Measuring, Monitoring, arid Clean-up Items LILCO Response The various radiation measuring, monitoring and clean-up items associated with the emergency plan are controlled and calibrated in accordance with the Statioh Health Physics Program. This program is delineated in and controlled by approved station procedures. In addition, there are the Emergency Plan, Emergency Plan Implementing Procecures, and required drills. The OQA Organization applies the pertinent portions m f the QA Program by auditing the implementation of these procedures, the Plan and drills.

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Item D. Site Grading LILC0 Response This item was responded to in SNRC-577. No further action is required. -

Item E. Sentiment Measurements in tie Intake Canal LILC0 Response

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Intake canal measurements referenced above are controlled by the station technical specifications including acceptance criteria and surveillance requirements. The 0QA Organization will apply the pertinent portions of the QA Program by auditing station compliance with technical specifications.

Item F. Accident-Related Meteorological Data Collection Equipment LILCO Response The meteorological data collection system will be inspected and calibrated on a periodic basis as part of the radiation monitoring system. The program will be audited by QA.

Item G. Expendable and Consumable Items Necessary for the Functional Performance of Safety-Related Structures, Systems, and Components.

LILC0 Response .

Procurement of expendable and consumable items is accomplished and controoled by approved station procedures. The 0QA Organization is an integral part of the procurement review process. The 0QA Organization, during this review process, applies the pertinent portions of the QA Program such as documen-tation, inspection requirements, etc., consistent with the item (s) being procured. In addition, the 0QA Organization audits the implementation of the procurement control procedures.

Item H. C.W. Intake Pipes (Service Water Piping)

LILC0 Response The service water system is already identified as a Q listed system. No further action is required.

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.. 7 Item I. Intake Canal Slopes Item J. Rock Jetty - Long Island Sound Item K/L. Sheet Pile Retaining Walls ( on the side of Screenwell) and Headwalls.

LILC0 Response Item J is controlled by the station technical specifications including acceptance criteria and surveillance requirements. The 0QA Organization will apply the pertinent portions of the QA Program by auditing station compliance with technical specifications.

Items I, K and L are controlled by the Preventative Maintenance Program.

This program is delineated and controlled by approved station procedures.

The Operational Quality Assurance organization is an integral part of the program from both a review and audit standpoint.

Item M. The following Items from NUREG-0737:

Plant Safety Parameter Display Console (I.D.2)

, Post Accident Sampling Capability (II.B.3)

Valve Position Indication (II.D.3)

Emergency Plans (III.A.1.1/III.A.2)

Equipment and Other Items Associated with Emergency Support Facilities (III.A.1.2)

LIL;0 Response The plant safety parameter display console, post accident sampling equipment and safety relief valve positive .,nosition indicators are maintained and calibrated in accordance with'th 3 requirements delineated in the Station Maintenance Work Request and Modification Procedures. The 0QA Organization applies the pertinent portions of the QA Program by auditing the implementation of these procedures. The emergency plan, including the emergency support facility, is controlled in accordance with the approved Emergency Flan Program ard Emergency Plan Inplementing Procedures. The 0QA Organization will apply the pertinent portions of the QA Program by auditing the conduct of emergency drills and the implementation of the program.

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j I . C.' 7 NSSS Vendor Review of-Procedures 4

i The following position revises the commitment made in SNRC-563, dated 5/15/81:

The Site Operations Manager of the General Electric Company, the nuclear steam supply system vendor, reviews and approves the procedures for the low power and power ascension test program. liis approval is required by the station procedure administering the Startup i Testing Program prior to the release for performance of any NSSS

startup test procedure.

Emergency procedures are being prepared using the Emergency Procedures Guidelines developed by the Emergency Procedures Subgroup of the BWR Owners .Gropp and the General Electric Company. " These Emergency Procedures will be reviewed by the General Electric Company Site Operations Manager prior to Fuel Load.

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II.K.3.22 Automatic Switchover of Reactor Core Isolation Cooling

System Suction r

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The RCIC system will be modified to automatically switch I

over the suction f m the Condensate Storage Tank to the

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suppression pool upon Condensate Storage Tank low level.

! Implementation of the modification prior to fuel load is j contingent upon timbly delivery of Class IE instrumentation.

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