ML19347F370

Forwards Positions Re post-TMI Requirements Outlined in NUREG-0737, Clarification of TMI Action Plan Requirements. Lists of Specific Items Addressed & Items to Be Addressed in 810530 Ltr Encl

ML19347F370
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	05/15/1981
From:	Navarro J, Novarro J LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19347F371	List: ML19347F370 ML19347F372
References
RTR-NUREG-0737, RTR-NUREG-737 SNRC-563, NUDOCS 8105190086
Download: ML19347F370 (3)

Text

-

LONG ISLAND LIGHTING COM PANY gama,O I. fit'w SHOREHAM NUCLEAR POWER STAT lON P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792

'(-

SNRC-563 7' i 'y' 5:3 3r May 15, 1981 iE E j $& C e\ sc= -=n=

r Mr. Harold R. Denton, Director 3 C7 '

Office of Nuclear Reactor Regulation 1 U.S. Nuclear Regulatory Commission g, ,.g W

Washington, D.C. 20555 SHOREHAM NUCLEAR POWER STATION - UNIT 1 DOCKET NO. 50-322

Dear Mr. Denton:

Forwarded herewith are fifteen (15) copies of our positions related to Post-TMI Requirements outlined in NUREG-0737,

" Clarification of TMI Action Plan Requirements". The twenty-one specific items addr'ssed are listed in Attachment 1 to this letter. Where applicable, our responses to certain NUREG-0578 items (SNRC-503, dated 8/29/80) are superceded by the respective responses contained herein.

This submittal is the second of three submittals dealing with NUREG-0737. The first submittal contained seventeen specific items and was forwarded via letter SNRC-557 dated 4/15/81. The last submittal is scheduled for 5/30/81 and will contain the remaining NUREG-0737 items as listed in Attachment 2.

Very truly yours,

\

^

1 rN-

,c

- ^ ~'c M r i '

//J. P. Novarro p s Project Manager v Shoreham Nuclear Power Station g 7

RWG:mc Attachment cc: J. Higgins k q;Ph)b c

's 3 0 3 ,9 0 0 % #f e

[ o SNRC-563 ATTACHMENT 1 NUREG-0737 ITEMS INCLUDED IN THIS SUBMITTAL I.A.l.2 Shift Supervisor-I.A.l.3 shift Manning I.A.3.1 Revise Scope and Criteria for Licensing Examinations I.C.3 Shift Supervisor Responsibility.

I.C.7 NSSS Vendor Review of Procedures I.C.8 Pilot Monitoring of Selected Emergency Procedures I.D.1 Control Room Design Reviews II.B.2 Plant Shielding II.B.3 Post-Accident Sampling II.F.1 Additional Accident Monitoring Instrumentation II.K.l.10 Operability Status II.K.l.22 Auxiliary Heat Removal System Procedures II.K.l.23 Reactor Vessel Level Indication II.K.3.3 Reporting Safety Relief Valve Failures II.K.3.13 HPCI and RCIC Initiation Levels II.K.3.16 Challenges and Failures to_ Relief Valves II.K.3.18 Modification of ADS Logic II.K.3.24 Space Cooling for HPCI and RCIC II.K.3.25 Power on Pump Seals III.D.3.3 In-Plant I Radiation Monitoring 2

III.D.3.4 Control Room Habitability w

~

i.

I '5 : C' SNRC-563 l

ATTACHMENT 2 NUREG-0737 ITEMS SCHEDULED FOR SUBMITTAL ON 5/30/81 I.A.2.1 Immediate Upgrading of RO & SRO Training and Qualification I.B.l.2 Evaluation of Organization and Management I.C.1 Short Term Accident and Practice Review I.C.6 Verify Correct Performance of Operating Activities I.D.2 Plant Safety Parameter Display. Console I.G.1 Training During Low Power Testing II.B.1 Reactor Coolant System Vents II.B.4 Training for Mitigating Core Damage II.D.1 Relief and Safety Valve Testing Requirements II E.4.2 Containment Isolation Dependability-II.F.2 Instrumentation for Detection of Inadequate Core Cooling II.F.3 Instrumentats for Monitoring Accident Conditions II.K.3.30 Small break LOCA Loads II.K.3.31 Plant-Specific Analysis III.A.l.1 Emergency Preparedness Short Term III.A.l.2 Upgrade Emergency (Based on Security Bldg.)

III.A.2 Emergency Preparedness III.D.l.1 Primary Coolant Outside Containment l

i i

3 M

- , . . , --- y-- -,- m r- ,-, * -, -,