ML20236N686

Forwards Updated Response to Re Safety Issues Mgt Sys,Based on Discussions W/Gw Rivenbark.Info Contains Summary of Changes Made & Basis for Each Change

ML20236N686
Person / Time
Site:	Hope Creek
Issue date:	11/03/1987
From:	Corbin McNeil Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NLR-N87211, NUDOCS 8711160288
Download: ML20236N686 (3)

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<a- . Electric and Gas

, . Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339 4800 -

- Stnior Vice President -

Nuclear ,

November 3, 1987 '

NLR-N87211 United States Nuclear Regulatory Commission / 3 Document Control Desk. 4

'. Washington,-DC 20555 ';

Gentlemen 1

, UPDATED' RESPONSE.

. SAFETY ISSUES: MANAGEMENT SYSTEM , j y HOPE CREEK GENERATING STATION i 'r /;

DOCKET NO. 50-354 ^

Public Service' Electric and_ Gas Company.(PSE&G) has reviewed'the

letter from C. A..McNelli,..Jr. (PSE&G) dated. September'23, 1987,

based.upon discussions with..Mr. G . -. W . Rytonbark'(NRC) and offers

.the attached updated response. The attat.:hed informa tion . contains , < <

. ,: .c a summary of.the, changes made and a bas,in for eachLchange. q / '

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'Should you have any questions, do not hesitate to contact us. 9 41 ; .

\ I sincerelyi  : ,

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Attachment , , ./ J

' ji C Mr. G. W. Rivenbark s  ;

USNRC Licensing Project Manager ', ,

f Mr. R. W. Borchardt .

4 USNRC Senior Resident Inspector' [ ,

,l, ,sq

. .vj Mr. W. T. Russell,' 'Adn:inis tra tor j USNRC Region I. Y,

s. . ,Ra, c

-Mr. D. .M.' Scott, Chief J Bureau of Nuclear Engineering  ; y '

Department of Environmental. Protection

.I 380 Scotch Roa'd '

Trenton, NJ. 08628 gss 8711160298 871103 PDR '

>- P ADOCK 05000354 I\

PDR '.

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, . 's ATTACHMENT Tbo attached table has been sevised,from the original ihtormation provided in the letter dated September 23, 1987./

In s d.nmary :

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Item No. Summary of Change

$f7 >

M57833 xThese'five items have been. categorized as not 3

M61401 applicable (N/A) by G. 01 . Rivenbark (GWR) of the y

M61452 .NRC based upon internal NRC review. i q M61483 t ,

5 M61562 .

( p 6

(

M64592

" NRC approval letter dated 4/9/87 is on hold pending )

resolution /of. concerns' raised.by NPDPU, FERC and  !

l th e .<Sr.C . No sbhedule^

yet availablei' a , l

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Theseitna items were physic' ally satisfied with the  ;

M65451 1 '

M65065 comp 3dtion of the Fall 1,987./outagee' l

Corre'ction ofJ ftypographical error in schedule.

M65348 M65730 bpdatebased=onrecentsubmittal (refecence).

n Projecte,d! schedule shown requires,hMM2 support. j 9

1A-7 Not applicable based on discussions with 4 '

~A-10 G. W. Rivenbark ,

f. .. i Not applicable ba's ed upon information contained "Y ( . '; ; B-56

, s' in referenced doriuments.

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NMSS-2 Updato based upon additional information provided NRR-3 by G.<W. Rivenbark f

NMSS-5 General schedular update and identification of NMSS-7 reference documents /

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~4 TABLE l-lITD4 NO. ITEM DESCRIPTION SCHEDULE REFERENCE

.M65451 SRV Acoustic ~ Monitor 10/87 C- Am. 5 i .M57833 Allegations & Investigations N/A GWR M61254- Ane ndme nt 15 - 5/86 C 5/19/86 '

M61306 Solid Radwaste. System 12/07 M61307 Solid State. Logic Modules 3/88 10/15/86 M61397' Purge Valve Operability 3/88 3/19/87 M61398 Single Loop Operation 8/87 C Am. 3 l M61399 Fire Protection Tech Specs 7/86 C LC 2C(7) l

'M61401 HPCI/RCIC Setooint Separation N/A GWR

,M614511 Partial-Feedwater Heating 7/86 C LC 2C(ll)

-M61452' Loss of Offsite Power N/A GWR ,

M61483 Electrical Distribution System N/A GWR M61561 DCRDR License Condition 4/87 C 4/23/87 i M61562 Environmental Qualification N/A- GWR Various Tech Spec Changes 7/86 C SSER 6, 16  !

M61701 Turbine Maintenance 7/86 C SSER 6, 3.5.1.3 M61702 M61704 Review Administration Add'tl info needed M63092- Inservice Inspection Program 3/88 10/10/86 M63994 Process-Control Program 11/86 C NRC Ltr 4/9/87 M64592 Restructuring of Atlantic On Hold NRC Ltr 4/9/87 M64740 Emergency Bus Undervoltage 3/88 Am. 7 M64949 Suppression Chamber Water Level 12/87 7/31/87 M64950 Secondary Containment Dampers 7/87 C Am. 6 M65013 SPDS License Condition 7/88 8/18/87 M65065 LLRT Appendix J Exemption 10/87 C Am. 4 M65066 LLRT Tech Spec Change See M65065 M65228 DCRDR Supplement III Report See M61561

.M65347 Revision to Section Numbers 9/87 C Am. 10 ,

3 Tech Spec MCPR Figure Revision 8/87 C Am. 9 M65348

' M65730 Inservice Test Program 11/87 9/21/87 75-(B-77) Salem ATNS - Item 2.1 C 8/24/87 75 (B-86) Salem ATWS - Item 2.2 C 5/21/85 I 75 (B-93) Salem ATWS - Item 4.5.2, 4.5.3 C 5/21/85 Mark I Long-Term Program N/A GWR A-7 BWR Feedwater Nozzle Cracking N/A GNR A-10 GL 84-15 and 4 B-56 Diesel Generator Reliability N/A SER 8.3.2.4

& App. C (A-44) )

MPA-A-20 10CFR50.62 Operating Reactor Reviews 12/87 7/14/87 and NRC l Ltr 10/14/37 -j NMSS-2 Access Authorization 12/86 C 12/2/87  :

NMSS-3 Misc. Amend. Concerning Physical 9/87 C 9/4/87 i l

Protection NMSS-4 Searches of Individuals 9/87 C 9/4/87 l Reporting Requirements 10/87 C 10CFR73.71

.NMSS-5 (10/8/87) i Requirements for Criminal 4/87 C 10CFR73 NMSS-7 History Checks (4/1/87)

NRR-3 Severe Accident Policy Implementation Under NRC development

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