ML20236N686
| 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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Public Service
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. 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
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3 Document Control Desk.
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'. Washington,-DC 20555 Gentlemen 1
, UPDATED' RESPONSE.
. SAFETY ISSUES: MANAGEMENT SYSTEM j
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HOPE CREEK GENERATING STATION i
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- 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.
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'Should you have any questions, do not hesitate to contact us. 9 41 ;.
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I sincerelyi i
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- s Attachment
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Mr. G. W.
Rivenbark s
USNRC Licensing Project Manager f
Mr.
R. W. Borchardt 4
USNRC Senior Resident Inspector'
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..vj Mr. W. T.
Russell,' 'Adn:inis tra tor j
USNRC Region I.
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-Mr.
D..M.' Scott, Chief J
Bureau of Nuclear Engineering y
Department of Environmental. Protection 380 Scotch Roa'd Trenton, NJ. 08628 gss 8711160298 871103 PDR ADOCK 05000354 I\\
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's ATTACHMENT Tbo attached table has been sevised,from the original ihtormation provided in the letter dated September 23, 1987.
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s d.nmary :
$f7 Item No.
Summary of Change M57833 xThese'five items have been. categorized as not M61401 applicable (N/A) by G. 01. Rivenbark (GWR) of the 3
M61452
.NRC based upon internal NRC review.
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q M61483 t,
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6 5
M61562 p
(
M64592 NRC approval letter dated 4/9/87 is on hold pending
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resolution /of. concerns' raised.by NPDPU, FERC and l
th e.<Sr.C.
No sbhedule yet availablei' l
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M65451 1
Theseitna items were physic' ally satisfied with the M65065 comp 3dtion of the Fall 1,987./outagee' l
Corre'ction ofJ typographical error in schedule.
f M65348 M65730 bpdatebased=onrecentsubmittal (refecence).
Projecte,d! schedule shown requires,hMM2 support.
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n 1A-7 Not applicable based on discussions with
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W. Rivenbark 4
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B-56 Not applicable ba's ed upon information contained "Y
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in referenced doriuments.
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'yo 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 i
M61561 DCRDR License Condition 4/87 C
4/23/87 M61562 Environmental Qualification N/A-GWR M61701 Various Tech Spec Changes 7/86 C
SSER 6, 16 M61702 Turbine Maintenance 7/86 C
SSER 6, 3.5.1.3 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
M65348 Tech Spec MCPR Figure Revision 8/87 C
Am. 9
' 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 A-7 Mark I Long-Term Program N/A GWR A-10 BWR Feedwater Nozzle Cracking N/A GNR B-56 Diesel Generator Reliability N/A GL 84-15 and 4
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
.NMSS-5 Reporting Requirements 10/87 C 10CFR73.71 (10/8/87) i NMSS-7 Requirements for Criminal 4/87 C
10CFR73 History Checks (4/1/87)
NRR-3 Severe Accident Policy Implementation Under NRC development s