ML20199E993
| ML20199E993 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/20/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NLR-N86068, NUDOCS 8606240164 | |
| Download: ML20199E993 (2) | |
Text
.
.A Pubhc Servke Electric and r,as Company l
i Cerbin A. McNeill, Jr.
Public Service Electric and Gas Cv ipiny P.O. 80x 236, H ancocks Bndge.NJ 08038 609 339-4800
%Ce President -
Nuc' ear June 20, 1986 NLR-N86068 Director of Nuclear Reactor Regu_a+. ion United States Nuclear Regulatory Cn.nmission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate #3 Division of BWR Licensing Dear Ms. Adensam GENERIC LETTER 83-28 (RE: SALEM ATWS EVENTS)
HOPE CREEK GENERATING STATION I
DOCKET NO. 50-354 In response to NRC request letter dated June 9, 1986, Public Service Electric and Gas Company (PSE&G) hereby submits the attached table indicating implementation of required actions to Generic Letter 83-28 for the Hope Creek Generating Station.
If you have any questions, do not hesitate to contact us.
Sincerely,
{
Attachment l
C Mr. D.
- h. Wagner Licensing Project Manager Mr.
R.
W.
Borchardt Senior Resident Inspector h
I 8606240164 860620 T'
1 PDR ADOCK 05000354 l\\
p FDR
l HOPE CREEK GENERATING STATION IMPLEMENTATION OF REQUIRED ACTIONS TO GENERIC LETTER 83-28 i
i i
ITEM DESCRIPTION IMPLEMENTATION L
1.1 POST-TRIP REVIEW Procedures available i
{
(Program description and procedure) and implemented.
r I
1.2 POST-TRIP REVIEW Capabilities I
j (Data and information capability) availab1q and implemented.
)
2.1 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE Proqrams available j
(Reactor Trip System components) and implemented.
7 1
l 2.2 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE Programs available (Programs for all safety-related components) and implemented.
1 j
3.1.1 POST-MAINTENANCE TESTING Procedures and
)
]
(Reactor Trip System components) administrative i
controls available i
and implemented.
l i
3.1.2 POST-MAINTENANCE TESTING Procedures and (Reactor Trip System components) administrative j
controls available and implemented.
3.1.3 POST-MAINTENANCE TESTING Completed.
f 1
(Reactor Trip System components) 3.2.1 POST-MAINTENANCE TESTING (Same as 3.1.1)
(All other safety-related components)
I i
3.2.2 POST-MAINTENANCE TESTING Completed.
(All other safety-related components) i 3.2.3 POST-MAINTENANCE TESTING (Same as 3.1.1)
(All other safety-related components) t 4.5.1 REACTOR TRIP SYSTEM RELIABILITY Technical Specifi-i 2
(System functional testing) cations availabJe and implemented.
i 4.5.2 REACTOR TRIP SYSTEM RELIABILITY Technical Specifi-t j
(Systen functional testing) cations available j
and implemented.
i
)
4.5.3 REACTOR TRIP SYSTEM RELIABILITY BWR Owner's Group i
(System functional testing)
Report NEDC-30844
[
j has been submitted to the NRC.
See i
letter from PSE&G i
to NRC dated j
May 21, 1985.
(Implementation pending completion of NRC review scheduled 9/30/86).
l