ML20011F067
| ML20011F067 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek |
| Issue date: | 02/21/1990 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9003010013 | |
| Download: ML20011F067 (2) | |
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PSEGL
( Public Service EDectric and Gas Company iP,0, Box 236 Hancocks Bridge, New Jersey 08038
- Hope Creek Operations -
9 l-February-21,- 1990-
'U.S..-Nuclear Regulatory Commission
~
JDocument Control Desk
-Washington,-DC 20555'
- 6 Gentlemen:
ANNUAL-REPORT TECHNICAL SPECIFICATION 6.9.1.5 HOPE. CREEK GENERATING STATION DOCKET'NO..50-354 Th'is'_ annual'Jreport' of challenges to Main Steam Line Safety : /..
Relief Valves (SRVs)- is being-submitted pursuant 'to
- the '
requirements of Technical : Specification 6.9.1.5 for-the year:
11989.
During 1989, -Hope-Creek experienced the following-unplanned-s challenges to SRVs-:
'l.-
_On 12/30/89,-- SRVs "H" and "M" lifted automatically _to control reactor _ pressure during the course of a' reactor. scram.
SRV "P" should<haveLopened,_.but did not due toia failed-pressure J switch.
(Ref: LER 89-025-00)._
Pleace note that SRV::"H" and SRV "P". are the lo-lo set SRVs at Hope s
- Creek, and are designed to arm and initially lift at 1047 PSIG.
Additionally, during the 1989 refueling outage, all SRVs twere=
replaced and' lift tested following replacement.- 'All replaced SRVs1 tested satisfactorily.
As-found bench testing of the SRVs which were removed determined the following:
8 SRVs tested 'at a setpoint greater than the acceptance
. criteria of<
1% (SRVs A,C,D,E,K,L,M, and P) as specified in Technical. Specification 3.4.2.1.
These SRVs will be rebuilt-and. tested prior to next scheduled installation (1991 refueling outage).
6 SRVs were within required setpoint tolerances.
f$l iThe Energy People
/j7
- 9003010013 900221 Ch
}Q PDR-ADOCK 05000354 R
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