ML20029A846
| ML20029A846 | |
| Person / Time | |
|---|---|
| Site: | Limerick |
| Issue date: | 02/21/1991 |
| From: | Leitch G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9103040372 | |
| Download: ML20029A846 (3) | |
Text
_ _ _. _. _. _. _. _ _.. _.. _ _
J j
s, TS 6.9.1.5.b i
PHILADELPHIA ELECTRIC COMPANY j
UMERICK GENER ATtNG STATION l
P. o, sox A S AN ATOG A, PENN$Yl-V ANI A 19464 (ris) sanit00, txT. 3000 i
o.iasau u. s.titew February 21, 1991-m..........
50-353 l
j LLeense Nos. NPF-39 NPF-85 j
r i
U.
S. Nuclear Regulatory Commission 2
Attn Document Control Desk Washington, DC 20555 Subjecti Limerick Generating Station, Units 1-and 2 f
1990 Annual Report of All Challenges to Safety / Relief Valves, Unit 1 - Report No. 6 and Unit 2 - Ruport No. 2 Gentlement This letter transmits the Limerick Generating Station, Units 1 and 2 1990 Annual Repor', of All Challenges to Safety / Relief Valves.
This report represents. Report No.- 6 for Unit 1 and Report-j No. 2 for Unit 2, as required by Technical Specification 6.9.1.5.b.
The definition of challenges considered in this L report is--the i
automatic opening of main steam system safety / relief -valves in-i response to high reactor prescuro, Unit 1 (Recort No. 6) i During 1990, there were no-automatic openings of the_ main steam safety / relief valves in. response to high reactor pressure.
Surveillance testing ' of the five (5) safety. relief valves associated with the ' Automatic Depressurization : System was-conducted in December 1990 with satisfactory results, as part l
of pre?aration - for restart of the unit following the third-refuel:.ng outage.
t t
( ll 910304037: o'e221 L
PDR ADOCh
'0352 l
R 1R (O
3913026820 l
Unit 2 (Recort No. 2) l During 1990, there was one ovent which automatically oponod the main steam safety / relief valves in responso to high reactor pressure.
On September 10, a full NSSSS Group I MSIV isolation occurred due to an instrument failure.
This occurred when a plant oporator was reading the Turbine Enclosure Stoam Tunnel Temperature Div 4 switches in who Auxiliary Equipment Room, concurrent with I&C testing of the NSSSS Main steam lino Div 1 temperature instrumentation.
Following the MSIV isolation, the roactor scrammed with the reactor vessel level decreasing to -48" and pressuro rising to 1112 psig, llPCI and RCIC both started, but due to the short duration of the initiation signal, only RCIC injected to the reactor vessel.
IIPCI was run in the full flow test modo.
The
'N' SRV opened initially on the pressure spike and the K, M,
}!, S and E SRV's woro cyclod to control reactor pressuro.
The plant ontored OPCON 4 at 2209 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.405245e-4 months <br />.
On Septotabor 11, I&C replaced the faulty temperaturo switch (TTS-025-2160) and satisfactorily performed a cal / functional test.
i Documentation of all challengos to the main steam system safety / relief valvoo has been submitted as part of the monthly operating report in ordor to comply with Technical Specification 6.9.1.6.
Should you have any questions concerning this_ matter, please contact us.
Very 1
- yours, KWM/kk cc T. T. Martin, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS bcct S. A. Hadfield R. M. Krich/RWG See Distribution Schedule i
______-2.-
DATE 02/25/91 09: 49 NRMS DOCUMENT CONTROL FORM SE0VENCE O 39130D6BRC GAFETY - RELIEF VALVE CHALLENCES REPORT STATION LGS
- e******************************v************
- ASST TO EXEC VP-NUCL MO/S24-2 01 I** PLANT MANAGER - PD PD/A4-19 01 I*
- CHAIRMAN - NRD CD/53A-1 01 I**REPORTINO BUPVR.-LOS LGS /338 01 1*
- CONSULTANT - NRD MO/524-1 01 I *
- SUP T.
ISEE-LOS SD-4-2 01
- EXECUTIVE ASST - NRD CD/51A-1 05 I**DIR.
RAD PROT CD/51A-5 01 o
- SECRETARY - NRD CD/53A-1 01 !**DIXON, J.
LOS/AD-1 01
- VP.
LIMERICK LGS-2OO 01 I**DIR, LICENSING SECT CD/52A-3 01 I*
- VP.
NUC ENQ/ SERVICES CD/63C-1 01 I**KIRCH, R,
MO/S7-1 01 I*
- VP.
NUCLEAR ENGR CD/53C-1 01 1** LGS SUPPORT SUPV LOS/333 01 1*
- VP.
PDAPS PD/SMO-1 01 I** SUPT OPER - LGB LOS/AD-1 01 1*
- MOR.
ENGINEERING CD/63D-5 01 Id* SUPT. TECH. - LGS LQB/A5-1 01 1*
- MOR.
PD GUALITY DIV PD/D-2-N 01 I** SUPT. TRAINING-LOS LOS-LTC 01 1*
- MGR.
GA PERF ASSESS CD/53A-1 01
- PLANT MANAGER - LOS LGB/A5-1 01 I**-
REGUESTS FOR CHANGES TO THIS DISTRIDUTION LIST MUST DE ADDRESSED TO THE ORGANIZATION RESPONSIDLE FOR ORIGINATING THE ATTACHED DOCUMENT (SEE NUCLEAR RELATED DOCUMENT REGISTER (NRDR) FOR RESP. ORG. ). THE RESP. ORO. WILL AUTHORIZE THE LOCAL DAC SUPERVISOR TO MAKE THE NECESSARY CHANGES.
ATTACHED IS A COPY OF:
REPORTNO 0006 0002 DATE O2/21/91 32 COPIES REQUIRED FOR DISTRIDUTION FEB 251991 LPd t