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Category:ANNUAL OPERATING REPORT
MONTHYEARML20196K1801998-06-30030 June 1998
Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with
ML20133B6541996-06-30030 June 1996
Annual 10CFR50.59 Rept 950701-960630 for Lgs,Units 1 & 2
ML20079B7631994-06-30030 June 1994
Annual 10CFR50.59 Rept,930701-940630
ML20059E7121993-06-30030 June 1993
Annual 10CFR50.59 Rept 920701-930630, for LGS Units 1 & 2
ML20127C5561992-06-30030 June 1992
Annual Plant Mod Rept Jul 1991-June 1992 for Limerick Generating Station Units 1 & 2
ML20094H0541992-02-21021 February 1992
1991 Annual Rept of All Challanges to Safety Relief Valves, Unit 1 - Rept 7 & Unit 2 - Rept 3
ML20059G3331990-06-30030 June 1990
Annual Plant Mod Rept Jul 1989-June 1990
ML20006B9251990-01-24024 January 1990
1989 Annual Rept of All Challenges to Safety/Relief Valves Units 1 & 2, Repts 5 & 1 for Units 1 & 2,respectively
ML20246L4111989-06-30030 June 1989
Annual Plant Mod Rept, Jul 1988 - June 1989
ML20153D7541988-06-30030 June 1988
Annual Plant Mod Rept,Jul 1987 - June 1988
ML20236Y2281987-06-30030 June 1987
Annual Plant Mod Rept, Jul 1986 - June 1987
ML20205F2211987-03-23023 March 1987
Rev 1 to 1986 Annual Rept of All Challenges to Safety/Relief Valves for Facility as Required by Tech Spec 6.9.1.5.b
ML20214W2291986-06-30030 June 1986
Annual Plant Mod Rept,Jul 1985 - June 1986
ML20140F3051986-02-27027 February 1986
Annual Rept of All Challenges to Safety/Relief Valves,Per Tech Spec 6.9.1.5.b.No Automatic Openings of Main Steam Sys Safety Valves in Response to High Reactor Pressure Occurred During 1985.Related Correspondence
1998-06-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with
ML20217A1691999-09-22022 September 1999
Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20212A8861999-09-13013 September 1999
Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01
ML20212A4481999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With
ML20211E9891999-08-20020 August 1999
LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5
ML20210L7051999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With
ML20209G0211999-06-30030 June 1999
GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation
ML20209D7741999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2
ML20207H8331999-05-31031 May 1999
Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam
ML20195G4651999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2
ML20209D7791999-05-31031 May 1999
Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2
ML20195B3021999-05-0606 May 1999
Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6
ML20206N2901999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With
ML20195G4761999-04-30030 April 1999
Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2
ML20206D8971999-04-22022 April 1999
Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8
ML20205N8341999-04-0101 April 1999
Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified
ML20205N9311999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With
ML20204G9851999-03-11011 March 1999
Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2
ML20207J7461999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With
ML20199G2371999-01-31031 January 1999
Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept
ML20199L5301999-01-19019 January 1999
Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331
B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998
Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1
ML20205K0381998-12-31031 December 1998
PECO Energy 1998 Annual Rept. with
ML20199F9611998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With
ML20198C7151998-12-10010 December 1998
Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8
ML20198A3871998-12-10010 December 1998
Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves
ML20206N4061998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With
ML20199E3281998-11-23023 November 1998
Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5
ML20195C9771998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With
ML20154H5691998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Limerick Generating Station,Units 1 & 2.With
ML20151X3511998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Limerick Generating Station Units 1 & 2.With
ML20237F0291998-08-27027 August 1998
Special Suppl Rept:On 960425,one Loose Part Detection Sys (Lpds) Was Identified to Be Inoperable.Initially Reported on 960531.Caused by Loose Parts Detector Module.Repairs Performed & Intermittent Ground No Longer Present
ML20237D1041998-08-17017 August 1998
Books 1 & 2 of LGS Unit 1 Summary Rept for 960301-980521 Periodic ISI Rept 7
ML20237A7761998-08-10010 August 1998
SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode
ML20236X7641998-07-31031 July 1998
Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2
ML20237B4711998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Limerick Generating Station,Units 1 & 2
ML20236N6751998-07-0909 July 1998
Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps
ML20151Z4881998-06-30030 June 1998
GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2
ML20236P9781998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Limerick Generating Station,Units 1 & 2
ML20196K1801998-06-30030 June 1998
Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with
ML20249B3501998-06-11011 June 1998
Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5
ML20249A5331998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Limerick Units 1 & 2
ML20247M7071998-05-14014 May 1998
Safety Evaluation Supporting Amend 128 to License NPF-39
ML20217Q5101998-05-0404 May 1998
Safety Evaluation Supporting Amend 127 to License NPF-39
ML20247H5071998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Limerick Generating Station
ML20216F3601998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Limerick Generating Station,Units 1 & 2
ML20217M0791998-03-31031 March 1998
Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively
ML20217D5701998-03-20020 March 1998
Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010
ML20216F9471998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for Limerick Generating Station,Units 1 & 2
ML20216F3471998-02-28028 February 1998
Revised Monthly Operating Rept for Feb 1998 for Limerick Genrating Station,Unit 1
1999-09-30
[Table view] |
Text
f ,5 C
1 TS 6.9.1.5.b c
3904031070 t~ =.
PHILADELPHIA ELECTRIC COMPANY L,lMERICK GENER ATING ST ATION P. O. BOX A SAN ATOG A, PENNSYLV ANI A 19464 (215) 3271200. EXT, 3000 onanau u. i. mew m . ....... ,
January 24, 1990
- ,..m...........,....
50-353 f- License Nos. NPF-39 NPF-85 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
LimerickL Generating Station, Units 1 and 2 1989 Annual Report of All Challenges to Safety / Relief Valves, Unit 1 - Report No. 5 and Unit 2 - Report No. 1 a
Gentlemen:
This letter transmits the Limerick Generating Station, Units 1 and 2 1989 Annual Report of All Challenges to- Safety / Relief Valves. This report represents Report No. 5 for Unit 1 and Report
- No. l' for' Unit 2, as required by Technical Specification 6.9.1.5.b. .
The definition of challenges considered in this report is the ]
l automatic opening of main steam system safety / relief. valves in e response.to high reactor pressure. q t I E
Unit 1 (Report No. 5) 1 i
, _During_1989, there were no -automatic operings , 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 May 1989 with satisfactory results, as part of preparation for restart of the unit following the second ,'!
refueling outage.
1 900206009s 900124
{DR ADOCK 05000352 PDC
[
. . lll -
unit 2 rRecort No. n 3904031070 During 1989, there was one event which automatically opened the main steam safety / relief valves in response to high reactor pressure.
On December 1 during the Main Steam Isolation Valve closure startup test, several Unit 2 Main Steam Relief Valves (MSRV's) were challenged. During the initial pressure increase, the
'2D', '2H', and '2S' MSRV's lifted per design reducing reactor pressure. After the three MSRV's closed, reactor pressure increased again and the '2B', '2D', '2F', '2H', '2K', '2M',
'2N' and '2S' MSRV's lifted. The eight MSRV's closed per
-design following a reduction in reactor pressure. A subsequent increase in reactor pressure was terminated when the '2K' MSRV was intentionally opened manually by the control room operator. Following closure of the '2K' MSRV, reactor pressure was controlled using High Pressure Coolant Injection and Reactor Core Isolation Coolants.
Additionally, the relief valves were cycled manually as part of the startup test program in September, 1989.
Documentation of all challenges to the main steam system safety / relief valves has been submitted as part of the. monthly operating report in order to comply with Technical Specification
'G.9.1.6.
Should you have any questions concerning this matter, please contact us.
Very t u ]yours,
/ ,
f KWM/kk
'cc: William 4 T. Russell,-Administrator,'-Region I, USNRC-T. J.-Kenny,-USNRC Senior Resident Inspector, ISS
DATE 01/25/90 14: 20' NRMS DOCUMENT CONTROL FORM SECUENCE O 3904031070 O e. ,
! SAFETY - RELIEF VALVE CHALLENIES I
CTAT16N' ' LCS coco ****************************************************************************-
.oACST~TO EXEC VP-NUCL MO/E24-2 01 1*
CCHAIRMAN - NRB CB/53A-1 01 I**MGR. GA PERF ASSESS CB/53A-1 01 1*
CCONSULTANT - NRB MO/S24-1 01 I** PLANT MANAGER - LCS LGS /AS-1 01 I*
cEXEC VP NUC CB/52C-7 01 I** PLANT MANAGER - PB PB/A4-1S 01 1*
CEXECUTIVE ASST - NRB CB/53A-1 05 I**CORRESP RELEASE PT LGS /T2-4 01 I*
O~ECRETARY - NRB CB/53A-1 01 I**DIR. RAD PROT CB/51A-5 01 1*
OVP. LIMERICK LCS-2OO 01 I**DIR. LICENSING SECT CB/52A-5 01 I*
OVP. NUC SERVICES CD51A-1 01 2** LGS SUPPORT SUPV LGS /333 01 1*
CVP. NUCLEAR ENGR CB/53C-1 01 I CVP. PBAPS PB/SMO-1 01 1** SUPT. OPERATIONS-LCS LCS/AS-1 01 I*
J. D/xCA/ 85-/ DJ '
M / Q A'd Af S'/-/ 1 I** SUPT. TECH. - LCS LCS/A5-1 01 I*
, CMCR. ENGINEERING CB/63B-5 01-I** SUPT. TRAINING-LCS LGS-PPC 01 I*
\ SUPT ISEb _LtrS &3 4-2. 01 2**
- l(T b obolo*gfiN G &W / f*fr 33D 0I
- REtVESTS FOR CHANGES TO THIS DISTRIBUTION LIST MUST BE ADDRESSED TO'THE ORGANIZATION RESPONSIBLE FOR ORIGINATING THE ATTACHED DOCUMENT (SEE NUCLEAR RELATED DOCUMENT REGISTER (NRDR) FOR RESP. ORG. ) . THE RESP. OR G. WILL AUTHORIZE THE LOCAL DAC SUPERVISOR TO MAKE THE NECESSARY CHANGES.
-C ATTACHED IS A COPY OF:
REPORTNO 0005 0001 DATE 01/24/90 32 COPIES REGUIRED FOR DISTPIBUTION W
.. .
