Similar Documents at Salem |
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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0261998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 1.With 990115 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr ML18106A9831998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Salem,Unit 2.With 981214 Ltr ML18106A9801998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Salem,Unit 1.With 981214 Ltr ML18106A9641998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Salem,Unit 2. with 981112 Ltr ML18106A9631998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Salem,Unit 1. with 981112 Ltr ML18106A9151998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Salem,Unit 2.With 981012 Ltr ML18106A9131998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Salem,Unit 1.With 981012 Ltr ML18106A8751998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Salem Generating Station,Unit 2.With 980915 Ltr ML18106A8741998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Salem Unit 1.With 980915 Ltr ML18106A8161998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Salem,Unit 1. W/980817 Ltr ML18106A8151998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Salem,Unit 2. W/980817 Ltr ML18106A7151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Salem,Unit 2. W/980715 Ltr ML18106A7141998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Salem,Unit 1. W/980715 Ltr ML18106A6541998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Salem Unit 1. W/980615 Ltr ML18106A6531998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Salem Unit 2. W/980615 Ltr ML18106A6121998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Salem Generating Station,Unit 1.W/980515 Ltr ML18106A6111998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Salem Unit 2. W/980515 Ltr ML18106A5561998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Salem,Unit 1. W/980415 Ltr ML18106A4591998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Salem Unit 2. W/980415 Ltr ML18106A3771998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Salem Generating Station,Unit 1.W/980316 Ltr ML18106A3761998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Salem Generating Station,Unit 2.W/980316 Ltr ML18106A3281998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Salem,Unit 2. W/980217 Ltr ML18106A3271998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Salem,Unit 1. W/980217 Ltr ML18106A2721997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Salem,Unit 2. W/980115 Ltr ML18106A2711997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Salem Generating Station,Unit 1.W/980115 Ltr ML18106A2081997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Salem,Unit 1. W/971212 Ltr ML18106A2071997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Salem,Unit 2. W/971212 Ltr ML18102B6811997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Salem,Unit 2.W/ 971117 Ltr ML18102B6801997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Salem,Unit 1.W/ 971117 Ltr ML18102B6271997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Salem,Unit 2. W/971015 Ltr 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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0 PS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department 1.....-;
.. *** December 14, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of November 1990 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, General Manager -
Salem Operations RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4
-~---The __~_D~_r:_g_y Peopk_ ____ _
. (~ 90:1.2:2101:3::: 901130 1 2J PDR R
ADOCK 05000272 PDR 95-2168 (1 OOM) 12-84
.,ERAGE DAILY UNIT POWER L~L Docket No.: 50-272 Unit Name: Salem #1 Date: 12/10/90 Completed by: Art Orticelle Telephone: 339-2122 Month November 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1112 17 1095 2 1112 18 1087 3 1080 19 1106 4 1112 20 1116 5 1096 21 1061 6 1114 22 1109 7 1091 23 1102 8 1107 24 1086 9 1046 25 1095 10 505 26 1090 11 487 27 1112 12 493 28 1107 13 577 29 1107 14 592 30 1109 15 596 31 16 747 P. 8.1-7 Rl
OPERATING DATA REPORT e Docket No: 50-272 Date: 12/10/90 Completed by: Art Orticelle Telephone: 339-2122 Operating Status
- 1. Unit Name Salem No. 1 Notes
- 2. Reporting Period November 1990
- 3. Licensed Thermal Power (MWt) 3411
- 4. Nameplate Rating (Gross MWe) 1170
- 5. Design Electrical Rating (Net MWe) 1115
- 6. Maximum Dependable Capacity(Gross MWe) 1149
- 7. Maximum Dependable Capacity (Net MWe) 1106
- 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA
- 9. Power Level to Which Restricted, if any (Net MWe) N/A
- 10. Reasons for Restrictions, if any NA This Month Year to Date Cumulative
- 11. Hours in Reporting Period 720 8016 117649
- 12. No. of Hrs. Rx. was Critical 720 5310.9 76219.5
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line 720 5127.8 73823.5
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 2217345.6 16426324.8 231527250.8
- 17. Gross Elec. Energy Generated (MWH) 733970 5402240 76863600
- 18. Net Elec. Energy Gen. (MWH) 701944 5141397 73153107
- 19. Unit Service Factor 100 64.0 62.7
- 20. Unit Availability Factor 100 64.0 62.7
- 21. Unit Capacity Factor (using MDC Net) 88.1 58.0 56.2
- 22. Unit Capacity Factor (using DER Net) 87.4 57.5 55.8
- 23. Unit Forced Outage Rate 0 36.0 22.7
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling outage scheduled to start 2/9/91 and last 55 days.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA 8-l-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1990 DOCKET NO.: _5::.;0"---=2"-7=-2~--
UN IT NAME: _s~a:..:l:..;;e""'m'""'#,_.,1;.--
DATE: 12/10/90 COMPLETED BY: Art Orticelle TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 1 2 NO. DATE TYPE (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0089' 11/09/90 F 71.4 B 5 ------- CH PUMPXX #11 STEAM GEN. FEED PUMP 0090 11/12/90 F 48.9 B 5 ------- CH PUMP XX #11 STEAM GEN. FEED PUMP 0092 11/14/90 F 37.9 B 5 ------- CH INSTRU #11 STEAM GEN. FEED PUMP e
1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-.Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)
E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9"0ther H-Other (Explain)
SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10,. 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 890412004 1 lA RX TRIP BRKR FAILURE DESCRIPTION: REPLACE UV TRIP DEVICE 900220102 1 11 CHILLER COND. PUMP FAILURE DESCRIPTION: BEARING HOUSING OIL LEAK - REPAIR 900322153 1 13 CHILLER COND. PUMP FAILURE DESCRIPTION: BEARING OIL LEAK - REPAIR 900919104 1 16SW25 FAILURE DESCRIPTION: VALVE STEM IS SEPARATED FROM THE DIAPHRAGM - REPAIR 901009117 1 12SW383 FAILURE DESCRIPTION: LEAKING SPOOL DOWNSTREAM -
REPLACE SPOOL 901119140 1 RMS 1R45A FAILURE DESCRIPTION: PLANT VENT SAMPLER FAILED -
TROUBLESHOOT AND REPAIR 901120089 1 1SW309 FAILURE DESCRIPTION: HOLE IN THE UPSTREAM FLANGE -
REPAIR
10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).
ITEM
SUMMARY
A. Design Change Packages lEC-3039 Pkg. 2 "Steam Generator Flow Rate (Steam) Instrument Loop Enhancement" - The purpose of this design change is to modify the primary and secondary steam flow input signals to the Reactor Protection Cabinets. A total of eight channels will be affected by this change. A new summator will be added to the steam flow loops. The existing square root extractors will be eliminated from the Reactor Protection Cabinets to provide room for the summator cards. The existing multipliers will be rewired to provide a dual multiplier and square root extraction function. (SORC 90-153) lEC-3049 Pkg. 1 "1R13A and 1R13B Setpoint Basis" - The purpose of this design change is to provide the design basis for allowing the setpoints for the 1Rl3A and 1R13B monitors to be revised. These detectors had been replaced with a different model during the implementation of DCP 1EC-1794A. (SORC 90-153) lSC-2160 Pkg. 1 "C02 System Automation" - The purpose of this design change is to modify the manually actuated C02 Fire Suppression System to include automatic actuation circuitry. To accomplish this, new spot thermal detection will be added to the affected rooms. The new thermal type detectors will be utilized for automatic C02 system actuation. The existing ionization type detection zones will remain in place but will be rewired to provide an "early warning" signal only. (SORC 90-154)
*~-----------------1 I
I I
10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)
ITEM
SUMMARY
lSC-2161 Pkg. 1 "C02 System Automation" - The purpose of this design change is to modify the manually actuated C02 Fire Suppression System to include automatic actuation circuitry. To accomplish this, new spot thermal detection will be added to the affected rooms. The new thermal type detectors will be utilized for automatic C02 system actuation. The existing ionization type detection zones will remain in place but will be rewired to provide an "early warning" signal only. (SORC 90-154) lSC-2154 Rev. 1 "Control Room Modifications" - The purpose of this design change package (DCP) is to perform modifications to the Salem Unit 1 Control Room Consoles and Recorder Panels to correct Human Engineering Deficiencies to comply with NUREG 0700 and the Salem Human Factors Guidelines.
This DCP is also to comply with the requirements of Specification S-C-VARX-MDS-0155 and licensing commitments for Salem Generating Station. (SORC 90-155) lEC-3056 Pkg. 1 "1R13 C, D & E" - The purpose of this design change package (DCP) is to establish and implement new setpoints for 1R13C, 1R13D & 1R13E Containment Fan Coil Unit effluent radiation monitors. (SORC 90-158)
B. Procedures and Revisions lIC-18.1.013 "Train A & B Reactor Trip Breaker Operability Test" Rev. 3 - The purpose of this revision is incorporate a change in the NRC reporting requirements from one (1) hour to thirty (30) days and provide a method of testing with a loss of the P-250 computer. (SORC 90-150)
NC.NA-AP.ZZ-0003(Q) "Document Control Program" Rev. 0 - This procedure describes the program for the control of Nuclear Department documents and the method of distribution and maintenance. (SORC 90-153)
10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)
ITEM
SUMMARY
Sl.OP-PT.SW-OOll(Q) "11 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)
Sl.OP-PT.SW-0012(Q) "12 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)
Sl.OP-PT.SW-0013(Q) "13 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)
Sl.OP-PT.SW-0014(Q) "14 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)
Sl.OP-PT.SW-0015(Q) "15 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)
10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)
ITEM
SUMMARY
C. *Deficiency Reports (DRs)
SMD 90-301 This disposition addresses the repair of spool 1-SW-121 which is part of PSE&G Pipe Specification 1S27C which is Nuclear Class III, Seismic Class I and Safety Related.
Essentially, a window will be cut in the pipe and a replacement piece will be fabricated and welded in. Performance of this work requires a Code Job. All work shall be accomplished in accordance with the Nuclear Department Repair Program and the Welding and Brazing Manual.
(SORC 90-156)
D. Temporary Modifications (TMODS)
STD 90-121 This TMOD provides for the anchorage of the non-saf~ty related chemical addition tank support to prevent its' potential seismic interaction with safety related (i.e., component cooling piping and auxiliary feedwater) equipment. (SORC 90-154)
STD 90-120 The purpose of this temporary modification is to provide a means of chemical (hydrazine or ammonia) addition to the Unit 1 Auxiliary Feedwater System. (SORC 90-155)
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 NOVEMBER 1990 SALEM UNIT NO. 1 The Unit began the period operating at 100% power. Power was reduced to 52% on 11/09/90 to repair No. 11 Steam Generator Feedwater Pump (SGFP) thrust bearing and various leaks in the feedwater heater drains. On 11/16/90, following completion of the repairs, the Unit was restored to full power and continued to operate at essentially full power throughout the remainder of the period.
REFUELING INFORMATION DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 MONTH NOVEMBER 1990
- 1. Refueling information has changed from last month:
YES NO X
- 2. Scheduled date for next refueling: February 9, 1991
- 3. Scheduled date for restart following refueling: April 10, 1991
- 4. a) Will Technical Specification changes or other license amendments be required?:
YES NO NOT DETERMINED TO DATE ~-x~-
b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:
YES NO x If no, when is it scheduled?: January 1991
- 5. Scheduled date(s) for submitting proposed licensing action:
N/A
- 6. Important licensing considerations associated with refueling:
- 7. Number of Fuel Assemblies:
- a. Incore 193
- b. In Spent Fuel Storage 588
- 8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
- 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2001 8-1-7.R4