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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Public*Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 14, 1994 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 January 1994 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, ager -
tions 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 Energy People ______ - - ----- ----- -- -, ----.....
0p*~~21 ~g5g~ 6~86~~72 1 PDR 95-2189 (10M) 12-89 R --~*~~-*-;;;:.
~VERAGE DAILY UNIT POWER L~L Docket No.: 50-272 Unit Name: Salem #1 Date: 02/10/94 Completed by: Mike Morroni Telephone: 339-2122 Month January 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl
e OPERATING DATA REPORT e Docket No: 50-272 Date: 02/10/94 Completed by: Mike Morroni Telephone: 339-2122 Operating Status
- 1. Unit Name Salem No. 1 Notes
- 2. Reporting Period January 1994
- 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) NIA
- 10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative
- 12. Hours in Reporting Period 744 744 145441
- 12. No. of Hrs. Rx. was Critical 118.2 118.2 95250.17
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line 0 0 91887.84
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 6895.2 6895.2 290779209.2
- 17. Gross Elec. Energy Generated (MWH) 0 0 96535970
- 18. Net Elec. Energy Gen. (MWH) -17717 -17717 91919836
- 19. Unit Service Factor 0 0 63.2
- 20. Unit Availability Factor 0 0 63.2
- 21. Unit Capacity Factor (using MDC Net) 0 0 57.1
- 22. Unit Capacity Factor (using DER Net) 0 0 56.7
- 23. Unit Forced Outage Rate 0 0 21.0
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
None.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Unit returned to service on 2/2/94.
8-1-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1994 DOCKET NO. :_,5'"-"0;..,-*=27'-=2..,,..,.__ __
UNIT NAME: Salem #1 DATE: 02-08-94 COMPLETED BY: Mike Morroni 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 0135 01/01/94 s 744 c 4 ----------- RC FUELXX NUCLEAR NORMAL REFUELING
--
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 CLER) 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)
-
SA.~ETY -RELATED MAINT,ANCE MdNTH: - JANUARY 1994 DOCK' NO:
UNIT NAME:
50-272 SALEM 1 DATE: FEBRUARY 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162
WO NO UNIT EQUIPMENT IDENTIFICATION 931116130 1 VALVE 12MS15 FAILURE DESCRIPTION: PLUG THREADS INSIDE BODY DAMAGED DURING REMOVAL - REPLACE 931214109 1 SOLID STATE PROTECTION SYSTEM TRAIN "A" FAILURE DESCRIPTION: OUTPUT TEST READS LOW -
INVESTIGATE 931214205 1 11 AUXILIARY FEEDWATER PUMP FAILURE DESCRIPTION: MOTOR SLINGER NOT SLINGING -
INVESTIGATE 931229159 1 13 REACTOR COOLANT LOOP FAILURE DESCRIPTION: FLOW CHANNEL 2 READS 18% WITH NO LOOP FLOW - INVESTIGATE 940103180 1 12 AUXILIARY FEEDWATER PUMP FAILURE DESCRIPTION: ERRONEOUS INDICATION -
INVESTIGATE 940110247 1 VALVE 13SJ54 FAILURE DESCRIPTION: VALVE OFF NORMAL INDICATION DID NOT CLEAR - INVESTIGATE 940117073 1 VALVE 12MS10 FAILURE DESCRIPTION: VALVE FAILED TO FULLY CLOSE -
TROUBLESHOOT 940122099 1 VALVE 11BF40 FAILURE DESCRIPTION: VALVE POSITION WILL NOT REACH 10'0% OPEN, IT WILL ONLY REACH 95%
- INVESTIGATE 940122100 1 VALVE 13BF40 FAILURE DESCRIPTION: VALVE DOES NOT REACH THE OPEN LIMIT - REWORK
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10,CFR.50. 59 EVALUATIOI DOCK' NO: 50-272 MdNTH: - JANUARY 1994 UNIT NAME: SALEM 1 DATE: FEBRUARY 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 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 and concurs with these evaluations.
ITEM
SUMMARY
A. Design Change Packages lEC-3208 Pkg 2 11 .salem Fire Damper Upgrade" - The design scope for this package includes the replacement, relocation and/or modification of existing fire dampers of Unit l's Auxiliary Building Ventilation (ABV)
Containment Purge System. The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply. Fire dampers lABF-016 and lABF-024 will be modified in place in accordance with the results of the manufacturer's (PREFCO) fire test report recommendations to obtain a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> fire rating.
The existing fire protective coating will not be necessary, and later replaced to facilitate damper modification. Fire dampers lABF-222 and lABF-228 will be replaced with new Ruskin 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> rated fire damper and moved into the fire barrier, eliminating the need for existing fire protective coatings. The reason for this change is to abide by the PSE&G commitment to the NRC and compliance with the requirements to 10CFR50, Appendix R. The margin of safety is not reduced because we are merely enhancing the Fire Protection System to meet the criteria of 10CFR50, Appendix "R". These modifications will not reduce the margin of safety for the Auxiliary Building Ventilation System or the Fire Protection System. (SORC 94-008)
10~FR50.59 EVALUATIO' MdNTH: - JANUARY 19~4 DOCK' NO:
UNIT NAME:
50-272 SALEM 1 DATE: FEBRUARY 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
B. Procedures and Revisions NC.NA-AP.ZZ-0027(Q) "Inservice Inspection Program" - The revision summary is as follows:
1.) This is a Limited Revision; 2.) The following technical changes was made at Step 5.4: Deleted requirement for SORC review of ISI program submittals to the NRC; 3.) The following minor, editorial changes were made to reflect the recent organization changes: a.) Changed "Nuclear Services" to "Nuclear Support and Services; b.) Changed "Site Services" to "Reliability and Assessment."; c.) Added "Manager Planning and Scheduling (Salem only)", and d.) Step 5.7.2: Changed history file location.
4.) Procedure was reformatted to comply with requirements of NC.NA-AP.ZZ-0032(Q) and NC.NA-AS.ZZ-0001.
5.) Revision bars were not used for typographical errors.
6.) This revision meets the biennial review requirements of NC.NA-AP.ZZ-0032(Q).
The Salem and Hope Creek Technical Specifications were reviewed, including Sections 4.0 and 6.0.
The Technical Specification review did not uncover any inconsistencies with this procedure revision.
Therefore, the proposal can not change the margin of safety as defined in the basis for any Technical Specification. (SORC 94-008)
10.c;,:FRSO ... 59. EVALUATION' DOCK.NO: 50-272 M~NTH: - JANUARY 1994 UNIT NAME: SALEM 1 DATE: FEBRUARY 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
- c. Temporary Modifications T-Mod 94-006 "Installation of Temporary Space Heaters" - This T-Mod will provide additional necessary heating to the Unit 1 Auxiliary Feedwater Storage Tank and Refueling Water Storage Tank level instrumentation lines to prevent these instrument and sample lines from freezing. The T-Mod will install a temporary enclosure heated by space heaters. The temporary enclosure will be constructed of scaffold material enclosed by Herculite. The existing heat trace system is not adequate for the present cold spell at Salem Station. This T-Mod will be monitored hourly by Maintenance when the temporary heaters are in service, and removed when weather conditions permit. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-007)
D. Deficiency Report (Use-As-Is)
SMD 94-009 "Operability of the 11, 12, 13 and 14 GB4 Valves"
- The 11, 12, 13 and 14 GB4 Valve actuator diaphragms may have reduced reliability due to a manufacturing defect with the actuators and a procedure error. The manufacturing error results in the diaphragm being compressed in the area of the bolt circle which may result in the diaphragm tearing. The procedure error addresses the torque value specified in procedure SC.IC-PM.ZZ-0003(Q) and results in the actuator lid bolting being torqued to a value double that recommended by the vendor. This may aggravate the manufacturing defect in tearing the diaphragms along the bolt circle. The GB-4 valves are air operated valves.
The valves provide containment isolation for the Steam Generator Blowdown System. A diaphragm failure of this type will result in a tear along the bolt hole circle where the actuator lids and diaphragm are bolted together. This would result in the valve being unable to maintain an open position and would result in the valve closing.
Since the valve is a spring assist to close valve and valve closure is based on the spring assist
109FR50.* 59 EVALUATIO,, DOCK. NO: 50-272 MONTH: - JANUARY 1994 UNIT NAME: SALEM 1 DATE: FEBRUARY 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
and evacuation of air from under the actuator diaphragm, the safety function of the valve to close is not affected. Loss of blowdown, in itself, is not a concern and is governed by chemistry concerns if blowdown is unavailable for long periods of time. The Technical Specification requirements for the GB-4 valves are to provide containment isolation. The failure of the diaphragm valve will result in the valve failing closed. The ability to satisfy the Technical Specification requirements is not affected during the time that the diaphragm fails since the ability of the valve to close is based on the spring assist and actuator air evacuation from under the diaphragm. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-008)
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 JANUARY 1994 SALEM UNIT NO. 1 The Unit began the period shutdown for the eleventh refueling outage.
The Unit entered Mode 2 "Hot Standby" on January 24, 1994. Low Power Physics Tests were completed on January 25, 1994 and preparations for increasing power to Mode 1, "Power Operation" were performed. A Reactor Trip occurred on January 27, 1994, due to Lo-Lo Level in #14 Steam Generator. The reactor achieved criticality on January 30, 1994, and preparation for increasing power continued throughout the remainder of the period.
RE~UELING INFORMATION~ DOCK.NO:
UNIT NAME:
50-272 MONTH: - JANUARY 1994 SALEM 1 DATE: FEBRUARY 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH JANUARY 1994
- 1. Refueling information has changed from last month:
YES X NO
- 2. Scheduled date for next refueling: MARCH 4, 1995
- 3. Scheduled date for restart following refueling: MAY 2. 1995
- 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?: MARCH 1995
- 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 732
- 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