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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i public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 12, 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 July 1994 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, 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
/(fl~
1 ThREnerav Peoole~- I 9408190226 940731 PDR ADOCK 05000272 ~-2189 (10M) 12-89 R PDR
e OPERATING DATA REPORT e Docket No: 50-272 Date: 08/10/94 Completed by: Mike Morroni Telephone: 339-2122 Operating Status
- 1. Unit Name Salem No. 1 Notes
- 2. Reporting Period July 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) N/A
- 10. Reasons for Restrictions, if any ~~~~___,N..,,,.__,A=-~~~~~~~~~~~~~
This Month Year to Date Cumulative
- 12. Hours in Reporting Period 744 5087 149784
- 12. No. of Hrs. Rx. was Critical 678.35 2914.58 98046.6
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line 648.58 2375.13 94262.97
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 2120853.6 7949685.6 298721999.6
- 17. Gross Elec. Energy Generated (MWH) 697480 2276330 98812300
- 18. Net Elec. Energy Gen. (MWH) 664768 2108071 94045624
- 19. Unit Service Factor 87.2 46.7 62.9
- 20. Unit Availability Factor 87.2 46.7 62.9
- 21. Unit Capacity Factor (using MDC Net) 80.8 37.5 56.8
- 22. Unit Capacity Factor (using DER Net) 80.1 37.2 56.3
- 23. Unit Forced outage Rate 12.8 44.1 21.8
- 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:
N A.
8-1-7.R2
.ERAGE DAILY UNIT POWER LE~
Docket No.: 50-272 Unit Name: Salem #1 Date: 08/10/94 Completed by: Mike Morroni Telephone: 339-2122 Month July. 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1050 17 0 2 1020 18 0 3 1055 19 587 4 1060 20 1028 5 1060 21 1048 6 1036 22 1073 7 1040 23 . 1036 8 1042 24 1060 9 1057 25 1056 10 1038 26 1044 11 1063 27 1075 12 1042 28 1057 13 1018 29 1060 14 982 30 1068 15 0 31 1060 16 0 P. 8.1-7 Rl
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1994 DOCKET NO. :_.5"""0..,..-2=7~2'="'"_ __
UNIT NAME: Salem #1 DATE: 08-10-94 COMPLETED BY: Mike Morroni TELEPHONE: 339-2"122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # COOE 4 COOE 5 TO PREVENT RECURRENCE 1440 07-14-94 F 95.42 A 2 ---------- HF CKTBRK LIGHTNING 1465 07-19-94 F 1.9 A 5 ---------- HB VAL VEX CONTROL VALVES TURBINE 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 CNUREG-0161)
E-Operator Training & License Examination Previous Outage F-Aaninistrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)
10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272 MONTH: - JULY 1994 UNIT NAME: SALEM 1 DATE: AUGUST 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-3252 Pkg 1 "Reracking Of spent Fuel Pool For Increased Storage Capacity" - This DCP will remove nine existing Exxon racks and replace then with nine maximum density Holtec racks. Relocate three Exxon racks in the spent fuel pool. In the reracked pool racks are located closer to the wall. The hook of the FH crane will not reach the first row of cells near the North wall and the first two rows of cells near the North wall and first two rows of cells near the East wall. For this purpose a new off set tool will be procured and used. This DCP will also modify the skimmers and strainer and make them removable for future access to the cells directly under these items.
New Holtec racks may require use of a funnel for inserting spent fuels. The spent fuel storage capacity will run out in 1998 if this change is not made. After this modification, the storage capacity in the spent fuel pool will be available until 2008 * . There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-056) lEC-3340 Pkg 1 "Waste Gas System Setpoint Modification" - 1. The following setpoints will be verified and adjusted as necessary during DCP installation in order to assure optimum system operation: 1WG8 control, Auto Waste Gas Decay Tank (WGDT) swap-over, Compressor Auto Start and Compressor Auto Stop.
- 2. A Special Test Procedure (STP) will be created as part of this DCP which will include, but will not be limited to, provisions for optimum test conditions, test procedures, calibrations and adjustments. Also, steps for adjustments of proportional band and reset for the 11WG22 and 12WG22 controllers will be provided in the STP in addition to the 1WG8 controller. The goal of this DCP is to maintain a suction header pressure of 0.5 to 2.0 psig as described in UFSAR (Section
- 11. 3)
10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272 MONTH: - JULY 1994 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
while operating in the automatic mode. Vendor recommended setpoint changes for the Waste Gas Compressors will be made so that the Waste Gas Compressors can be operated in the automatic mode, as described in the SAR. In addition, the vendor recommended setpoint changes will be used to improve the reliability of the Waste gas Compressors. The changes performed by this modification to the WGS do not affect any credible failure modes. All plant modifications for this DCP are confined to the recalibration of selected Waste Gas instrumentation. There no is no increased potential for WGDT rupture since the output of the compressors is reduced in regard to
_the design limits of the tanks. The modification involves non-safety related instrumentation and does not involve any Category 1E systems. No active or passive failure modes are associated with this change, and the electrical performance in regard to failure (e.g., hot shorts, grounded shorts, etc.) is not affected by this modification. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-060)
B. Procedures and Revisions LOCA 3 & LOCA 4 "EOP & FSAR Changes for Recirculation Mode" -
There have been several performance issues identified over the years related to the operation of the Residual Heat Removal System (RHRS) during the Recirculation Mode following a Loss Of Coolant Accident (LOCA). These issues include: 1.)
Unintended flow paths and their consequences; 2.)
Excessive RHRS pump flows during Hot Leg Recirculation; 3.) Excessive suction boost to the Charging/Safety Injection pumps and Intermediate Head Safety Injection pumps. PSE&G and Westinghouse have worked together to develop changes for Salem Units 1 and 2 to address these issues. The scope of this safety evaluation includes an assessment of the following changes:
1.) Modification of the RHR pump design basis for
. e 10CFR50.59 EVALUATIONS e
DOCKET NO: 50-272 MONTH: - JULY 1994 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
net positive suction head (NPSH) to take credit for Containment air pressure; and 2.) Selected Emergency Operating Procedure (EOP) step changes.
The first is necessary to justify an increase in RHR pump "worst-case" maximum flow potential and address Containment Sump level setpoint accuracy.
The changes identified in Item 2 are being made to preclude undesirable RHR pump flow alignments and to enhance RHRS long term availability. No Technical Specification flow limits are affected by these changes. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-057)
NC.NA-AP.ZZ-0034(Z) "Performance Indicator Program" - This proposal deletes Nuclear Administrative Procedure NC.NA-AP.ZZ-0034(Z), Performance Indicator Program. The Performance Indicator Program has been incorporated into the Business Plan. The Operational Quality Assurance Program does not apply to this procedure. Although this procedure is briefly described in the UFSAR (Section 13.5.1 (Hope Creek), Plant Procedures, and Section 13.5.1.1 (Salem), Nuclear Administrative Procedures), it performs no function relative to the safe operation of either Hope Creek or Salem Stations. Therefore, deleting this procedure will have no affect on the safe operation of either Hope Creek or Salem Stations. UFSAR Change*
Requests for Hope Creek and Salem UFSARs are being concurrently submitted with this proposal to remove the description of this procedure from the UFSAR. This procedure does not affect the operation of any equipment, either safety related or non-safety related. Therefore, deleting this procedure will have no effect on any equipment important to safety. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-060)
.10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272 MON~H: - JULY 1994 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
- c. SAR Changes UFSAR Section 17.2 "Quality Assurance During the Operations Phase" -
The proposed changes: 1.) Reflect current organizational structure; 2.) Make editorial enhancements, and 3.) Provide clarifications.
Additionally, the changes effect selected Quality Assurance (QA) oversight practices for monitoring implementation of the Nuclear Department Procedure System. Changes in QA practices will now utilize the assessment process to evaluate the effectiveness of Nuclear Department groups implementation of the Nuclear Department Procedure System. The assessment approach expands the scope of QA to evaluate process requirements for preparing, reviewing, revising and issuing departmental administrative and implementing procedures. There are no credible failure modes associated with this change. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 94-058}
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 JULY 1994 SALEM UNIT NO. 1 The Unit began the period operating at full power and continued to operate at essentially 100% power until July 14, 1994, when operators manually tripped the reactor due to loss of all circulators. An electrical storm in the area caused a bus voltage perturbation which activated the protective relays on the bus feeding the Circulating Water Pumps. A time delay has been installed to prevent a future similar occurrence. The Unit was returned to 100% power on July 20, 1994, and continued to operate at essentially 100% power throughout the remainder of the period.
. REFUELING INFORMATION e e DOCKET NO: 50-272 MONTH: - JULY 1994 UNIT NAME:
DATE:
SALEM 1 AUGUST 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH JULY 1994
- 1. Refueling inf ormat.ion has changed from last month:
YES NO X
- 2. Scheduled date for next refueling: APRIL 8, 1995
- 3. Scheduled date for restart following refueling: JUNE 6, 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-l-7.R4