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 S*ervice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 8, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 September 1993 are be~ng sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance lOCFR50.59 Evaluations Operating Summary Refueling Information 8?tJZL 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 Energy People .- . -
9310200209 930930 * -- r---- 95-2189 (10M) 12-89 PDR ADOCK osooo311 I **
R PDR /__,
~ERAGE DAILY UNIT POWER L~L Docket No.: 50-311 Unit Name: Salem #2 Date: 10-08-93 Completed by: Mark Shedlock Telephone: 339-2122 Month September 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1081 17 1052 2 1048 18 949 3 865 19 1127 4 410 20 1100 5 480 21 1114 6 1057 22 1117 7 1115 23 1133 8 1088 24 1128 9 1120 25 1108 10 1113 26 1119 11 1116 27 1113 12 1108 28 1115 13 1114 29 1118 14 1091 30 1125 15 1095 31 16 1068 P. 8.1-7 Rl
OPERATING DATA REPORT~
Docket No: 50-311 Date: 10/08/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status
- 1. Unit Name Salem No. 2 Notes
- 2. Reporting Period Se:gtember 1993
- 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~O~N~E=-~~~~~~~~~~~~~~
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 720 6551 104904
- 12. No. of Hrs. Rx. was Critical 720 3977.1 67742.7
- 13. Reactor Reserve Shutdown Hrs. O 0 0
- 14. Hours Generator On-Line 720 3831.1 65389.6
- 15. Unit Reserve Shutdown Hours O 0 0
- 16. Gross Thermal Energy Generated (MWH) 2349696.0 12604588.8 157700278.6 Gross Elec. Energy Generated (MWH) 785910 4233530 68941018
- 18. Net Elec. Energy Gen. (MWH) 753235 4016932 65602908
- 19. Unit Service Factor 100 58.5 62.3
- 20. Unit Availability Factor 100 58.5 62.3
- 21. Unit Capacity Factor (using MDC Net) 94.6 55.4 56.5
- 22. Unit Capacity Factor (using DER Net) 93.8 55.0 56.1
- 23. Unit Forced Outage Rate O 14.6 22.4
- 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:
NA 8-l-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH SEPTEMBER 1993 DOCKET NO.: _,5:;.;:0'°"'"-=27:.. .:2""=-_ __,
UNIT NAME: Salem #2 DATE: 10/08/93 COMPLETED BY: .Mark Shedlock TELEPHONE: 339-2122 METHOD OF r -
SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0037 9-3-93 F 46.8 A 5 ---------- CH PIPEXX #21 S.G. FEED PUMP LEAK 0038 9-17-93 F 14.3 B 5 ----------- HF HT EX CH WATERBOX CLEANING 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-Refuel ing 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)
SAFET¥ RELATE~ MAI~TEN,CE MONTH: - SEPTEMBER 1993 DOCKE~O:
UNIT NAME:
50-311 SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 WO NO UNIT EQUIPMENT IDENTIFICATION 930818218 2 2R46A MAIN STEAMLINE RADIATION MONITOR FAILURE DESCRIPTION: CHECK SOURCE WEAK - INVESTIGATE 930920109 2 21 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION: 2LI1640 >3.3% DIFFERENCE WITH 2LI518 - TROUBLESHOOT 930920112 2 24 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION: 2LI1643.>3.3% DIFFERENCE WITH 2LI548 - TROUBLESHOOT 930922069 2 24 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: SW FLOW LOW IN LOW SPEED -
INVESTIGATE AND CORRECT 930927150 2 PRESSURIZER LEVEL INDICATION FAILURE DESCRIPTION: 2LT459 CLOSE TO 3% DIFFERENCE WITH OTHER CHANNEL - INVESTIGATE
10CFR50.59 EV~LUAT~ONS~
- ONTH: - SEPTEMBER 1993 DOCKE~O:
UNIT NAME:
50-311 SALEM 2 DATE: OCTOBER 8, 1993 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 2EC-3200 Pkg 1 "Fuel Transfer Tube Blind Flange Replacement/Bolt Reduction" - The proposed modification will replace the existing 20 11 fuel transfer blind flange at Salem Unit 2. The existing flange which uses two (2) flexitallic gaskets and requires twenty bolts to obtain a proper seal, will be replaced with a new blind flange utilizing a new seal design which only requires four bolts to obtain a proper seal. The new blind flange utilizes a Westinghouse design ,
which replaces the flexitallic gaskets with a rubber Quad ring seal design. Design calculations performed by Westinghouse show that a minimum of four (4) bolts can be used with the quad ring seals while still generating sufficient preload to compress the seals and resist hydraulic and seismic forces. The proposed changes to the fuel transfer tube blind flange is being implemented as a maintenance/ radiation dose reduction enhancement (ALARA). The margin of safety of the fuel transfer tube blind flange and bolting is defined, in part, by the requirements imposed by the ASME code. The design requirements have been shown to be met. The containment isolation function is maintained. The margin of safety is therefore, unaffected.
(SORC 93-082) 2EC-3078 Pkg 1 "Rosemount 1153 Upgrade/Replacement with 1154 11 Rev.
7 - The purpose of this revision is to revise the 10CFR50.59 evaluation to reflect the instrument accuracies as calculated by the setpoint/accuracy calculations. Although some of these changes are in the less-conservative direction, the analysis performed on the EOP basis and proposed EOP revisions has been found to be acceptable. This modification replaced 27 Rosemount electronic transmitters with new transmitters having improved performance under harsh environmental conditions.
.. e 10CFR50.59 EVALUATIONS DOCKEAo: 50-311
~ONTH: - SEPTEMBER 1993 UNIT NAME: SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: {609)339-5162 (cont.'d)
ITEM
SUMMARY
The new transmitters are seismically and environmentally qualified for the installed locations. There is no change to instrument process variable spans. The new transmitters are equal to or better than the previous instruments under all conditions. Verification of the P-11 allowable value, consistent with the setpoint calculation, will continue to assure that manual block of safety injection is defeated well above the SI actuation allowable value of ~ 1775 psi. There is no impact on the margin of safety as defined in the basis for any Technical Specification. {SORC 93-085) 2EC-3211 Pkg 1 "SGFP/Condensate Pump/Feedwater Heaters: System Design Press Modifications" Rev. 3 - The purpose of this revision is to revise the 10CFR50.59 evaluation to address a change to UFSAR Table 10.4-1. This change will provide setpoint corrections for the 21, 22 and 23 condensate pump recirculation flow control loops to ensure a maximum sustained nominal pressure of 625 psig during cold startup. This change will also provide setpoint corrections for the f eedwater heaters 26A, 26B and 26C thermal relief valves 21, 22 and 23HV22. This change will develop a two-out-of-two high pressure trip signal by installing redundant transmitters on the discharge piping of each f eedwater pump to provide the required protection while minimizing the potential for a spurious trip. The existing feed pump trip circuitry will be modified to allow the feed pump to trip on a high feed pump discharge pressure at all power levels. The existing L&N power supply, bistable and transmitter from each of the #21 and
- 22 SGFP analog discharge pressure transmitter-circuits, as well as the existing Keylock override switches will be deleted to implement the new single channel instrument loop trip circuitry noted above. The only Technical Specification which involves SGFP circuitry is Technical Specification 3/4.3.2.b {Table 3.3-3, 5.a
& 8.f), feedwater isolation and a trip of main feedwater pumps starting the motor driven Auxiliary
- . e 10CFR50.59 EVALUATIONS DOCKE.O: 50-311 MONTH: - SEPTEMBER 1993 UNIT NAME: SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'1 d)
ITEM
SUMMARY
Feedwater pump. This modification does not alter this function in any way. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-085)
B. Temporary Modifications TMOD 93-031 "Temporary Operation and Control of CW Systems" -
The purpose of this modification is to provide temporary connections for continued operation of Unit 2 CW equipment (circulating water pumps, circulator bearing lube pumps, screen wash pumps, and traveling screens) during performance of DCP lSC-2297 when old Panel 371 will be replaced by new Panel 371. This design change does not reduce the margin of safety as defined in the basis for any Technical Specification. There are no requirements directly specified for the operation or performance of any circulating water system equipment in the Technical Specifications. The TMOD allows the.
operator to manually start the circulating water pumps when adequate circulator bearing lube header pressure is available and to maintain circulator bearing lube pressure and travelling screen wash header pressure manually from Panel 360-2 during the installation of Panel 371 by DCP lSC-2297.
(SORC 93-083)
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 2 SEPTEMBER 1993 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued to operate at full power until September 3, 1993, when power was reduced to 90% to repair a leaking turbine auxiliaries cooling system heat exchanger drain valve. On September 4, 1993, power was further reduced to 48% to repair a leaking drain valve on #21 steam generator feedwater pump. The Unit was returned to full power on September 6, 1993, and continued to operate at full power until September 28, 1993, when power was reduced to 80% to replace 22B circulating water pump and clean condenser water boxes. The Unit was returned to full power later, the same day, and continued to operate at full power throughout the remainder of the period.
REFUELING INFORMATION e
DOCKET NO: 50-311 MONTH: - SEPTEMBER 1993 UNIT NAME: SALEM 2
.- DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH SEPTEMBER 1993
- 1. Refueling information has changed from last month:
YES NO X
- 2. Scheduled date for next refueling: SEPTEMBER 17, 1994
- 3. Scheduled date for restart following refueling: NOVEMBER 6, 1994
- 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?:
- 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 464
- 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: March 2003 8-1-7.R4