ML18100A311

Monthly Operating Rept for Mar 1993 for Salem,Unit 2.W/ 930414 Ltr

ML18100A311
Person / Time
Site:	Salem
Issue date:	03/31/1993
From:	Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9304190333
Download: ML18100A311 (13)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 14, 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 March 1993 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 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 I&d..tf The Energy Peop~e

- -93o4i9o333 930331- ----- --\fl o* 0 9 n PDR ADOCK 05000311 a J 95-2189 (~L)~2-89 R PDR I

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8-1-7.R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-311 Unit Name: Salem #2 Date: 4/10/93 Completed by: Mark* Shedlock Telephone: 339-2122 Month March 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET)

\

1 1121 17 0 2 1116 18 0 3 1122 19 0 4 1125 20 0 5 1122 21 0 6 1126 22 0 7 1109 23 0 8 1140 24 0 9 1112 25 0 10 1120 26 0 11 1124 27 0 12 992 28 0 13 1140 29 0 14 1089 30 0 15 1113 31 0 16 490 P. 8.1-7 Rl

'If!.~ .8~.1-7 Rl OPERATING DATA REPORT Docket No: 50-311 Date: 4/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period March 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,,_,__,,A"'--~~~~~~~~~~~~~~-

This Month Year to Date Cumulative

11. Hours in Reporting Period 744 2160 100513

12. No. of Hrs. Rx. was Critical 371.1 1716.71 65482.31

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 371.1 1675.51 63233.97

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1255075.2 5590744.8 150686434.6 Gross Elec. Energy Generated (MWH) 429040 1913950 66621438

18. Net Elec. Energy Gen. (MWH) 407183 1830957 63416933

19. Unit Service Factor 49.9 77.6 62.9

20. Unit Availability Factor 49.9 77.6 62.9

21. Unit Capacity Factor (using MDC Net) 49.5 76.6 57.0

22. Unit Capacity Factor (using DER Net) 49.1 76.0 56.6

23. Unit Forced outage Rate 6.1 7.5 22.5

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling outage scheduled to start 3-20-93 for approximately 74 da s.

25. If shutdown at end of Report Period, Estimated Date of startup:

06/01/93

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MARCH 1993 DOCKET NO. ~5~0~*3~1~1 __ _____

UNIT NAME Salem #2 DATE 04/10/93  ;

COMPLETED BY Mark Shedlock TELEPHONE 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 0015 03/04/93 F 3.50 *A 5 ---------- HF PUMPXX CIRCULATING WATER PUMPS 0016 03/05/93 F 6.48 A 5 ---------- HF PUMPXX CIRCULATING WATER PUMPS 0017 03/08/93 F 7.45 A 5 ---------- HF PUMPXX CIRCULATING WATER PUMPS 0018 03/09/93 F 1.58 B 5 .................... HF PUMPXX OTHER SAFETY PROBLEMS 0011 03/12/93 F 4.32 B 5 ---------- HH VAL VEX OTHER HEATER DRAIN SYSTEM PROBLEMS 0012 03/12/93 F 6.58 B 5 ---------- HF PUMPXX STEAM UNITS THERMAL DISCHARGE LIMITS ENVIRONMENTAL 0020 03/12/93 F 4.47 A 5 ---------- HF PUMPXX CIRCULATING WATER PUMPS 0019 03/12/93 F 5.65 A 5 ---------- HF PUMPXX CIRCULATING WATER PUMPS 0013 03/16/93 F 24.00 A 3 ---------- cc GENERA NUCLEAR STEAM GENERATOR CONTROLS 0014 03/17/93 s 348.90 c 4 ---------- zz zzzzzzzzz 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)

~E~~

MONTH:

RELATED MAINTEN. .E

- MARCH 1993 DOCKET,O:

UNIT NAME:

50-311 SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 900402096 2 VALVE 2SF22 FAILURE DESCRIPTION: STEAM GENERATOR BLOWDOWN SAMPLING LINE INSULATION DAMAGED - REPAIR 900607218 2 22 AUXILIARY FEEDWATER PUMP FAILURE DESCRIPTION: AUX FEED PUMP AREA - REPAIR/

REPLACE INSULATION 910912089 2 VALVE 23MS222 FAILURE DESCRIPTION: 23MS222 UNINSULATED - INSULATE 911014139 2 21 STATION POWER TRANSFORMER FAILURE DESCRIPTION: INFEED BREAKER DOOR BENT - REWORK 911101217 2 VALVE 2SW39 INDICATION FAILURE DESCRIPTION: 21SW39 INDICATION CANNOT BE SEEN

- REMOVE PAINT 911213107 2 VALVE 22CC120 FAILURE DESCRIPTION: SURROUNDING PIPING CORRODED -

REMOVE INSULATION 920328069 2 VALVE 23SW66 FAILURE DESCRIPTION: INSULATION MISSING - REINSULATE 920328085 2 VALVE 24SW71 FAILURE DESCRIPTION: REINSULATE PIPING BEHIND CFCU MOTOR COOLER 920328086 2 VALVE 24SW66 FAILURE DESCRIPTION: REINSULATE PIPING BEHIND CFCU MOTOR COOLER 920328094 2 VALVE 24BF26 FAILURE DESCRIPTION: 24BF26/REINSULATE

• 3AFET.~ REI.ATED MAINTEN. .E DOCKET41l: 50-311 MONTH: - MARCH 1993 UNIT NAME: SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST (cont'd) TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 920410233 2 VALVE 22SW20 FAILURE DESCRIPTION: REPAIR VALVE POSITION INDICATOR 9212210175 2 23 CHARGING PUMP FAILURE DESCRIPTION: INSULATION MISSING - REPLACE 921223188 2 VALVE 21SW127 FAILURE DESCRIPTION: VALVE FLEW OPEN - INVESTIGATE

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930220086 2 24 SERVICE WATER PUMP FAILURE DESCRIPTION: PACKING GLAND INJECTION LINE CLOGGED - REPAIR 930305083 2 RADIATION MONITOR 2R11A FAILURE DESCRIPTION: MONITOR COUNTS INCREASED -

INVESTIGATE 930322081 2 RADIATION MONITOR 2R5 FAILURE DESCRIPTION: SPENT FUEL PIT RADIATION MONITOR SPIKED - INVESTIGATE 930327263 2 2 POLAR CRANE FAILURE DESCRIPTION: MAIN HOIST WILL NOT MOVE -

TROUBLESHOOT

'l.0.CFR50. 5~ EVALUATIONS MONTH: - MARCH 1993 e DOCKET.:

UNIT NAME:

50-311 SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST 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 and concurs with these evaluations.

ITEM

SUMMARY

A. Design Change Packages 2EC-3210 Pkg. 1 "Rigging for #23 AFW Pump and Turbine" - The purpose of this change is to install permanent rigging system (lifting lugs and supplemental steel) for maintenance for the Unit 2 Steam Driven Auxiliary Feed Pump and Turbine, which allows removal and transport of the Pump and Turbine components, at El.

84 1 -0 11 of Auxiliary Building of Unit 2. The enclosure will be modified to provide a removable panel. Rigging and handling of overhead loads are not addressed in the Technical Specifications.

Adding new rigging devices does not change the plant Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-020) 2EC-3196 Pkg. 1 "RG 1.97 EQ Valve Limit Switch and Solenoid Modifications" - This design change package modified the existing power, wiring and electrical protective devices of Environmentally Qualified (EQ) solenoids and valve position limit switches to provide electrical separation from Non-Environmentally Qualified (Non-EQ) solenoids and valve position limit switches. It was determined from a review of the applicable Technical Specifications and their bases that there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-022) 2EC-3189 Pkg. 1 "Permanent Backup Power During Refueling" - This modification provides permanently installed backup power feeds to certain loads so that they can be operated during refueling when their buses are de-energized. Power connections at each end are made through temporary jumpers and control cable connections are made through SB 1 selector switches. This modification will not involve any loads that may affect the reactor criticality or reactor coolant boron concentration. Tying Group Busses 2F & 2H with permanent connections with tie

• 11.'.)CFR.50. 59 EVALUATIONS MONTH: - MARCH 1993 e DOCKET':

UNIT NAME:

50-311 SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

breakers at each end will increase operation flexibility. The loads can be powered without individual alternate power sources. Therefore, this proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. {SORC 93-022) 2SC-2164 Pkgs.1-3 "Synchronization of Diesel Generators 2A, 2B, and 2C" - These changes will provide a permissive to allow the operator to synchronize Diesel Generators 2A, 2B, and 2C with associated vital buses. These permissives will be enabled during a specific closing phase angle ranges, slip limits (F limit),

and voltage ranges. These permissives will be blocked when out of these specific ranges. In addition, the syncrocloser check relays will permit dead bus closures of the diesel generator breakers.

These change packages consist of the modifications of the Design Generator Control Panel No. 2A to add a syncrocloser check relay, auxiliary relay, and green indicating light, remove the existing synch check relay and use the existing spare test switch in order to accomplish the above changes. The implementation of this DCP will not reduce the margin of safety as defined in the basis for any Technical Specification. Failure of the synchronizing permissive circuit will not render the Diesel Generator inoperable or affect the limiting conditions for station operation and equipment surveillance requirements as described in the Technical Specifications. (SORC 93-022) 2EC-3180 Pkg. 1 "Replacing Spare CRDM Clamps with Code Qualified MSCA's" - The purpose of this change is to replace the existing Mechanical Seal Clamp assemblies (MSCA) on all 4 spare CROM Head penetrations with ASME Code qualified new MSCAs. The new MSCA's additionally will have live loading mechanisms on the bolting involved. RCS leakage is covered by Technical Specification 3.4.6.2, and the plant will continue to comply with this Technical Specification. In the event of RCS leakage, the evaluation will be completed and the appropriate action taken. As practiced in the past, PSE&G does not intend to operate with any known head area leakage. Visual inspection during the heatup time and subsequent

• LOCF~50. 59 EVALUATIONS MONTH: - MARCH 1993 e DOCKET':

UNIT NAME:

50-311 SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

operation indications provide detection assurance.

No catastrophic failures or leaks constituting a LOCA are estimated. As such, any margins of safety as determined from the Technical Specifications or their bases are not reduced. (SORC 93-022) 2EC-3081 Pkg. 1 "Penetration Area Welding Receptacles" - This DCP provides three new 460V welding receptacles, one in the Chilled Water Pump Area, El. 100, at column lines BC-16.2, one in the Main steam Penetration Area, El. 100, near column lines FF-16. 8, and one in Personnel Hatch Area, El. 100, near column lines GG-16.8. These receptacles are in a common circuit fed from a new circuit breaker, I2118-21X, in the 2El 460-230 Volt Control Center. The proposed design change will not reduce the margin of safety as defined the basis for any Technical Specification because the new welding receptacles will be on a circuit powered from a non-vital bus control center. The control center has the spare capacity to take the additional circuit and there will be no effect on any other part of the power distribution system, vital or non-vital. There is no increase in the load on the control center or the group bus as far as the Load Management study is concerned because the welding receptacles are intermittent loads. (SORC 93-023) 2EC-3216 Pkg. 1 "Replacement of Boric Acid Instrumentation" - The following description applies to both Units, unless otherwise noted. a) Install new pressure indication filled system at the BAT pumps discharge and at the Unit 2 BA filter inlet and discharge to replace existing installation. b) Install new assemblies as above at the BAT pumps suction. The addition and rework of the instrumentation does not affect the ability of the Boron Injection system to perform its intended function since they are being used for indication only. Therefore, the margin of safety is not compromised. (SORC 93-026) 2EC-3198 Pkg. 1 "Overhead Annunciator Enhancement Project" - The following is a description of the design change: 1.)

Existing window A-9 will be reengraved to read ANNUN

• 1-0CFR~0.59 EVALUATIONS MONTH: - MARCH 1993 e DOCKET.O:

UNIT NAME:

50-311 SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

TRBL (was logic failure). 2.) Add additional alarm capability to the overhead Annunciator (OHA) System; specifically, in addition to being received by the OHA Windows A-1 (Annunciator Power Failure) and A-9 (ANNUN TRBL), significant OHA alarms are being grouped with the output to be received by a single indicator located on a new RZ pushbutton station which is installed on 2cc1 near the OHA CRT, and termed "OHA TROUBLE". Each of these alarm inputs is also being assigned a unique SER point. Relays are being added to provide the output of each of these alarm inputs to the new "OHA TROUBLE" alarm, and also a scanner point for SER point assignments. 3.)

Display the window locations for each SER point on the CRT. 4.) Loss of 28VDC relay added for pushbutton alarm circuit with an input into the aux annunciator typewriter. There is no basis in the Technical Specifications which is affected by this modification. Therefore, this proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-026) 2EC-3190 Pkg. 1 "Pressurizer Safety/Relief Valve Piping System Modifications" - This modification consists of installation of drain lines and associated manual valves and pipe supports to fully drain the pressurizer Power Operated Valve and Safety Valve loop seals. In addition, existing supports for the SV/PORV piping will be modified as required to be in compliance with code allowable stresses. As part of this modification, the SV internals will be upgraded with steam compatible internals. Also, appropriate valve modifications will be performed on the PORVs.

This proposal will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-026)

B. Procedures and Revisions TS2.0P-SO.CH-0002 "Chilled Water System - Cross Tie" - This is a temporary procedure is used to complete DCP 2EC-3083, Chiller Condenser s.w. Pipe Replacement.

This procedure allows the cross-tie of Unit 2 Chillers with Unit 1 chillers when Unit 2 chillers are out of service. This procedure expires

'ulCFR50.59. EVALUATIONStt DOCKET,O: 50-311 MONTH: - MARCH 1993 UNIT NAME: SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

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ITEM

SUMMARY

06/15/93. Sufficient cooling is still available to

1) Ensure Control Room air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and 2) Ensure habitability for both Salem Units 1&2. The loss of Control Air does not preclude safe shutdown of the Units. The Uni ts have been evalua.ted for partial loss of Control Air as well as total loss of Control Air.

The margin of safety as defined in the bases of the Technical Specifications is unaffected by this temporary procedure. (SORC 93-027)

c. Temporary Modifications T-Mod # 93-033 "Modification to Temporary Jumpers" - The sizes of the Temporary Jumpers are IAW the National Electrical Code; Table 310-16, based on the expected Load Requirements. The Overcurrent Protection selected for the Temporary Jumpers will prevent overload, should the actual load exceed the expected load. The Temporary Jumper cables used are out standard 90 degree C, low voltage type cables which can be used in wet or dry conditions and have been qualified for class lE use. System voltage degradation and Electrical system overload concerns have been addressed per the requirements to monitor and/or shed loads as described in this TMOD package. Electrical Separation, combustible loading, Seismic Qualification and seismic 2 over 1 are not applicable in the Turbine Building.

Equipment Grounding has not been altered in this Tmod package. If metallic scaffolding is used to support cables, Grounding requirements for the scaffolding have been specified. Grounding requirements specified meet NEC Article 250. The spare Bkrs. 2F26X, 2H26X, & 2H5Y to be installed for this TMOD will not cause any change in the 2KV Bkr.

2F5D relay settings. This is due to the fact that settings of spare Bkrs. will be set at or below the highest setting on any existing Bkr, and therefore, will not impact the Bkr. coordination. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-028)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 MARCH 1993 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued to operate at essentially full power until March 12, 1993, when a brief load reduction was performed to replace the #21 Heater Drain Pump discharge valve controller. The Unit was restored to 100% power and continued to operate at essentially full power until March 16, 1993, when a Reactor Trip occurred following a loss of #22 Steam Generator Feedwater Pump and subsequent low-low level in #24 steam Generator.

The plant was then cooled down and the Seventh Refueling outage commenced.

DOC~ET,O:

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• • ~EFUELING _INFORMATION 50-311 MONTH: - MARCH 1993 UNIT NAME: SALEM 2 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH MARCH 1993

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: MARCH 20. 1993

3. Scheduled date for restart following refueling: .JUNE l, 1993

4. a) Will Technical Specification changes or other license amendments be required?:

YES NO x NOT DETERMINED TO DATE b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:

YES NO x If no, when is it scheduled?: APRIL 1993

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-l-7.R4