ML18102A389

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Monthly Operating Rept for Aug 1996 for Salem Unit 2. W/960911 Ltr
ML18102A389
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/31/1996
From: Garchow D, Heller R, Phillips R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9609180392
Download: ML18102A389 (15)
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit September 11, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 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 report for the month of August is being sent to you.

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General Manager -

Salem Operations RH:vls Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region I

  • 475 Allendale Road King of Prussia, PA 19046 9609180392 960831 PDR ADOCK 05000311 R PDR The power is in your hands.

95*2168 REV. 6/94

~ERAGE DAILY UNIT POWER LE-41a Docket No.: 50-311 Unit Name: Salem #2 Date: 09/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month August 1996 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

OPERATING DATA REPORT ~

Docket No: 50-311 Date: 09/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period August 1996
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) 1115
6. Maximum Dependable Capacity(Gross MWe) 1149
7. Maximum Dependable Capacity (Net MWe) 1106
8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA
9. Power Level to Which Restricted, if any (Net MWe) N/A
10. Reasons for Restrictions, if any NA This Month Year to Date Cumulative
11. Hours in Reporting Period 744 5855 30239.24
12. No. of Hrs. Rx. was Critical 0 0 78083.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 75229.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 0
17. Gross Elec. Energy Generated (MWH) 0 0 78648898
18. Net Elec. Energy Gen. (MWH) -3442 -24512 74716542
19. Unit Service Factor 0 0 57.7
20. Unit Availability Factor 0 0 57.7
21. Unit Capacity Factor (using MDC Net) 0 0 51. 7
22. Unit Capacity Factor (using DER Net) 0 0 51. 3
23. Unit Forced outage Rate 100 100 28.7
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling extension.

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

Under review.

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UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH August 1996 DOCKET NO. 50-311 UNIT NAME Salem #2 DATE 09-10-96 COMPLETED BY Robert Phi l lips : .

TELEPHONE 609-339-2735 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 5 TO PREVENT RECURRENCE 3859 08-01-96 F 744 FC 4 --------- ... zz zzzz Refueling Schedule Exceeded 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)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: 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.

1. Design Change Packages (DCP) 2EC-3264, Pkg. 1 "Hagan R&R Project - Replacement of 21 and 22 Boric Acid Transfer Pump Control Circuit Fuses" Rev. 0 - This Design Change Package (DCP) changed the No. 21 and No.

22 Boric Acid Transfer Pump 115VAC control power fuses from fifteen (15) amps to five (5) amps. This provides proper circuit protection for the control transformers. The replacement fuses do not change the function or operation of the Boric Acid Transfer Pumps. In addition, a loss of a Boric Acid Transfer Pump due to a fuse failure can not result in the loss of a safety function or cause an accident.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-046) 2EC-3266, Pkg. 1 "Diesel Generator Lube Oil Temperature Low Alarm Setpoint" Rev. 0 - This change accomplished three tasks.

First, 2A Diesel Generator lube oil pump heater failure alarm temperature switch and lube oil heater control switch (0-400°F) were replaced with similar, 0-250°F range switches. Temperature sensor locations on 2C Diesel Generator were rearranged to facilitate consistent physical arrangement of both the heaters and heater failure alarm.

Following the switch replacement and sensor rearrangement, the low temperature alarm setpoints were raised from 80°F to 100°F for all three Diesel Generators.

Neither the high temperature setpoints nor the heater on and off setpoints were affected. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-034)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-339-5162 2EC-3338, Pkg. 7 "Group Bus Undervoltage Protection - Condensate Pumps" Rev. 0 - This change package modified the control circuit of the Unit 2 Condensate Pump No. 21 by adding an undervoltage trip signal for the condensate pump. This change is not considered "important to safety" and no Technical Specification margins apply to the Condensate Pump or Condensate System except for section 6.0 which only relates to the chemistry of the Condensate System.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-047) 2EC-3353, Pkg. 1 "Replacement of Low Pressure Turbine Rotors with Fully Integral Design" Rev. 1 - This modification involved removing and replacing the existing Low Pressure Turbine Rotors with new mono-block design rotors. The new rotors are a fully integral design and eliminates shrunk-on discs and key plates. All equipment is specified to meet or exceed material and design requirements. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-067) 2EC-3357, Pkg. 1 "21 Service Water Pump Replacement" Rev. 0 -This change replaced the existing No. 21 Service Water Pump with a new Johnston pump with a slightly different design.

This modification provides more reliable service water operation and has no impact on the Technical Specifications. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-035) 2EC-3358, Pkg. 1 "No. 23 Service Water Pump Replacement" Rev. 2 - This package replaced Nos. 23 Service Water Pump with a pump manufactured of materials that are more resistant to the corrosive and erosive silt laden brackish river water than the existing pump materials. This evaluation has been revised

IOCFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-339-5162 to incorporate information regarding cooling flow to the motor oil cooler, the vortex suppresser, the increased weight of the pump and the seismic qualifications of the pump/motor assembly. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-094) 2EC-3359, Pkg. 1 "No. 22 Service Water Pump Replacement" Rev. 1 - This DCP replaced the existing No. 22 Service Water Pump with a new Johnston Pump Co. pump with a slightly different design. The replacement service water pump material is compatible with brackish river water, able to withstand the high silt flows, and designed for an NPSHa at 76 feet river water level. The replacement of the service water pumps with Johnston Pump Co. pumps provides more reliable operation. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-085) 2EC-3376 Pkg. 1 "Main Turbine Lube Oil Drain Piping Rework" Rev. 0 -

This change modified the Main Turbine Lube Oil Evactor and Demister/Exhaust Hood oil drainage system by adding loop seals and a drain pot. This change also rerouted the Service Building Stairwell roof rain water drainage from discharging into the Delaware River to discharging into the skimmer tank. The Main Turbine Lube Oil evactor and drain piping is not referenced in the Salem Unit 2 Technical Specifications or their bases. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-041) 2EC-3385, Pkg. 1 "Residual Heat Removal Flow Setpoint" Rev. 0 - This DCP replaced Rosemount "P" board amplifier and calibration cards in 2FT-641 NB with Rosemount "R" boards, calibrated the flow transmitters to a new range of 0-1300 gpm; and changed the setpoint of2FC641 A-C/B-D to close valves 21/22 RH29 from 1000 gpm to 1150 gpm. Although the Rosemount "P" boards are fully qualified for application

  • 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-339-5162 in the Residual Heat Removal Rooms, Rosemount "R" boards have demonstrated enhanced performance/accuracy under radiation exposure conditions as compared to the "P" boards. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-039) 2EC-3387, Pkg. 1 "2A Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modification" Rev. 0 -

This DCP installed two new voltage sensing relays and an auxiliary relay to monitor the output voltage of Emergency Diesel Generator 2A. Contacts from the auxiliary relay replaced the existing voltage permissive contact in the closing circuit of the main circuit breaker for the emergency diesel generator. The setpoints of the new voltage sensing relays are at a higher voltage than the existing relays and will prohibit the emergency diesel generator main circuit breaker from closing when the generator output is less than the required voltage. This DCP also installed indicating lights on the Generator Control Panel which will identify when the voltage and speed permissive are satisfied. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-051) 2EC-3396, Pkg. 1 "Installation of Transfer Switches for Appendix R Alternate Shutdown" Rev. 0 - Motor control center and control panel circuits for 36 components (3 chillers, 17 valves, 4 vent fans, 8 room coolers and 4 pumps) were modified to include local switches which isolate component wiring from the Control Room, Relay Room and ceiling area of the 460-230 Switchgear Room, thus precluding the necessity of electrical wiring modifications and jumpers to operate the subject equipment in achieving Hot Standby in the event of a fire in these areas. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-046)

  • 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-339-5162 (Cont'd) 2EC-3403, Pkg. 1 "Emergency Diesel Generator 2A Fuel Oil Day Tank Level Switch Setpoint" Rev. 0 - This DCP raised the 2A Emergency Diesel Generator Fuel Oil Day Tank low level alarm and back-up pump start setpoint from 18" to 27". It also, lowered the setpoints on the regular/back-up stop switch from 46" to 43" and the regular/back-up high level alarm/stop switch from 47" to 45". All tolerances are+/- 1/2 inch for consistency and readability. This also includes manufacturers tolerances. This change is in the conservative direction for the back-up pump start and low level alarm setpoint so the margin of safety is increased by this modification. The margin of safety for the primary stop setpoint for the transfer pumps and the secondary stop setpoint for the transfer pumps/high tank level alarm is unaffected. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-050) 2EC-3450, Pkg. 1 "Replacement of Hagan Isolators and Summators with NUS Modules" Rev. 0 - This DCP replaced Westinghouse -

Hagan Model 110 Isolator 2PM55A with NUS Model OCA801 Signal Isolator and Westinghouse - Hagan Model 111 Summators 2PM455C, 2PM455E, and 2PM455G with NUS Model MTH801 Signal Summators in Loop 2PT-455, Channel I Pressurizer Protection and Control. This DCP made no changes to the functional, operational or design requirements of any affected instrument loops in the Reactor Control and Protection System, including instrument ranges, setpoints and protection channel response times. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 96-045) 2EC-3453, Pkg. 1 "Mid-Loop Wide Range Level Upgrade" Rev. 0 - This DCP installed a new differential pressure transmitter, toggle switch and indicator for wide range mid-loop level operations. The new transmitter was mounted seismic category 1 near the existing narrow range transmitter

  • 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-339-5162 2LT16274. A toggle switch was mounted seismic II/I near both wide and narrow range transmitters. The toggle switch allows switching between narrow or wide range transmitters as required. The new wide range transmitter utilizes all existing cabling and electronics from narrow range channel 2LT16274. A new wide range indicator was installed directly in the existing narrow range indicator mounting bracket and rewired to existing indicator cabling.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-089) 2EC-3456, Pkg. 1 "Emergency Diesel Generator 2A Air Compressor Setpoint Change" Rev. 0 - This design change replaced pressure control switches 2PD6476, 2PD6477 and 2PD7210 for Emergency Diesel Generator 2A starting air turbo-boost air compressors 2DAE7, 2DAE8 and 2DAE13 respectively.

The new switches are ASCO Model SAI ID/TH10A21 which have an adjustable operating range of 13-300 psig.

To eliminate abnormal setpoint drift between calibrations resulting from tubing-induced vibration, flexible hose was added between the metal tubing and instrument port. Since this DCP does not adversely affect the reliability of the starting and turbo-boost air system, there is additional assurance that the Emergency Diesel Generator will start and operate efficiently to mitigate accident consequences.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-050) 2EC-3467, Pkg. 3 "Safety Injection System Motor Operated Valves 2SJ12 and 13 Disc Weep Hole Modifications (Generic Letter 95-07 Pressure Locking)" Rev. 0 - This DCP drilled a 1/8" weep hole in the valve disc (charging pump/Boron Injection Tank side of the Boron Injection Outlet to Cold Leg Valves 2SJ12 and 2SJ13. This provides an internal relief path to preclude potential pressure locking due to a pressure build up in the valves' bonnet cavity and in the space between the valve disc. This is consistent with preventive methods

.10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-3 3 9-5162 promulgated in NUREG-1275, Vol. 9. This modification does not reduce the safety margin of the Safety Injection System and enhances the reliability of the system by providing an internal relief path for any fluid trapped in the valve bonnet, thus ensuring valve operability. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-051) 2EC-3470, Pkg. 1 "Steam Generator Blowdown Sampling Isolation Bypass" Rev. 0 - This DCP implemented the following specific changes to the facility: 1) Installed a keylock switch (position 2) and bypass mode indicator; 2) Placed a label, with attached Bypass key, near the keylock switch indicating the switch's function, and 3) Added a 28 VDC relay to change circuit configuration to provide bypass mode indication and energize the bypass circuitry.

Setpoints and action levels for Emergency Operating Procedure actions remain unchanged. Coincidence logic and redundancy are not changed. The closure times for containment isolation valves are not affected. Sampling during normal operations are not affected by this DCP.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-070) 2EC-3478 Pkg. 1 "Relief Valve Replacement and Relocation" Rev. 0 - This DCP replaced the existing safety relief valve 2CV141, Crosby Model JMAK-SPL, with a Crosby model JRAK-BS bellows style safety relief valve. The modification also relocated 2CV141 and check valve 2CV63 further away from the slow oscillations caused by the pulsation dampener and elbow. The new configuration places the check valve downstream of 2CV141 to eliminate the starvation potential (and subsequent flow oscillation) caused by the check valve being located upstream of the relief valve. The modification does not reduce the margin of safety of the emergency core cooling system, boration systems, or any other plant

  • 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R. HELLER TELEPHONE: 609-339-5162 (Cont'd) systems. This modification does not reduce the margin of safety as defined in the bases for any Technical Specification. (SORC 96-050) 2EC-3541, Pkg. 1 "Letdown Isolation Bypass" Rev. 0 - This DCP installed a keylock switch, two auxiliary relays and one interposing relay. When the keylock switch is placed in the "bypass" position, the two auxiliary relays and interposing relay will be energized. A contact from the interposing relay will energize the control console bezel letdown isolation bypass indicator light. The remaining contacts on the energized auxiliary relays provide the correct contact configuration in order to allow the operator to bypass the low pressurizer level (less than 17% pressurizer level) isolation signal and allow positioning control for the Chemical and Volume Control system letdown valves. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-081) 2EE-0134, Pkg. 01 "Coating For Containment Fan Coil Unit Cooling Coil &

Motor Cooler Water Boxes" Rev. 0 - This DCP implemented the refurbishment of the corrosion deteriorated containment fan coil unit cooling coil and motor cooler water boxes by the repair of water box components and the application of a protective coating to resist further corrosion. The coating material functions to provide a protective coating for the water box surfaces which does not impact either the hydraulic or thermal performance of the Containment Fan Coil Units. Extensive design bases testing by ASTM indicates the material does not degrade.

No flaking or peeling has been reported. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-004) 2EE-0188, Pkg. 1 "Modifications to Auxiliary Annunciator Alarms 505 &

716" Rev. 0 - The pre-op. condensate bypass strainer has been removed. Auxiliary Annunciator point #716, "Pre Opera. Cond. Bypass Strainer Diff Press/Hi", was alarming

I 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-339-5162 repeatedly with the Condensate Bypass System aligned. In addition, the associated differential pressure switch 2PD 10169 was tripping due to panel vibrations. Since the pre-op. condensate bypass strainer is no longer in place, Auxiliary annunciator point #716 and pressure switch 2PD 10169 serve no useful purpose and were removed as part of this package. The removal of this alarm does not affect Operations. The plant auxiliary annunciator and the condensate system are not described in the Technical Specifications. There is no reduction in the margin of safety as defined in the bases for any TS. (SORC 96-094)

REFUELING INFORMATION DOCKET NO: 50-311 MONTH: AUGUST 1996 UNIT NAME: SALEM2 CONTACT: R.HELLER TELEPHONE: 609-3 3 9-5162 MONTH: AUGUST 1996

1. Refueling information has changed from last month: YES ~*-~* NO . X .
2. Scheduled date for next refueling: (currently in refueling)

Scheduled date for restart following refueling: (to be determined)

3. 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? (to be determined)

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 0
b. In Spent Fuel Storage 777
8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 AUGUST 1996 SALEM UNIT NO. 2 The Unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the Unit will remain shutdown pending completion of the following actions:

  • Appropriately address long standing equipment reliability and operability issues
  • After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner
  • After the restart review, meet with the NRC and communicate the results of that review
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