ML18102B452

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Monthly Operating Rept for June 1997 for Salem Unit 1. W/970715 Ltr
ML18102B452
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/30/1997
From: Garchow D, Ritzman R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970442, NUDOCS 9707220151
Download: ML18102B452 (11)
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  • Publi,c Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236

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Nuclear Business Unit JUL 15 1997 LR-N970442.

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly oper'ating report for June, 1997, is attached.

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I rLcUJP David F.

General Manager -

Salem Operations RAR:tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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95-2168 REV. 6/94

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  • DOCKET NO.: 50-272 Salem 1 UNIT:

DATE: 06/13/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH JUNE 1997 The following items completed during June 1997 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations S97-009, Control Room Normal Air Conditioning System Plenum Drain Modification. This design change adds two 1 inch drain openings in the Control Room Normal Air Conditioning Plenum to reduce standing water in the plenum.

The Control Area Air Conditioning System (CAACS) is designed to maintain room temperatures within the specified limits required for operation, maintenance, and testing of plant controls. The emergency (filtration) portion of the CAACS provides uninterrupted safe occupancy during post-accident conditions. This design change represents an operational improvement to the CAACS.

This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

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  • lEC-3385, Pkg. 1, Replacement of 12SVDC Battery Chargers.

This design change modifies the 125VDC system by replacing six battery chargers. The battery chargers were exhibiting an increasing number of age-related failures and are no longer being manufactured. Battery chargers from another manufacturer were installed. Expected benefits include less frequent maintenance, spare part availability, and increased reliability.

These battery chargers are not accident initiators or contributors to any accident analyzed in the UFSAR and are not required to be directly involved in the mitigation of an accident analyzed in the UFSAR. This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3401, Pkg. 1, uB" Emergency Diesel Generator Starting Air and Turbo Boost System Upgrade. This design change enhances the "B" Emergency Diesel Generator Starting Air and Turbo Boost System. It replaces existing components with components made of stainless steel or other corrosion resistant material, removes the starting air dryer, and raises the relief valve setpoint to minimize unnecessary compressor cycling.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3429, Pkg. 4, uB" Emergency Diesel Generator Jacket Water Piping Modifications. This design change adds flexhose downstream of isolation valves to isolate the tubing between the pressure switch and the isolation valve from diesel vibrations. To accommodate the flexhose installation, tubing downstream of the f lexhose was rerouted and supported. This design change provides a higher safety factor against fatigue failure.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

  • lEC-3438, Pkg. 2, "B" Emergency Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modifications. This design change installs two voltage sensing relays and an auxiliary relay to monitor the output voltage of the "B" Emergency Diesel Generator (EDG) .

Contacts from the auxiliary relay replace the voltage permissive contact in the closing circuit of the main circuit breaker for the EDG. The setpoints of the voltage sensing relays are at a higher voltage than the previous relays and will prohibit the EDG main circuit breaker from closing when the EDG output is less than the required voltage. This design change also installs indicating lights on the generator control panel to identify when the voltage and speed permissives are satisfied.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3453, Pkg. 2, "B" Emergency Diesel Generator Fuel Oil Day Tank Setpoint Change. This design change adjusted the level switch setpoints associated with the fuel oil day tank. This design change allows the Emergency Diesel Generator to run longer after the receipt of the low level alarm and before it runs out of fuel. This change also mitigates the consequences of a loss of the fuel oil transfer pump.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3455, Pkg. 2, "B" Emergency Diesel Generator Prelube Oil Pipe Modifications. This design change modifies piping to accommodate diesel engine to diesel skid differential motion imposed on the piping system. Flexible mechanical joints and f lexhose were installed on the suction and discharge sides of the prelube oil pump and the prelube drain valve was removed.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lube oil, and jacket water auxiliary systems to increase vibration tolerance. The changes include replacing piping and tubing with flexhose; adding bracing, supports, and brackets; and relocating valves.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3533, Pkg. 2, "B" Emergency Diesel Generator Starting and Turbo-Boost Air Compressor Start/Stop Pressure Switches.

This design change replaces pressure control switches for the Emergency Diesel Generator starting and turbo-boost air compressors. This design change also revises the auto stop setpoint for the air compressors to increase the margin prior to safety relief valve operation.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3701, Pkg. 1, Switchgear and Penetration Area Ventilation System Reliability Enhancement Modification.

This design change enhances the Switchgear and Penetration Area Ventilation System reliability and ability to maintain temperatures within its design limits. This is accomplished by modifying the supply fans start logic, the switchgear exhaust/return fans control circuits, the modulating damper controls, the penetration area exhaust fan control circuits, and the isolation damper controls.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during June, 1997.

Procedures

  • Summary of Safety Evaluations
  • There were no changes in this category implemented during June, 1997.

UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during June, 1997.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during June, 1997.

Other Summary of Safety Evaluation There were no changes in this category implemented during June, 1997.

  • OPERATING DATA REPORT
  • Docket No: 50-272 Date: 07/10/97 Comp.leted by: Robert PhillipseJ' Telephone: 339-2735 Operating Status
1. Unit Name Salem No. 1 Notes
2. Reporting Period June 1997
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 720 4343 181799
12. No. of Hrs. Rx. was Critical 0 0 104380.45
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 100338.27
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 31806229.2
17. Gross Elec. Energy Generated (MWH) 0 0 105301000
18. Net Elec. Energy Gen. (MWH) -2088 -15945 100158791
19. Unit Service Factor 0 0 55.2
20. Unit Availability Factor 0 0 55.2
21. Unit Capacity Factor (using MDC Net) 0 0 49.8
22. Unit Capacity Factor (using DER Net) 0 0 49.4
23. Unit Forced Outage Rate 100 100 33.3
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Steam Generator replacement.

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

Under review.

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AVE~ DAILY UNIT POWER LEVEL

  • Docket No.: 50-272 Unit Name: Salem #1 Date: 07/10/97 Compieted by: Robert Phillips QJ' Telephone: 339-2735 Month June 1997 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 16 0 P. 8.1-7 Rl

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH June 1997 DOCKET NO. : _,5"""0'"'"-2""7""2~--

UN IT NAME: Salem #1 DATE: 07/10/97 COMPLETED BY: Robert Phillips ,

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 6-1-97 F 744 F,C 4 ----------- zz zzzz Steam Generator Replacement 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)

Refueling Information Month: June, 1997

  • Docket No.

Unit Name:

50-272 Salem 1 Contact: D.Tisdel Telephone: 609-339-1538 Month: June, 1997

1. Refueling information has changed from last month: Yes: No: X
2. Scheduled date for next refueling: To Be Determined Scheduled date for restart following refueling: To Be Determined
3. a. Will Technical Specification changes or other license amendments be required?

Yes: X No: 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? To be Determined

4. Scheduled date (s) for submitting proposed licensing action: To be Determined

\ 5. Important licensing considerations associated with refueling:

6. Number of Fuel Assemblies:
a. Incore: 0
b. In Spent Fuel Storage: 953
7. Present Licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: April 2012

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  • SALEM GENERATING STATION
  • MONTHLY OPERATING

SUMMARY

- UNIT 1 JUNE 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and 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 the 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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