ML18101A479

Monthly Operating Rept for Apr 1989 for Salem,Unit 1.W/ 890511 Ltr

ML18101A479
Person / Time
Site:	Salem
Issue date:	04/30/1989
From:	Miller L, Orticelle A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905230340
Download: ML18101A479 (10)

Text

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.*.-o PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station flay 11, 1989 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 April 1989 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information sk~

L. K. Miller General Manager -

Salem Operations RH: sl cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4

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.e AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date 5-09-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 4451 Month APRIL 1989 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 j,G'*:f

OPERATING DATA REPORT Docket No .50-272 Date: 5~--o-=-=-9--~8~9~--------

Telephone: 935-6000 Completed by Pell White Extension: ~4~4~5~1-------------

Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period April 1989

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 N/A

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9. Power Level to Which Restricted, if any (Net MWe) N/A

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10. Reasons for Restrictions, if any N/A

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This Month Year to Date Cumulative

11. Hours in Reporting Period 719 2879 103752

12. No. of Hrs. Reactor was Critical 0 1862.33 66 494. 53

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 1811.75 64 447. 65

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 6106848 201543640.4

17. Gross Elec. Energy Generated (MWH) 0 2039200 66986380

18. Net Elec. Energy Generated (MWH) -4020 1945095 63751219

19. Unit Service Factor 0 62.9 62.1

20. Unit Availability Factor 0 62.9 62.1

21. Unit Capacity Factor (using MDC Net) 0 61.1 55.6

22. Unit Capacity Factor (using DER Net) 0 60.6 55.1 2 3. Unit Forced Outage Rate 0 12.2 22.1

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:

Unit currently in 8th refueling outage scheduled start date May 26, 1989.

8-l-7.R2

HNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272

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REPORT MONTH APRIL 1989 Unit Name Salem No.I Date 5-09-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 C od*e 5 Prevent Recurrence NUCLEAR REACTOR 0071 4-01-89 s 719 c 4 ------ CA VESSEL OVERHAUL GENERATOR MAJOR 0071 4-01-89 s 719 c 4 ------ HA GENERA OVERHAUL MAJOR TURBINE 007 1 4-01-89 s 719 c 4 ------ HA TURBIN OVERHAUL 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit-F: Forced A-Equipment Failure-explain 1-Man ua 1 Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Refue ling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-0ther (LER) File H-Other-explain (NUREG 0161)

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 890125071 1 EMERG. AIR COMPRESSOR FAILURE DESCRIPTION: #1 EMERG. AIR COMPRESSOR OIL LEAK / REPLACE GASKET.

890330094 1 lSAll 8 FAILURE DESCRIPTION: FAILED LEAK RATE TEST/MARK NO. A-157. INSPECT.

890330112 1 lSAll 9 "FAILURE DESCRIPTION: FAILED LEAK RATE TEST / MARK NO. A-165. INSPECT.

890410160 1 1C5Y FAILURE DESCRIPTION: lC VTL INSTR. BUS INVERTER BREAKER/CHANGE OVERLOAD.

890413128 1 RX CAVITY LIGHTING FAILURE DESCRIPTION: RX CAVITY LIGHTING/TROUBLESHOOT.

890425105 1 11SJ188 FAILURE DESCRIPTION: LEAKING THRU/CLEAN OFF BORIC ACID & CAP END OF PIPE.

SALEr1 UNIT 1 890425112 1 11SJ189 FAILURE DESCRIPTION: LEAKING THRU/CLEAN OFF BORIC ACID & CAP END OF PIPE.

890425113 1 12SJ188 FAILURE DESCRIPTION: LEAKING THRU/CLEAN OFF BORIC ACID & CAP END OF PIPE ..

890425119 1 12SJ189 FAILURE DESCRIPTION: LEAKING THRU/CLEAN OFF BORIC ACID & CAP END OF PIPE.

.MAJbR PLANT MODIFICATIONS DOCKET NO.: 50*-272

~EPORT MONTH APRIL 1989 UNIT NAME: Salem 1 DATE: May 10, 19 89 COMPLETED BY: P. White TELEPHONE: 609/339-4455

• DCR NO. PRINCIPAL SYSTEM DESCRIPTION lEC-02065 Charging This design change added a pulsation dampener to the discharge of the positive displacement charging pump.

lEC-02066 Charging This design change added a suction stabilizer to the piping upstream of the #13 positive displacement charging pump.

lEC-02173 Turbine Controls This design change installed AMSAC (ATWS Mitigation System Actuation Circuitry).

lEC-02271 Electrical This design change eliminated the 91% voltage vital bus transfer scheme between station power transformers and provided (3) 91% undervoltage relays wired to each vital bus providing inputs to its SEC unit for a 2 of 3 logic to the diesel generator.

• DCR - Design Change Request

e MAJOR PLANT MODIFICATIONS e

DOCKET NO.: 50-272 REPORT MONTH APRIL 1989 UNIT NAME: Salem 1 DATE: May 10, 19 89 COMPLETED BY: P. White TELEPHONE: 609/339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 lEC-02065 This design change added a pulsation dampener to the discharge of #13 positive displacement charging pump. The unit selected is _a gas charged bladder design which is currently in use at a number of other nuclear plants. There was no change to any plant process or discharge or to the environmental impact of the plant. "No unreviewed safety or environmental questions are involved.

lEC-02066 This design change added a suction stabilizer to the piping upstream of #13 positive displacement charging pump. The unit selected is a gas charged bladder design which is currently in use at a number of other nuclear plants. There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lEC-02173 This design change installed AMSAC (ATWS Mitigation Actuation Circuitry). The system provides a diverse means for tripping the main steam turbine and initiating auxiliary feedwater in the event of an anticipated transient without a scram. There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lEC-02271 This design change eliminated the 91% voltage vital bus transfer scheme between station power transformers and provided (3) 91% undervoltage relays wired to each vital bus providing inputs to its SEC unit for a 2 of 3 logic to the diesel generator. There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 APRIL 1989 SALEM UNIT NO. 1 The Unit was shutdown for the entire period for a refueling outage.

Major work accomplished during the period included the following:

1. Reassembly of nos. 12 & 14 Reactor Coolant Pump Seals;

2. Containment Fan Coil Unit service water piping replacement;

3. Eddy current examination of Steam generator tubes, and

4. Fuel element ultrasonic testing and full face visual inspection

5. Replacement of Vital Instrument Inverter Fuel element visual inspection and ultrasonic testing disclosed a total of eleven (11) assemblies requiring further examination. An evaluation of the affected assemblies cleared six (6) for re-use, five (5) were identified for replacement.

Eddy current testing showed thirty two tubes indicating greater than 30% wear and all 362 row one tubes are to be plugged. Additionally, three plugs from previously plugged tubes have been removed for analysis as a follow up to the North Anna tube plug failure.

REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: P. White UNIT NAME: Salem 1 DATE: May 10, 19 89 TELEPHONE: 609/935-6000 EXTENSION: 4497 Month APRIL 1989

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: March 28, 1989

3. Scheduled date for restart following refueling: May 24, 1989

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? May 1989

5. Scheduled date(s) for subm~tting proposed licensing action:

May if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Inc ore 193 B) In Spent Fuel Storage 540

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: September 2001 8-1-7.R4