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

e .*.-o Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 flay 11, 1989 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. RH: sl Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information L. K. Miller General Manager -Salem Operations cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 -----")*-*4(")

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o5otu272 R PDC The Energy People ff14 'l I 95-2189 (SM) 12-88 Completed by Month APRIL .e AVERAGE DAILY UNIT POWER LEVEL Art Orticelle 1989 Docket No. Unit Name Date Telephone Extension Day Average Daily Power Level Day Average Daily (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 50-272 Salem # 1 5-09-89 609-935-6000 4451 Power Level j,G'*:f OPERATING DATA REPORT Completed by Pell White Operating Status Docket No .50-272 Date:

Telephone:

935-6000 Extension:

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

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

10. Reasons for Restrictions, if any N/A

11. Hours in Reporting Period 12. No. of Hrs. Reactor was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Generated (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 2 3. Unit Forced Outage Rate This Month Year to Date 719 2879 0 1862.33 0 0 0 1811.75 0 0 0 6106848 0 2039200 -4020 1945095 0 62.9 0 62.9 0 61.1 0 60.6 0 12.2 Cumulative 103752 66 494. 53 0 64 447. 65 0 201543640.4 66986380 63751219 62.1 62.1 55.6 55.1 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 Completed by No. Date 0071 4-01-89 0071 4-01-89 007 1 4-01-89 1 F: Forced S: Scheduled HNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH APRIL 1989 Unit Name Date Telephone Extension Salem No.I Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1 s s s 2 Reactor 719 c 4 719 c 4 719 c 4 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refue ling D-Regulatory Restriction Report ------------------E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Code 4 CA HA HA 3 Method 1-Man ua 1 Component C od*e 5 VESSEL GENERA TURBIN 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 5-09-89 609-935-6000 4451 Cause and Corrective Action to Prevent Recurrence NUCLEAR REACTOR OVERHAUL GENERATOR MAJOR OVERHAUL MAJOR TURBINE OVERHAUL 4 Exhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Salem as Source WO NO 890125071 890330094 890330112 890410160 890413128 890425105 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1 EMERG. AIR COMPRESSOR FAILURE DESCRIPTION:

1. 1 EMERG. AIR COMPRESSOR OIL LEAK / REPLACE GASKET. 1 lSAll 8 FAILURE DESCRIPTION:

FAILED LEAK RATE TEST/MARK NO. A-157. INSPECT. 1 lSAll 9 "FAILURE DESCRIPTION:

FAILED LEAK RATE TEST / MARK NO. A-165. INSPECT. 1 1C5Y FAILURE DESCRIPTION:

lC VTL INSTR. BUS INVERTER BREAKER/CHANGE OVERLOAD.

1 RX CAVITY LIGHTING FAILURE DESCRIPTION:

RX CAVITY LIGHTING/TROUBLESHOOT.

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 MONTH APRIL 1989 *DCR NO. PRINCIPAL SYSTEM lEC-02065 Charging lEC-02066 Charging lEC-02173 Turbine Controls lEC-02271 Electrical

• DCR -Design Change Request DOCKET NO.: 50*-272 UNIT NAME: Salem 1 DATE: May 10, 19 89 COMPLETED BY: P. White TELEPHONE:

609/339-4455 DESCRIPTION This design change added a pulsation dampener to the discharge of the positive displacement charging pump. This design change added a suction stabilizer to the piping upstream of the #13 positive displacement charging pump. This design change installed AMSAC (ATWS Mitigation System Actuation Circuitry).

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.

e MAJOR PLANT MODIFICATIONS e DOCKET NO.: 50-272 REPORT MONTH APRIL 1989 UNIT NAME: Salem 1 *DCR lEC-02065 lEC-02066 lEC-02173 lEC-02271 DATE: May 10, 19 89 COMPLETED BY: P. White TELEPHONE:

609/339-4455 SAFETY EVALUATION 10 CFR 50.59 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.

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.

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.

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 UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT NO. 1 APRIL 1989 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.

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• 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 proposed licensing action: May if required 6. Important licensing considerations associated with refueling:

7. 8. 9. NONE Number of Fuel Assemblies:

A) Inc ore B) In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:

8-1-7.R4 193 540 1170 1170 September 2001