ML18093B028

Monthly Operating Rept for Jul 1988 for Salem Unit 1. W/880810 Ltr

ML18093B028
Person / Time
Site:	Salem
Issue date:	07/31/1988
From:	RONAFALVY J, WHITE P, ZUPKO J M Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8808220217
Download: ML18093B028 (11)

Text

• AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month JULY 1988 Day Average Daily Power Level (MWe-NET) 1 1095 --*---------

2 1102 -3 1099 4 1098 5 1090 ---------6 1113 7 10 82 8 1100 --------9 1084 --*---------

10 1090 ------------

11 10 83 12 1083 ------------**---

13 1108 --**---------

14 1077 15 10 61 16 1097 --*--P. 8.1-7 Rl Day Docket No. Unit Name Date Telephone Extension 50-27 2 -saieffi#-1

-*-----*s -4:. 8a 6cr9::93-5

___ 6_0 _o o-* 4451 Average Daily Power Level (MWe-NET) 17 1074 18 1087 19 1060 20 1071 21 1080 22 1082 23 1074 24 1086 25 1080 26 1090 27 1044 -*------28 1088 29 1066 30 1051 31 1067

. ' *

• OPERATING DATA REPORT Docket No .50-272 Date:

Completed by Pell White Telephone:

935-6000 Extension:

Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period July 1988 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)ll49 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 This Month 11. Hours in Reporting Period 744 12. No. of Hrs. Reactor was Critical 744 13. Reactor Reserve Shutdown Hrs. 0 14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0 16. Gross Thermal Energy Generated

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(MWH) 2541662.4

17. Gross Elec. Energy Generated (MWH) 839880 18. Net Elec. Energy Generated (MWH) 805491 19. Unit Service Factor 100 2 0. Unit Availability Factor 100 21. Unit Capacity Factor (using MDC Net) 97.9 22. Unit Capacity Factor (using DER Net) 97 .1 2 3. Unit Forced Outage Rate 0 Year to Date 5111 3423.3 0 33 49. 2 0 11292842.8 3778840 3601183 65.6 65.6 63.7 63.2 1.1 Cumulative 97200 6112735 0 59140.9 0 18 3561851. 6 60973330 57997392 60.8 60.8 53.9 53.5 23 *. 2 24. Shutdowns scheduled over next 6 months (type, date and duration of each) N/A 25. If shutdown at end of Report Period, Estimated Date of Startup: N/A 8-l-7.R2 Completed by No. Date N/A 1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1988 D o c ke t No . 5 0 -2 7 2 Unit Name Date Telephone Extension Salem No.1 Pell White Type 1 Duration Hours Reason 2 Method of Shutting Down Reactor License Event Report 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Code 4 3 Method 1-Manual Component Code 5 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther August 4, 1988 609-935-6000 44 51 ** Cause and Corrective Action to Prevent Recurrence 4 Exhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

• 5 Exhibit 1 Salem as Source

• PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO IDENTIFICATION 870401046 870602041 870708038 880120046 880208141 1 lA SWG 97 FAILURE DESCRIPTION:

NOT ATTACHED TO PIPE PLEASE REPAIR. 1 11 S.W.P. FAILURE DESCRIPTION:

HANGER MISSING. REPLACE HANGER. 1 12CCHX FAILURE DESCRIPTION:

HAS NO FLOW IN AUTO/CORRECT.

HAS NO FLOW WHEN TEMP CONTROLLER REACHES SET POINT. 1 13SW24 FAILURE DESCRIPTION:

DAMAGE VALVE BODY/REPLACE/MK.

NO. M-114 1 1S27C FAILURE DESCRIPTION:

HOLE IN PIPE BEFORE 15SW274/REPAIR.

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* -, *

• WO NO 880428101 880526040 880613104 880620078 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1 11 WASTE GAS COMPRESSOR FAILURE DESCRIPTION:

INOPERABLE/REPLACE.

1 lB DIESEL FAILURE DESCRIPTION:

LINE TO TURBO./LEAK/REWORK.

THERE IS A LEAK ON THE 1/2" COOLING LINE TO THE TURBO. 1 1ABV15 FAILURE DESCRIPTION:

SUPPLY REG/BLOWING AIR/REPLACE.

1 lRlB FAILURE DESCRIPTION:

MONITOR IN WARN/INVESTIGATE AND REPAIR. .! 880705143

• 1 1CC71 FAILURE DESCRIPTION:

LTDWN CTL VLV/NOT CONTROLLING/TROUBLESHOOT.

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880718085 880718121 880727080 900714001 1 lC D-G FAILURE DESCRIPTION:

TURBO AIR COMP/NOT STARTING/TROUBLESHOOT.

1 1R41A FAILURE DESCRIPTION:

PLNT VNT PART RAD MONITOR IS FAILED. TROUBLESHOOT/REWORK.

1 14 LOOP FAILURE DESCRIPTION:

14 REACTOR COOLANT LOOP T AVE/DELTA T HAS FAILED HIGH. 1 12 S.W. PUMP FAILURE DESCRIPTION:

INSP./PULL AND REPLACE WITH SPARE. PULL 12 SERVICE WTR PUMP AND INSTALL REBUILT PUMP. * *

• MAJOR PLANT MODIFICATIONS REPORT MONTH JULY 1988 *OCR NO. lEC-1181 lEC-2188 lSM-0091 lSM-0472 PRINCIPAL SYSTEM Radiation Monitoring Service Water PASS Air Regulator Component Cooling

• DCR -Design Change Request

• DOCKET NO.: 50-272 UNIT NAME:

DA TE : --A U9: us t 10 I 19 8 8 COMPLETED BY: J. Ronafalvy TELEPHONE:

609/339-4455 DESCRIPTION This modification added five high range main steam line monitors.

The monitors are qualified for post-accident operation.

This modification installed a "cross type" vortex breaker beneath the bellmouth of No. 16 Service Water Pump to inhibit cavitation.

This modification replaced the instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident.

This modification installed an OFF Delay Relay in the control circuitry of Valve 1CC131 to prevent closure of the valve due to the resulting pressure transient caused by starting a Service Water pump.

• MAJOR PLANT MODIFICATIONS REPORT MONTH JULY 1988 DOCKET NO. 50-272 UNIT NAME:

• DCR lEC-1181 lEC-2188 lSM-0091 lSM-0472 DATE: August 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE:

609/339-4455 SAFETY EVALUATION 10 CFR 50.59 -------This modification added monitors to detect any possible activity in the Main Steam lines. This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

The addition of this new regulator will allow the PASS System to operate at accident temperatures as it was originally designed.

This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients.

This modification did not alter any plant process or discharge or affect 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 JULY 1988 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation.

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• REFUELING INFORMATION DOCKET NO.: COMPLETED BY: J. Ronafalvy UNIT NAME: 50-272 Salem 1 DATE: TELEPHONE:

EXTENSION:

August 10, 19 88 609/935-6000 4497 Month JULY 1988 1. Refueling information has changed from last month: YES NO X -----2. Scheduled date for next refueling:

April 15, 1989 3. Scheduled date for restart following refueling:

May 30, 1989 4. A) B) Will Technical Specification changes or other license amendments be required?

YES NO ----NOT DETERMINED TO DATE X Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled?

February 1989 5. Scheduled date(s) for submitting proposed licensing action:

if required 6. Important licensing considerations associated with refueling:

NONE 7. Number of Fuel Assemblies:

A) Inc ore B) In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

9. Date of last refueling that can be discharged to spent fuel pool assuming the present 19 3 464 1170 1170 licensed capacity:

_September 2001 8-l-7.R4

-1. *

• Public Service Electric and Gas Company P.O. Box E 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 August 10, 1988 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 July 1988 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 Sincerely yours, J. Pii::-1: 9 . 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 The Energy People ' \ 95-2189 (11 M) 12-84