ML18095A532

Monthly Operating Rept for Sept 1990 for Salem Unit 2.W/ 901012 Ltr

ML18095A532
Person / Time
Site:	Salem
Issue date:	09/30/1990
From:	LABRUNA, MORRONI M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9010240140
Download: ML18095A532 (8)

Text

Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 12, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 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 reports for the month of September 1990 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Sincerely yours, General Manager -Salem Operations cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 \ The Energy People 95-2189 (11M)12-84

.. VERAGE DAILY UNIT POWER Completed by: Art Orticelle Month SEPTEMBER 1990 Day Average Daily Power Level {MWe-NET}

• 1 573 2 585 3 1054 4 67 5 0 6 0 7 0 8 116 9 943 10 1044 11 1013 12 1028 13 1042' 14 1098 15 1058 16 1063 P. 8.1-7 Rl Day Docket No.: Unit Name: Date: Telephone:

50-311 Salem #2

• 10/11/90 609-339-2122 Average Daily Power Level {MWe-NET}

17 1080 18 1079 19 1101 20 1117 21 962 22 1107 23 1032 24 1073 25 1052 26 1086 27 1078 28 1096 29 1041 30 1071 31

• OPERATING DATA REPOR ... Docket No: 50-311 Date: 10-11-90 Completed by: Art Orticelle Telephone:

609-339-2122 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period SEPTEMBER 1990 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) 1.106 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give

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

10. Reasons for Restrictions, if any N/A

11. Hours in Reporting Period 12. No. of Hrs. Rx. 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 Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Outage Rate This Month 720 664. 5 . 0 612.5 0 1990867.2 659442 629290 85.1 85.1 79.0 78.4 14.9 Year to Date 6551 3141.4 0 2955.9 0 9582396.0 3209572 3030116 45.1 45.1 41.8 41.5 10.2 Cumulative 78600 49147.2 0 47501.1 0 98634135.4 49256624 46830022 60.4 60.4 53.9 53.4 25.2 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: N/A 8-l-7.R2 NO. DATE 0064 09/01/90 0067 09/04/90 0081 09/24/90 I I I DURATION I TYPE (HOURS) REASON 2 +-I F 41.1 B UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH SEPTEMBER 1990 ,-----r-------T METHOD OF I I I SHUTTING LICENSE I I I EVENT I I

I REACTOR I REPORT # I CODE I CODE I DOWN -+------+---

• --+-----5 I ---------I CH I PUMPXX DOCKET NO. :

__ UNIT NAME: Salem #2 DATE: 10/10/90 COMPLETED BY: Art Orticel le' TELEPHONE:

339-2122 -----, CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE

1. 21 SG Feed Pump I I I I +----+-----+----------+----+-------+-------+-

F 107.5 A ' ---------J CH I PUMPXX I #21 SG Feed Pump * +---------+-------+

3 F 3.4 A I 5 I ---------I IB J INSTRU I 2C Safeguards Equip. Cabinet J -+------+-----+----+------------------1 I I I I I I *--+-------+*----*--+-------+-------+--------*-----------l

-+--I I I I I-----+------+-----+------+------+-----+------+-------+---

' I I 1----+-----1-----+-----+-----+-----+------+-----+

I I I I I 1----+-----+----t------i-----+-------+------+-----+--------+-----------------l I I I I l----+-----1---

--+-----+-----+----

-+-------+-------+-------+-

---

' I I I I I 11191" 2 F: Forced S: Scheduled Reason: A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain) 3 Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source

• SAFETY RELATED MAINTENANCE MONTH: -SEPTEMBER 1990 DOCKET NO: UNIT NAME: 50-311 SALEM 2 WO NO UNIT 900109081 2 SW BAY SUMP LINES DATE: COMPLETED BY: TELEPHONE:

OCTOBER 10, 1990 M. MORRONI ( 609) 339-2068 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

SW BAY SUMP LINES CLOGGED -SNAKE OUT AND FLUSH 900614065 2 AUXILIARY ANNUNCIATOR FAILURE DESCRIPTION:

AUXILIARY ANNUNCIATOR PT 125 IN ALARM -TROUBLESHOOT

& REWORK --------------------------------------------------------------------------

' 900911164 2 900918203 2 22 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:

LOW SPEED BREAKER TRIPS -TROUBLESHOOT 22 REACTOR COOLANT PUMP FAILURE DESCRIPTION:

PERFORM 10 YEAR INSERVICE

• INSPECTION OF 22RCP FLYWHEEL MAJOR PLANT MODIFICATIONS MONTH: -SEPTEMBER 1990

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 OCTOBER 10, 1990 M. MORRONI (609) 339-2068 -----------------------------------------------------------------------------

• DCR PRINCIPAL SYSTEM DESCRIPTION

---

.------------

None for the period.

• DCR -Design Change Request

-<1 ' *

• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 SEPTEMBER 1990 SALEM UNIT NO. 2 The Unit began the period at reduced power to facilitate repairs to steam leaks on No. 21. Steam Generator Feedwater Pump (SGFP). The repairs were completed and the Unit was restored to 100% power on September 3, 1990. On September 4, 1990, the Unit experienced a Reactor Trip following the loss of 21 SGFP, due to a suction pressure switch and a faulty heater drain valve controller/

positioner.

The Unit was restored to 100% power on September 9, 1990, and, with the exception of several short duration load reductions, operated at essentially full power throughout the remainder of the period. During the period of September 9-30, load reductions occurred due to failure of the P-250 computer during Reactor Trip Breaker Surveillance testing and a faulty relay in the 2C Safeguards Equipment Control cabinet. *

-* ... , ..

• REFUELING INFORMATION MONTH: -SEPTEMBER 1990 MONTH SEPTEMBER 1990

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES NO 50-311 SALEM 2 OCTOBER 10, 1990 M. MORRONI (609) 339-2068 2. Scheduled date for next refueling:

November 30, 1991 3. Scheduled date for restart following refueling:

February 9, 1992 A. a) Will Technical Specification changes or other license amendments be required?:

YES 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?:

October 1991 5. Scheduled date(s) for submitting proposed licensing action: N/A 6. Important licensing considerations associated with

7. Number of Fuel Assemblies:

a. Incore 193 b. In Spent Fuel Storage 316 8. Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

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

March 2003 8-1-7.R4