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

OPS~G

• 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.

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 RH:pc 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 ~L Docket No.: 50-311 Unit Name: Salem #2

• Date: 10/11/90 Completed by: Art Orticelle Telephone: 609-339-2122 Month SEPTEMBER 1990 Day Average Daily Power Level Day Average Daily Power Level

{MWe-NET} {MWe-NET}

• 1 573 17 1080 2 585 18 1079 3 1054 19 1101 4 67 20 1117 5 0 21 962 6 0 22 1107 7 0 23 1032 8 116 24 1073 9 943 25 1052 10 1044 26 1086 11 1013 27 1078 12 1028 28 1096 13 1042' 29 1041 14 1098 30 1071 15 1058 31 16 1063 P. 8.1-7 Rl

• 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 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 Year to Date Cumulative

11. Hours in Reporting Period 720 6551 78600

12. No. of Hrs. Rx. was Critical 664. 5 . 3141.4 49147.2

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 612.5 2955.9 47501.1

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1990867.2 9582396.0 98634135.4

17. Gross Elec. Energy Generated (MWH) 659442 3209572 49256624

18. Net Elec. Energy Gen. (MWH) 629290 3030116 46830022

19. Unit Service Factor 85.1 45.1 60.4

20. Unit Availability Factor 85.1 45.1 60.4

21. Unit Capacity Factor (using MDC Net) 79.0 41.8 53.9

22. Unit Capacity Factor (using DER Net) 78.4 41.5 53.4

23. Unit Forc~d Outage Rate 14.9 10.2 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

UNIT SHUTDOWN AND POWER REDUCTIONS DOCKET NO. : -'5~0:...*=3..:...11,___ _~

REPORT MONTH SEPTEMBER 1990 UNIT NAME: Salem #2 DATE: 10/10/90 COMPLETED BY: Art Orticel le' TELEPHONE: 339-2122

,-----r-------T -----,

I METHOD OF I I I I I SHUTTING LICENSE I I I I I DURATION 2

DOWN EVENT I SYSTE~ I COMPO~ENT I CAUSE AND CORRECTIVE ACTION I NO. DATE I TYPE (HOURS) REASON REACTOR I REPORT # I CODE I CODE I TO PREVENT RECURRENCE I

+- F -+------+--- * - - + - - - - -

0064 09/01/90 I 41.1 B 5 I --------- I CH I PUMPXX #21 SG Feed Pump

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

0067 09/04/90 F 107.5 A 3 ' --------- J CH I PUMPXX I #21 SG Feed Pump *

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

0081 09/24/90 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-----+------+-----+------+------+-----+------+-------+---

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

!----+----+----~-----+------+------+

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

1----+-~-~~-+---~-+-~---+~~-+-----+-~--t-~~--+i~~~~~~---j-

' I I I I I 11191" 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-Regulatory 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)

• SAFETY RELATED MAINTENANCE

• DOCKET NO: 50-311 MONTH: - SEPTEMBER 1990 UNIT NAME: SALEM 2 DATE: OCTOBER 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: ( 609) 339-2068 WO NO UNIT EQUIPMENT IDENTIFICATION 900109081 2 SW BAY SUMP LINES 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 22 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: LOW SPEED BREAKER TRIPS -

TROUBLESHOOT 900918203 2 22 REACTOR COOLANT PUMP FAILURE DESCRIPTION: PERFORM 10 YEAR INSERVICE

• INSPECTION OF 22RCP FLYWHEEL

MAJOR PLANT MODIFICATIONS MONTH: - SEPTEMBER 1990

• DOCKET NO:

UNIT NAME:

50-311 SALEM 2 DATE: OCTOBER 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (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 defect~ve 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, 1~90, 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

• DOCKET NO: 50-311 MONTH: - SEPTEMBER 1990 UNIT NAME: SALEM 2 DATE: OCTOBER 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 MONTH SEPTEMBER 1990

1. Refueling information has changed from last month:

YES NO ~~X~~

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 ~-x~_

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 r~fueling:

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