ML18095A884

Monthly Operating Rept for Mar 1991 for Salem 2

ML18095A884
Person / Time
Site:	Salem
Issue date:	03/31/1991
From:	Orticelle A, Thomson F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9104220271
Download: ML18095A884 (8)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 15, 1991 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 March 1991 are being sent to you.

RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information 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 23G01H Tbe_~riergy People 9104220:271 9fiy:0*-:*1 - -

F'DR 11:iDOCK i:i5(i()&i: 11 R

PDR 95-2189 (10M) 12-89

Month MARCH 1991 Day Average Daily (MWe-NET) 1 1099 2

1090 3

1085 4

662 5

817 6

1092 7

1113 8

1104 9

1095 10 902 11 974 12 1084 13 1100 14 1076 15 1099 16 1107 P. 8.1-7 Rl

~ERAGE DAILY UNIT POWER LE~

Power Level Docket No.

Unit Name Date Completed by Telephone 50-311 Salem #2 04-10-91 Art Orticelle 609-339-2122 Day Average Daily Power Level (MWe-NET) 17 1098 18 1112 19 1093 20 1058 21 1080 22 1120 23 963 24 563 25 972 26 1074 27 1113 28 1106 29 1098 30 1007 31 1024

e OPERATING DATA REPORT e Docket No:

Date:

Completed by:

Art Orticelle Telephone:

Operating status

1.

Unit Name Salem No. 2

2.

Reporting Period MARCH 1991

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 50-311 04-10-91 609-339-2122 Notes

8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA

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)

23. Unit Forced Outage Rate This Month 744 744 0

744 0

2428036.8 810564 776985 100 100 94.4 93.7 0

Year to Date 2160 2160 0

2160 0

7214954.4 2416742 2320828 100 100 97.1 96.4 0

cumulative 82969 53516.2 0

51870.05 0

113208423.4 54148669 51528639 62.5 62.5 56.2 55.7 23.6

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

MAINT. OUTAGE. 5/11/91, APPROX. 14 DAYS

25. If shutdown at end of Report Period, Estimated Date of Startup:

NA 8-1-7.R2

NO.

DA'IE 0013 03/04/91 0014 03/10/91 0015 03/12/91 0016 03/21/91 0017 03/23/91 0018 03/26/91 0020 03/30/91 0019 03/31/91 0021 03/31/91 1

F: Forced S: Scheduled DURATION UNIT SHUTOOWN AND POWER REDUCTIONS REroRI' MONI'II =MAR=CH~l=-99"-=1=-------

MEI'HOD OF SHU'ITING LICENSE OOWN EVENT SYSTEM

<n1PONEN['

OOCKEI' NO.: 50-311

-~--~-

UNIT NAME:

Salem #2 DA'IE: 04-10-91 CX11PLEI'ED BY: Art Orticelle TELEPHONE:

339-2122 C'AUSE AND CDRRFCTIVE ACTION TYPE 1 (HOORS)

REASON z REACIDR REroRI' #

CDDE 4 CDDE 5

'IO PREVENT RFaJRRENCE F

F F

F F

F F

F F

2 Reason:

22.35 12.77 50.50 0.13 23.15 10.43 5.38 2.63 2.98 B

A A

B A

A B

B B

A-Fquipnent Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction 5

5 5

5 5

5 5

5 5

E--Operator Training & license Examination F-Adrninistrative G--Operational Error {Explain)

H-Other (Explain)

HB CH HI HF CI HH SH HF HF 3

Method:

1-Manual 2-llfanual Scram 3-Autanatic Scram 4-COntinuation of Previous outage 5-Load Reduction 9-0ther VALVEX NUCLEAR MN. S'IM. SAEI'Y RElJEF VALVES PUMP XX 22 S'IM GENERA'IOR FEEDPUMP VALVEX NUCLEAR BI..OWOOWN SYSTEM VALVES PUMP XX CIRCUIATING WATER PUMPS HTEXCH NUCLEAR S'IM GENERA'IOR TUBE LEAKS PUMP XX FEEDWATER HEATER DRAIN PUMPS VALVEX POWER OPERATED RELIEF & SAFEIY VALVE PUMP XX CIRCUIATING WATER PUMPS PUMP XX CIRCUIATING WATER PUMPS 4

5 Exhibit G - Instructions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for licensee Event Report (LER) File (NUREXJ-0161)

SAFETY RELATED MAINTENANCE MONTH: -

MARCH 1991 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 910214146 2

910225115 2

DATE:

COMPLETED BY:

TELEPHONE:

APRIL 10, 1991 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION 23 COOLANT CHARGING PUMP FAILURE DESCRIPTION:

INCREASED VIBRATION -

INVESTIGATE.

AND REPAIR VALVE 21SW6 FAILURE DESCRIPTION:

VALVE 21SW6-THRU WALL LEAK UPSTREAM OF VALVE -

REPAIR

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I 10CFR50.59 EVALUATIONS MONTH: -

MARCH 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 APRIL 10, 1991 F. THOMSON (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).

ITEM

SUMMARY

A.

Temporary Modifications (TMODS)

TMR 91-024 TMR 91-027 TMR 91-028 The purpose of this TMOD is to allow 4 of the 5 Containment Fan Coil Units (CFCUs) to operate in the high speed, high flow condition in an attempt to lower Containment pressure/

temperature while 2VC5 is replaced.

The proposed operating conditions are bounded by existing analysis.

The system would still function normally during accident conditions.

(SORC 91-020)

The purpose of this modification is to install cap nuts on the body to bonnet joint of 21BF19, and inject leak repair compound to stop gasket leaks at the body to bonnet joint.

The valve has been analyzed to operate as ~er the original design with the cap nuts in place.

The instruction calls for the replacement of the regular body to bonnet nuts with the cap nuts on a one by one basis.

Therefore, this TMOD is not considered to be maintenance on the valve that would affect its performance.

(SORC 91-026)

The purpose of this modification is to install cap nuts on the body to bonnet joint of 24BF19~

and inject leak repair compound to stop gasket leaks at the body to bonnet joint.

The valve has been analyzed to operate as per the original design with the cap nuts in place.

The instruction calls for the replacement of the regular body to bonnet nuts with the cap nuts on a one by one basis.

Therefore, this TMOD is not considered to be maintenance on the valve that would affect its performance.

(SORC 91-026)

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 MARCH 1991 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued operating at full power until March 4, 1991, when load was reduced to approximately 50% to blowdown 22 Steam Generator Feedwater Pump {SGFP) strainer.

The Unit returned to full power on March 5, 1991, and continued to operate at full power until March 10, 1991, when power was reduced to 50% to blowdown 22 SGFP strainer.

The Unit was returned to full power on March 11, 1991, and continued to operate at full power until March 24, 1991, when load was reduced due to Solar Magnetic Disturbances.

During the power descent, 21 SGFP tripped on a low suction pressure signal.

The' Unit was stabilized at 58% power and the SGFP trip setpoint was reset.

The Unit was returned to full power on March 25, 1991 and continued to operate at essentially full power until March 30, 1991 when load was reduced to approximately 60% to repair the Boron Injection Tank relief valve.

The Unit was returned to full power on March 31, 1991, and continued to operate at full power throughout the remainder of the period.

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e e

REFUELING INFORMATION MONTH: -

MARCH 1991 MONTH MARCH 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES x

NO 50-311 SALEM 2 APRIL 10, 1991 F. THOMSON (609)339-2904

2.

Scheduled date for next refueling:

JANUARY 4, 1992

3.

Scheduled date for restart following refueling:

MARCH 15, 1992

4.

a)

Will Technical Specification changes or other license amendments be required?:

YES NO I

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?:

December 1991

5.

Scheduled date(s)* for submitting proposed licensing action:

N/A

6.

Important licensing considerations associated with refueling:

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