ML18095A810

Monthly Operating Rept for Feb 1991 for Salem Unit 2

ML18095A810
Person / Time
Site:	Salem
Issue date:	02/28/1991
From:	Orticelle A, Thomson F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9103250387
Download: ML18095A810 (10)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 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 February 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 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 ~~Q~-----

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e OPERATING DATA REPORT -

Docket No:

50-311 Date:

3/10/91 Completed by:

Art Orticelle Telephone:

339-2122 Operating status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period February 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

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 672 1416 82225

12. No. of Hrs. Rx. was Critical r,-- 13. Reactor Reserve Shutdown Hrs.

(

14. Hours Generator On-Line 672 0

674 1416 52772.2 0

0 1416 51126.1

(_

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15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Elec. Energy Generated (MWH)

18. Net Eiec. 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 Forced Outage Rate 0

2260360.8 752987 723348 100 100

. 97. 3 96.5 0

0 4786917.6 1606179 1543844 100 100 98.6 97.8 0

0 110780386.6 53338106 50751655 62.2 62.2 55.8 55.4 23.8

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

Mid Cycle. 05/11/91. two weeks

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

NA 8-1-7.R2

.ERAGE DAILY UNIT POWER L~L Docket No.:

50-311 Unit Name:

Salem #2 Date:

3/10/91 Completed by:

Art Orticelle Telephone:

339-2122 Month February 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1064 17 1070 2

1002 18 1055 3

1094 19 1084 4

1094 20 1087 5

1096 21 1100 6

1099 22 1109 7

1088 23 1086 8

1098 24 1054

(

I 9

1086 25 1100 10 1093 26 1098 11 1119 27 1105 12 1099 28 1072 13 1102 29 14 942 30 15 827 31 16 1060

(

P. 8.1-7 Rl

NO.

DATE 0008 01/30/91 0009 02/01/91 0012 02/01/91 0010 02/13/91 0011 02/14/91 1

F:

Forced S: Scheduled DURATION TYPE1 (HOURS)

REASON 2 F

F F

F F

2 Reason 29.1 24.0 342.2 18.9 34.1 A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction B

B B

B B

UNIT SHUTDO~N AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1991 METHOD OF SHUTTING DOWN REACTOR 5

5 5

5 5

LICENSE EVENT SYSTEM REPORT #

COOE4 HA HH HH HG HH

.3

• Method:

1-Manual 2-Manual Scram 3-Automatic Scram E-Operator Training & License Examination F-Aaninistrative 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain) 4 COMPONENT COOE6 GENERA PUMPXX PUMP XX HTEXCH PUMPXX DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #2 3/10/91 Art Orticelle 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE Rotor Collector Rings Generator Feed Water Heater Drain PLll'DS Feed Water Heater Drain PlillJS Condensor Tube and Water Box Cleaning Feed ~ater Heater Drain PLlllY><<

5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 - Same Source (NUREG-0161)

• ...............,/

, SAFETY RELATED MAINTENANCE MONTH: -

FEBRUARY 1991 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 900820130 2

901026072 2

910130129 2

910219207 2

DATE:

COMPLETED BY:.

TELEPHONE:

MARCH 10, 1991 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION FHB EXHAUST FAN -

2VHE20 FAILURE DESCRIPTION:

BROKEN BOLT IN FAN BELT SHROUD BRACKET -

REPLACE RD-2-SW-906 -

2A DIESEL SW SPOOL FAILURE DESCRIPTION:

REPLACE SPOOL RD-2-SW-906 SPOOL 2-SW-2319 FAILURE DESCRIPTION:

SPOOL ERODED AT FLANGE -

REPAIR RADIATION MONITOR 2R45B FAILURE DESCRIPTION:

2R45B IS SPIKING INTO ALARM -

TROUBLESHOOT AND REPAIR

---~----------------------------------------------------------------------

10CFR50.59 EVALUATIONS MONTH: -

FEBRUARY 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 MARCH 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.

Design Change Packages 2EC-3046 Pkg 1 2EC-3068 Pkgs. 1-4 B.

Procedures and Revisions OPS. PROC. II-1.3.6 "NIS Console Rear Panel Door Extension" -

This DCP adds a new door to the rear access panel of the Nuclear Instrumentation System (NIS) console to provide additional depth for enclosing cables which presently protrude beyond the existing panel envelopes The purpose of this modification is to avoid potentially adverse interaction between the normally open doors and the protruding cables.

Installation of the new rear door extends the cabinet envelope and reduces the potential for an inadvertent reactor trip due to the sensitivity of the NIS equipment.

(SORC 91-015)

"Containment Fan Coil Unit Test Connections" -

The purpose of this design change is to install 1" instrument test connections on the CFCU duct work between the CFCU fans and cooling coils for Unit 2.

Temperature connections are being added to the outlet ductwork at the pitot tube locations to provide the capability to perform heat exchanger performance testing to comply with NRC Generic Letter 89-13.

(SORC 91-016)

"Draining the Reactor Coolant System" Unit 2, Rev. 7" - This revision to the procedure revised the time delay from shutdown to reduced inventory operation with various size hot leg openings and with or without cold leg side openings and operable Stearn Generators.

These changes are being incorporated to implement the Salem-specific Engineering Standard Analysis (PSE 90-557).

Other, minor improvements have also been made to the procedure.

(SORC.91-014)

10CFR50.59 EVALUATIONS MONTH: -

FEBRUARY 1991 (Cont'd)

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 MARCH 10, 1991 F. THOMSON (609)339-2904

---

~--------------------------------

ITEM S2.0P-PM.CC-0021(Q)

S2.0P-PM.CC-0022(Q)

S2.0P-PT.SW-0021(Q)

S2.0P-PT.SW-0022(Q)

SUMMARY

"Component Cooling Heat Exchanger High Flow Flush" - These are new procedures which were developed to meet the intent of NRC Guideline 89-13.

These procedures provide the instruction necessary to collect pressure drop data across the service Water side of the Component Cooling Heat Exchangers so that the relationship between flow and pressure drop can be trended.

(SORC 91-011)

"No. 21 Containment Fan Coil Unit Heat Transfer Performance Data Collection" Rev. 0" - This procedure provides the instruction necessary to collect heat transfer data from No. 21 Containment Fan Coil Unit (CFCU).

The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13.

( SORC 91-016}

"No. 22 Containment Fan Coil Unit Heat Transfer Performance Data Collection" Rev. O" -

This.

procedure provides the instruction necessary to collect heat transfer data from No. 21 Containment Fan Coil Unit (CFCU}.

The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13.

(SORC 91-016}

C.

Temporary Modifications (TMODS}

TMR 91-022 This modification will install a leak repair enclosure around the bonnet of valve 22AF22 to stop the body to bonnet leak that currently exists on the valve.

This modification is required to prevent an over temperature condition from developing on the 2~ Auxiliary Feedwater Header by eliminating a flowpath across the 22AF22 valve.

The removal of the leak path across the pressure seal will prevent the check valve back leakage into the header.

Without a flow path, the header temperature will remain at ambient conditions and design temperatures will be maintained.

(SORC 91-018)

10CFR50.59 EVALUATIONS MONTH: -

FEBRUARY 1991 (Cont'd}

ITEM TMR 91-019 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 MARCH 10, 1991 F. THOMSON (609)339-2904 The purpose of this modification is to install a leak repair clamp surrounding the gasket area of valve 21BF19 to stop a body to bonnet leak.

The leak repair compound is classified as Category 1 and is approved for use in the system.

(SORC 91-018}

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 FEBRUARY 1991 The Unit began the period operating at essentially full power and continued operating at full power until February 14, 1991, when load was reduced to approximately 75% for repairs to the main bus duct cooling fan.

The Unit was restored to full power on February 16, 1991, following repairs to the fan, and continued to operate at essentially full power throughout the remainder of the period.

C'.

~ REFUELING INFORMATION MONTH: -

FEBRUARY 1991 MONTH FEBRUARY 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES x

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

2.

Scheduled date for next refueling:

December 26, 1991

3.

Scheduled date for restart following refueling:

February 9, 1992

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?:

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