ML18095A605

Monthly Operating Rept for Oct 1990 for Salem Unit 2.W/

ML18095A605
Person / Time
Site:	Salem
Issue date:	10/31/1990
From:	Labruna S, Orticelle A, Thomson F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9011260119
Download: ML18095A605 (10)

Text

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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department November 15, 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 October 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 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 Enclosures 8-1-7.R4 19046 The Energy People ----s:,6i 1u".(:iT:l:~ *~1 Ci:t(>:::::i.------

PDR ADOCK 05000311 l_. \\_....,..:.-.,~ ~J 1;:

F'DC r&:v+

111 95-2168 (100M) 12-84

.VERAGE DAILY UNIT POWER L~L 1

Docket No.:

50-311 Unit Name:

Salem #2 Date:

11/10/90 Completed by:

Art Orticelle Telephone:

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

(MWe-NET) 1 1081 17 1091 2

1103 18 1081 3

1080 19 1112 4

1064 20 1081 5

1077 21 1085 6

479 22 1108 7

609 23 1097 8

845 24 1092 9

1076 25 1102 10 1110 26 1103 11 1110 27 1085 12 1060 28 1104 13 947 29 1102 14 1010 30 1109 15 1089 31 1112 16 1115 P. 8.1-7 R1

OPERATING DATA REPORT.

Docket No:

50-311 Date:

11/10/90

, Completed by:

Art Orticelle Telephone:

339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period October 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) 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~~~~~~~~~~~~~~~

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 2 o..Unit Availability Factor

21. Unit Capacity Factor (using MDC Net)

22. Unit Capacity Factor (using DER Net)

23. Unit Forced Outage Rate This Month 745 745 0

745 0

2470128.0 823096 790275 100 100 95.9 9-5.1 0

Year to Date 7296 3886.4 0

3700.9 0

12052524.0 4032668 3820391 50.7 50.7 47.3 47.0 8.3 Cumulative 79345 49892.2 0

48246.l 0

101104263.4 50079720 47'620297 60.8 60.8 54.3 53.8 24.9

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:

NA 8-1-7.R2

NO.

DATE 0085 10/06/90 0086 10/06/90 0087 10/06/90 0088 10/06/90 0091 10/07/90 0089 10/08/90 0090 10/08/90 2

F:

Forced S:

Scheduled DURATION TYPE1 (HOURS)

REASON 2 F

7.3 F

3.4 F

5.6 F

16.8 F

19.1 F

3.2 F

4.8 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction B

B B.

B B

B B

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1990 METHOD OF SHUTTING DOWN REACTOR 5

5 5

5 5

5 5

3 LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 HH HH HH HH HH HH HH E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain) 4 DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 Salem #2 11/10/90 Art Orticel le 339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE5 TO PREVENT RECURRENCE PUMPXX

1. 21 HD TANK PUMP PUMPXX

1. 21 HD PUMP & 21 COND. PUMP PUMPXX

1. 21 HD PUMP & 21 COND. PUMP & 22 SGFP PUMPXX

1. 21 HD PUMP & 21 COND. PUMP & 22 SGFP PUMP XX

1. 21 HD PUMP & 23 COND. PUMP PUMP XX

1. 22 COND. PUMP PUMPXX

1. 22 COND. PUMP 5

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

Exhibit 1 - Sarne Source

SAFETY RELATED MAINTENANCE MONTH: -

OCTOBER 1990 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 870815154 2

900110165 2

901008201 2

921121003 2

940113001 2

2B DIESEL GENERATOR DATE:

COMPLETED BY:

TELEPHONE:

NOVEMBER 10, 1990 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

SERVICE OR REPLACE AIR START MOTOR 2C DIESEL GENERATOR FAILURE DESCRIPTION:

TROUBLESHOOT OIL LEAKS IN THE VICINITY OF lL, 6R CYLINDERS 25SW2 FAILURE DESCRIPTION:

REPLACE THE VALVE AS PER THE CODE JOB PACKAGE 26SW2 FAILURE DESCRIPTION:

REPLACE THE VALVE AS PER THE CODE JOB PACKAGE 24 REACTOR COOLANT PUMP FAILURE DESCRIPTION:

INSPECT AND REPLACE PUMP SEALS

MAJOR PLANT MODIFICATIONS MONTH: -

OCTOBER 1990

• DCR PRINCIPAL SYSTEM None for the period.

DCR -

Design Change Request DOCKET NO:

50-311 UNIT NAME:

SALEM 2 DATE:

COMPLETED BY:

TELEPHONE:

NOVEMBER 10, 1990 F. THOMSON (609) 339-2904 DESCRIPTION

10CFR50.59 EVALUATIONS MONTH: -

OCTOBER 1990 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 NOVEMBER 10, 1990 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 A.

Design Change Packages 2SC-2154 Pkg. 1 2SC-02183 Pkg. 1 2SC-2017 2SC-2271 B.

Procedures and Revisions 2 IC-18.1.010 2 IC-18.1.011

SUMMARY

"Control Room Modifications" -

The purpose of this design change is to implement corrective actions required to resolve forty nine (49) of the Human Engineering Discrepancies identified in the Salem Unit 2 Control Room and various additional changes requested by PSE&G.

(SORC 90-149)

"Installation and Upgrade of Penetration Seals" The purpose of this design change is to install/ upgrade penetration seals in selected penetrations located in the Auxiliary Building.

(SORC 90-149)

"Unit No. 2 Chiller Condenser Piping Replacement" -

The purpose of this design change is to replace the existing 4" lined carbon steel Service Water (SW) piping to Nos. 21, 22 and 23 Chiller Condensers with 6% molybdenum stainless steel.

(SORC 90-143)

"Panel 335 Fire Suppression System" -

The purpose of this design change is to add a fire detection and dry pipe fire suppression system for Panel 335, located in Containment at el.

100 I -0.

( SORC 90-146)

"SSPS Train A, Rx Trip Breaker UV Coil and Auto Shunt Trip" Rev. 4 -

The purpose of this revision is to reflect the changes in the reporting requirements.

(SORC 90-149)

"SSPS Train B, Rx Trip Breaker UV Coil and Auto Shunt Trip" Rev. 4 -

The purpose of this revision is to reflect the changes in the reporting requirements.

( SORC 90-149}

1~0CFR50. 59 EVALUATIONS MONTH: -

OCTOBER 1990 (Cont'd)

ITEM 2 IC-18.4.002 2 IC-18.4.005 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 NOVEMBER 10, 1990 F. THOMSON (609)339-2904 "Response Time of SSPS Logic -

Rx Trip -

A" Rev.

2 -

The purpose of this revision is to reflect the changes in the reporting requirements.

(SORC 90-149)

"Response Time of SSPS Logic -

Rx Trip -

B" Rev.

2 -

The purpose of this revision is to reflect the changes in the reporting requirements.

(SORC 90-149)

C.

Temporary Modifications (TMODS)

STD 90-114 The purpose of this modification is to perform a temporary leak repair on Valve 22MS44.

This TMOD will replace cap nuts on a mechanical joint on the 22MS44 Valve with slotted cap nuts.

Sealing compound is then to be injected into the slotted cap nuts in an attempt to eliminate a joint leak.

This joint leak cannot be repaired with the Unit at power, however, a permanent repair will be made during the next outage of sufficient duration or the 2R6 outage.

( SORC 90-142)

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 OCTOBER 1990 The Unit began the period operating at 100% power.

On October 6, 1990, power was reduced to perform scheduled maintenance on feed and condensate components.

The maintenance activities were completed and the Unit was restored to 100% power on October 8, 1990.

The Unit continued to operate at essentially full power throughout the remainder of the period.

REFUELING INFORMATION MONTH: -

OCTOBER 1990 MONTH OCTOBER 1990 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO ~_X __

50-311 SALEM 2 NOVEMBER 10, 1990 F. THOMSON (609)339-2904

2.

Scheduled date for next refueling:

November 30, 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?:

October 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