ML18096A209

Monthly Operating Rept for Jul 1991 for Salem Unit 1

ML18096A209
Person / Time
Site:	Salem
Issue date:	07/31/1991
From:	Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9108210059
Download: ML18096A209 (10)

Text

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.O*PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 12, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 July 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, fl/o-t? o-L~,r:

General Manager ~~

Salem Operations cc:

Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures The Energy Pe~p]e

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ttvERAGE DAILY UNIT POWER L~L Completed by:

Mark Shedlock Month July 1991 Day Average Daily Power Level (MWe-NET) 1 1103 2

1089 3

1100 4

1089 5

1094 6

1084 7

1075 8

1093 9

1087 10 1090 11 1094 12 1091 13 1081 14 1087 15 1097 16 1036 P. 8.1-7 Rl Day Docket No.:

50-272 Unit Name:

Salem #1 Date:

8/10/91 Telephone:

339-2122 Average Daily Power Level (MWe-NET) 17 1083 18 1066 19 1103 20 1084 21 1065 22 1043 23 1064 24 1067 25 1066 26 1073 27 1065 28 1087 29 1082 30 1084 31 1067

OPERATING DATA REPORT-Docket No:

50-272 Date:

8/10/91 Completed by:

Mark Shedlock Telephone:

339-2122 Operating status

1.

Unit Name Salem No. 1 Notes

2.

Reporting Period July 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)

10. Reasons for Restrictions, if any

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 Forced Outage Rate This Month 744 744 0

744 0

2539401.6 838300 803727 100 100 97.7 96.9 0

NA Year to Date 5087 3183.9 0

3068.5 0

10262647.2 3400870 3239962 60.3 60.3 57.6 57.1 6.0 NIA Cumulative 123480 80147.4 0

77636.0 0

244325032.4 81113510 77208634 62.9 62.9 56.5 56.1 22.0

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 1

2 F:

Forced S:

Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1991 DURATION TYPE1 (HOURS)

REASON 2 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain) 3 LICENSE EVENT SYSTEM REPORT #

CODE4 Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4

DOCKET NO.:

50-272.

UNIT NAME:

Salem #1 DATE:

8/10/91 COMPLETED BY:

Mark Shedtock TELEPHONE:

339-2122.

COMPONENT CAUSE AND CORRECTIVE ACTION CODE5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)

TO PREVENT RECURRENCE 5

Exhibit 1 - Same Source

SAFETY RELATED MAINTENANCE MONTH: -

JULY 1991 DOCKET NO:

UNIT NAME:

50-272 SALEM 1 WO NO UNIT 901023116 1

901026069 1

910330093 1

910611006 1

910614060 1

910617067 1

910710151 1

910710144 1

DATE:

COMPLETED BY:

TELEPHONE:

EQUIPMENT IDENTIFICATION DIESEL SERVICE WATER SPOOL AUGUST 10, 1991 J. FEST (609)339-2904 FAILURE DESCRIPTION: REPLACE SPOOL RD-l-SW-325-1 DIESEL SERVICE WATER SPOOL FAILURE DESCRIPTION: REPLACE SPOOL RD-1-SW-361 SERVICE WATER SPOOL FAILURE DESCRIPTION: DEGRADED SECTION IN SPOOL RD-1-SW REPLACE WG DEMIN WATER CONTROL VALVE FAILURE DESCRIPTION: VALVE 11WG013 -

REPLACE DIAPHRAGM 15 CONTAINMENT FAN COIL UNIT FLOW INDICATION FAILURE DESCRIPTION: 15 CFCU FLOW INDICATION FAILED TO ZERO -

TROUBLESHOOT REFUELING WATER STORAGE TANK LEVEL INDICATION FAILURE DESCRIPTION: RWST INDICATED LEVEL IS ERRATIC -

TROUBLESHOOT 15 SERVICE WATER PUMP FAILURE DESCRIPTION: 15 SW PUMP LOOSE WHEEL -

FLOW IS ERRATIC AND AMPS ARE SWINGING -

PULL PUMP 13 CHARGING PUMP FAILURE DESCRIPTION: 13 CHARGING PUMP CYLINDER PACKING LEAKS -

REPACK CYLINDER PACKING

10CFR50.59 EVALUATIONS MONTH: -

JULY 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-272 SALEM 1 AUGUST 10, 1991 J. FEST (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 lEA-01017 Pkg. 1 B.

Procedures AIT&QP

SUMMARY

"Installation and Operation of a Portable Liquid Radwaste System" -

Package 1 proposes a modification to install and operate a portable liquid radwaste system to assist in the processing of liquid radwaste.

The portable system will be located in the Auxiliary Building truck bay on the 103' elevation.

The installation of the portable system in the Auxiliary Building and the continued use of approved station procedures for sampling, analyzing and releasing of the liquid radwaste assures that the guidelines and concentrations given in 10CFR100 and 10CFR20, Appendix B, Table II, Column 2 continue to be met.

The installation of the system within the Auxiliary Building provides containment and therefore Nureg 0800, section 15.7.3 is inapplicable.

{SORC 91-039)

"Artificial Island Security Training &

Qualification Plan" -

Rev. 2 of this procedure revises the procedure primarily to comply with changes to New Jersey State Law N.J.S.A 2C:39-6J, regarding firearms qualification and requalification for law enforcement and private security personnel.

The firearms program described in the Plan also conforms to the New Jersey Division of Criminal Justice Police Training Commission Basic Firearm Course for Security Guards at Nuclear Power Plants.

Also a change has been made relative to referrals of security force members to the employee assistance program* {EAP).

The intent of the change is to ensure that anyone displaying behaviors indicative of potential performance or reliability problems would be relieved of duty and not permitted to return until documented successful completion of the appropriate EAP activity was verified.

{SORC 91-042)

10CFR50.59 EVALUATIONS MONTH: -

JULY 1991 (Cont'd)

ITEM C.

Safety Evaluations S-l-RCS-MSE-0791-0 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-272 SALEM 1 AUGUST 10, 1991 J. FEST (609)339-2904 "Steam G~nerator Explosive Plug Issues" -

Rev. 0 of this Safety Evaluation (S/E) is being carried out to document review of explosive plug leakage, over pressurization of Steam Generator (S/G) tubes, fishmouth and bulging, S/G primary to secondary leakage during future fuel cycles due to the Salem decision to return to power with explosive plugs in 11 S/G (20 plugs), 13 S/G (17 plugs) and 14 S/G (15 plugs).

According to this evaluation, explosive plug leakage, check valve effect during heat up/cool down, bulging of an affected tube due to over pressurization, fishmouth and resultant primary to secondary leakage is considered to be an operational event.

The leakage, based on Salem and industry experience is expected to be less than 5 gpd.

The consequences of this leakage are minimal and require effort to monitor.

The negative aspect of leakage from the this known and acceptable phenomenon is the masking of an unknown or unacceptable phenomenon such as a rapidly propagating crack of circumferential nature.

However, this type of event is analyzed in the Salem UFSAR with appropriately low probability.

Returning the explosively plugged S/Gs to service is not increasing the consequences of a S/G tube rupture as analyzed in the Salem UFSAR.

(SORC 91-041)

D.

Deficiency Reports (DRs) Use-As-Is Dispositions DR :ft: SMT 91-247 "11 Steam Generator (S/G)" - During the installation of the 11 S/G nozzle dam, 1 pint of hydraulic fluid was spilled in the S/G bowl.

The fluid was cleaned up manually using terri towels.

It is estimated that no more than 1 oz.

remained in the bowl as a minor oil film.

This safety evaluation has been prepared to document there is no USQ in the remaining hydraulic oil mixing with the Reactor Coolant System (RCS).

This incident challenges RCS chemistry but as is documented here, this incident did not result in RCS chemistry being out of specification during shutdown.

10CFR50.59 EVALUATIONS MONTH: -

JULY 1991 (Cont'd)

ITEM DR # SMD 91-274 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-272 SALEM 1 AUGUST 10, 1991 J. FEST (609)339-2904 RCS chemistry will be monitored during plant startup and compliance with Technical Specifications is assured.

There is no increase in the probability of accidents analyzed in the UFSAR.

( SORC 91-041)

"Unit 1 Containment Liner" -

Attachment clips on the Unit 1 Containment liner were found to be rusting.

These clips are located in random areas above the spring line.

The attachment clips exist on Unit 1 only and were installed during construction for rigging.

These clips do not appear to have been painted at that time.

Since the UFSAR implies that all internal surfaces were to be painted, this DR and unpainted clips are considered to be a deviation from the UFSAR.

Although the clips with rust may be an appearance problem, the Containment integrity is not being impacted as evidenced by successful Type-A containment leak rate testing during the ninth refueling outage.

Clips with rust have no other impact on the probability or consequences of a malfunction of equipment important to safety.

(SORC 91-052)

SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 1 JULY 1991 The Unit began the period operating at full power and continued to operate at essentially full power throughout the remainder of the period.

REFUELING INFORMATION MONTH: -

JULY 1991 MONTH JULY 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

APRIL 18, 1992 50-272 SALEM 1 AUGUST 10, 1991 J. FEST (609)339-2904

3.

Scheduled date for restart following refueling:

JUNE 12, 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?:

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 588

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:

September 2001 8-1-7.R4

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