ML18096A270

Monthly Operating Rept for Aug 1991 for Salem Unit 2.W/ 910913 Ltr

ML18096A270
Person / Time
Site:	Salem
Issue date:	08/31/1991
From:	Fest J, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9109200270
Download: ML18096A270 (10)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station September 13, 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 August 1991 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions, Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information 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__ . _ _ . __ . * * * -----..

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~ERAGE DAILY UNIT POWER L~

• Docket No. : 50-311 Unit Name: Salem #2 Date: 9/10/91 Completed by: Mark Shedlock Telephone: 339-2122 Month August 1991 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET} (MWe-NET}

1 1069 17 1077 2 1072 18 1074 3 1060 19 1076 4 1042 20 1074

• 5 1067 21 1075 6 1071 22 1046 7 1069 23 1055.

8 1060 i4 1046 9 1057 25 1056

• 10 1091 26 1057 11 1051 27 1035 12 .1031 28 1068 13 872 29 1046 14 1060 30 1078

• 15 1030. 31 1045 16 1073 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-311 Date: 9/10/91 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period August 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 NA

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 744 5831 86640

12. No. of Hrs. Rx. was Critical 744 5591. 6 56947.8

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 744 5567.3 55277.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2529273.6 18737460.0 124730929.0

17. Gross Elec. Energy Generated (MWH) 830979 6227523 57959450

18. Net Elec. Energy Gen. (MWH) 797485 5972865 55180676

19. Unit Service Factor 100 95.5 63.8

20. Unit Availability Factor 100 95.5 63.8

21. Unit Capacity Factor (using MDC Net) 96.9 92.6 57.6

22. Unit Capacity Factor (using DER Net) 96.1 91. 9 57.1

23. Unit Forced Outage Rate 0 0 22.4

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

Refueling outage scheduled to start 1-4-92 and last 75 days.

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

NA 8-1-7.R2

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH AUGUST 1991 DOCKET NO. 50-311 UNIT 'NAME Salem #2 DATE 9/10/91 COMPLETED BY Mark Shedlock TELEPHONE 339-2122 .

METHOD OF SHUTTING LICENSE DURATION DOYN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0062 8/12/91 F 5.0 B 5 ------ CH INSTRU #22 STEAM GEN. FEED PUMP 0058 8/13/91 F .9 B 5 ------ CH FILTER #22 STEAM GEN. FEED PUMP 1 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-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG~0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-other H-Other (Explain)

~I*s~F~~y RELATED MAINTENANCE MONTH: - AUGUST 1991 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 I DATE: SEPTEMBER 10, 1991 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 910618131 2 RADIATION MONITOR 2R42C FAILURE DESCRIPTION: NO SCAN ON MONITOR - INVESTIGATE 910619073 2 SW SPOOL 2-SW-2253 FAILURE DESCRIPTION: SPOOL 2-SW-2253 HAS A THROUGH WALL LEAK - REPLACE SPOOL 910724109 2 NUCLEAR INSTRUMENT .2N41 FAILURE DESCRIPTION: INSTALL NEW NI DETECTOR CURRENT PER FLUX MAP 910724112 2 NUCLEAR INSTRUMENT 2N42 FAILURE DESCRIPTION: INSTALL NEW NI DETECTOR CURRENT PER FLUX MAP 910724114 2 NUCLEAR INSTRUMENT 2N43 FAILURE DESCRIPTION: INSTALL NEW NI DETECTOR CURRENT PER FLUX MAP 910724116 2 NUCLEAR INSTRUMENT 2N44 FAILURE DESCRIPTION: INSTALL NEW NI DETECTOR CURRENT PER FLUX MAP 910731143 2 RADIATION MONITOR 2R5 FAILURE DESCRIPTION: RADIATION MONITOR 2R5 COMM.

FAILURE - INVESTIGATE 910814073 2 21 CHARGING PUMP RM COOLER FAILURE DESCRIPTION: ROOM COOLER HAS TUBE LEAK -

INVESTIGATE 910820202 2 SERVICE WATER VALVE 21SW8 FAILURE DESCRIPTION: VALVE 21SW8 GOING CLOSE FOR NO REASON - TROUBLESHOOT 910820206 2 SPOOL 1-MP-P-4113 FAILURE DESCRIPTION: LEAK IN PIPE WELD /SPL 1-MP-P-4113 - REPLACE

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: - AUGUST 1991 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1991 COMPLETED BY: J. FEST TELEPHONE: (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 and concurs with these evaluations.

ITEM

SUMMARY

A. Design Change Packages (DCP)

DCP # 2EC-3075 Pkg. 1 "Removal of BIT Tank Relief Valve 2SJ10" - This DCP removes the BIT tank relief valve 2SJ10.

some of the downstream piping and hangers will also be removed due to stress concerns. A blind flange will be installed on the upstream side of the valve and a pipe cap will be installed on the downstream side to blank off the lines.

Also, valve 2SJ77, which was capped off during the BIT removal, will be removed. Westinghouse has performed a 50.59 safety evaluation to address the removal of the BIT *relief valve, (Westinghouse transmittal SECL-91-51 Rev. 1).

Westinghouse concluded that removal of the relief valve will not constitute a USQ.

(SORC 91-060)

DCP # 2EC-3055 Pkg. 1 "Unit 2 Control Room HVAC Modifications" - This change to the facility is a rebalance of the Control Area Air conditioning System (CAAS} to provide for more cooling in the Data Logging Room by taking air from the_Electrical Equipment Room. The existing transfer grilles are removed from the wall between the Data Logging Room and the Electrical Equipment Room to ensure the modified air flow patterns do not increase the pressure in the Data Logging Room. No new accident scenarios are presented by this change. The rebalancing of the CAAS will have no affect on Control Room heating, cooling, or habitability requirements. None of the accident scenarios in the Salem UFSAR Section 15 will be impacted. (SORC 91-075)

DCP # 2EC-3059 Pkg. 1 "Control Room Modifications Phase III" - This design change was issued to implement the corrective actions required to resolve six of the Human Engineering Discrepancies (HED) identified in the Salem Unit 2 Control Room and various additional changes.

10CFR50.?9 EVALUATIONS DOCKET NO: 50-311 MONTH: - AUGUST 1991 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1991 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

The HEDs were generated during the Detailed Control Room Design Review conducted in accordance with NRC NUREG 0700 requirements.

The following HEDs are addressed: 472, 476, 478, 482, 484 and 751. The equipment which is added to the control console, control panel, recorder panel, and hot shutdown panel in this modification meets the same design and material standards as the rest of the existing equipment on the console and panels. This modification will not cause systems to be operated outside or testing limits, and the additional control loads on the electrical system imposed by this modification are judged to be negligible.

(SORC 91-081)

DCP # 2SC-2015 Pkg. 1 "Replacement and Testing of Gamma-Metrics Neutron Flux Detectors & In-Containment Cable Assemblies" - This design change provides for the two Gamma-Metrics detector assemblies and in-containment cable assemblies, which are part of the neutron flux monitoring system, to be replaced. No increase of probability of a malfunction of equipment important to safety will occur as a result of this modification.

This is an independent back-up system which is not required for safety. No increased consequences of a malfunction will exist since no malfunction of equipment important to safety will be generated. (SORC 91-081)

B. Procedures and Revisions (Proc)

1. S2.RE-RA.ZZ-0010(Q) Guidelines for Mis~ligned/Dropped Control Rod Recovery" Rev. 0 - This procedure provides guidelines for the operation of the reactor during the recovery of a dropped or misaligned control rod. The procedure was written to satisfy the requi~ements of INFO SOER 84-02R01.

This procedure will not create the possibility of an accident of a different type than any previously analyzed in the SAR. The UFSAR and the Technical Specifications allow for the recovery of a misaligned or dropped control rod.

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: - AUGUST 1991 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1991 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

The guidelines in the procedure were established to ensure that certain acceptance criteria are met during and after the recovery. These criteria are within the UFSAR and Technical Specifications bounds. (SORC 91-075)

c. Technical Specification Interpretations (TSI)

TSI # LCO 3.3.2.1 "Table 3.3 Semi-Automatic Swapover" Rev. 0 -

TSI LCO 3.3.2.1 Table 3.3-3 Item 9 clarifies Amendment 69. In order to achieve an uninterrupted flow of ECCS water to the core, certain valves need to be placed in their armed condition prior to entering Mode 3. These valves are 21SJ113, 22SJ113, 21CC16, and 22CC16. The SJ44 and RH4 valves will not be armed until called for in Procedure EOP-LOCA-3, Transfer to Cold Leg Recirculation. The Semi-automatic Swapover System performs the same function as described in the SAR for swapping over to the recirculation phase from the injection phase. All equipment comprising the system is tested to verify operability. No malfunctions other than those already evaluated in the SAR are created by this interpretation.

(SORC 91-059)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 AUGUST 1991 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued operating at essentially full power until August 12, 1991, when power was briefly reduced to inspect low suction pressure trip devices. The Unit returned to 100% power on August 13, 1991, and continued to operate at full power throughout the remainder of the period.

r----

1 REFUELIN,G INFORMATION DOCKET NO: 50-311 MONTH: - AUGUST 1991 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1991 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH AUGUST 1991

1. Refueling information has changed from last month:

YES X NO

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 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 340

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