ML18102B453

Monthly Operating Rept for June 1997 for Salem Unit 2. W/970715 Ltr

ML18102B453
Person / Time
Site:	Salem
Issue date:	06/30/1997
From:	Garchow D, Ritzman R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970443, NUDOCS 9707220154
Download: ML18102B453 (11)

Text

e 0 ,ps~G Pu?lic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 15 1997 LR-N970443 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for June, 1997, is attached.

W5F David F. G rchow General Manager -

Salem Operations I

RAR:tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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The power is in your hands.

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95-2168 REV. 6/94

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 06/13/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH JUNE 1997 The following items completed during June 1997 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations S96-031, Masoneilan Air Operator Retainer Clip. This design change enhances the reliability of the Containment Fan Coil Units Service Water Inlet and Outlet Valves and the Turbine Lube Oil and Auxiliary Cooling Heat Exchangers Service Water Bypass Valve by installing a declutching pin retainer clip.

The clip provides a positive method to hold in pin in its engaged position.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

S97-018, Service Water Flow Element, Instrument Tubing/Root Valve Addition. This design change provides a reliable and effective method to measure and monitor Service Water flow to Charging Pump Lube Oil Coolers, Charging Pump Room Coolers, Safety Injection Pump Lube Oil Coolers, and a Safety Injection Pump Room Cooler.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

S97-076, Add Welded Pipe Cap to Main Steam Valves. This design change provides a passive containment boundary to the pressure test valves on the Steam Generators and the vent valves on the Main Steam lines near the Steam Generators.

The passive containment boundary consists of a safety related pipe nipple and a welded cap at the outlet of the valves.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

S97-098, Install Flow Points and Vent Opening in the Component Cooling Heat Exchanger Rooms Duct Work. This design change installs air flow test points and modifies an access door in the duct from the 21 Component Cooling Water Pump Room Cooler that supplies air to the 21 and 22

• Component Cooling Heat Exchanger Rooms. This redistribution will allow for an improved air flow.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3264, Pkg. 2, Reactor Protection System Signal Low-Low Tavg Nomenclature Change. This design change clarifies conflicting documentation regarding the Reactor Protection System Low Tavg and Low-Low Tavg signals. The name of the Tavg reactor protection signal is being changed from Low Tavg to Low-Low Tavg for standardization. The associated pushbuttons in the control room are being changed from

yellow to white to achieve consistency in recognizing and responding to alarm and control functions.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3353, Pkg. 1, Replacement of Low Pressure Turbine Rotors with Fully Integral Design. This design change removes and replaces the Low Pressure Turbine Rotors with new mono-block rotors. Each rotor replacement consists of the new rotor, inner cylinder, seals, and associated bearing cover modifications. The installation of the new rotors is expected to result in increased turbine efficiency.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3590, Pkg. 16, Integrated Testing of NRC GL 96-06 Modifications. This design change package performs the integrated acceptance testing of the modifications made to the Service Water system by other packages of 2EC-3590.

This design change package does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3612, Pkg. 1, NRC GL 96-06 Overpressurization Related Modifications. This design change adds six relief valves to limit the post-accident peak operating pressures of certain piping segments inside containment. This design change will ensure that the post-accident operating conditions for the associated containment isolation valves do not exceed their design limits.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3617, Pkg. 1, Pressure Operated Relief Valve Control Mo~ifications. This design change modifies the control actuation circuitry for the Pressure Operated Relief Valves.

The modification provides separation/isolation of safety related and non-safety related functions to prevent a single failure from affecting both Pressure Operated Relief Valves.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3623, Pkg. 1, Flux Mapping Cabinet Power Change. This design change replaces the power feed to a demultiplexor and two modems in the Flux Mapping Cabinet. This will allow the use of the Safety Parameters Display System as a primary Core Exit Thermocouple display for use during the performance of Emergency Operating Procedures.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3625, Pkg. 1, Switchgear and Penetration Area Ventilation System Reliability Enhancement Modification.

This design change enhances the Switchgear and Penetration Area Ventilation System reliability and ability to maintain temperatures within its design limits. This is accomplished by modifying the supply fans start logic, the switchgear exhaust/return fans control circuits, the modulating damper controls, the penetration area exhaust fan control circuits, and the isolation damper controls.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during June, 1997.

Procedures Summary of Safety Evaluations S2.0P-SO.ABV-000l(Q), Rev. 4, Auxiliary Building Ventilation System Operation. This procedure revision disables the automatic start feature of one of the two 100% supply air fans under normal operating conditions and imposes additional operability requirements on both supply and exhaust air fans to assure building temperatures can be maintained within design limits under certain postulated single failures. These procedural controls were imposed until the fan logic is modified via a design change.

This procedure revision does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.

Therefore, this procedure revision does not involve an Unreviewed Safety Question.

TS2.SE-SU.ABV-0002(Q), Rev. 0, Auxiliary Building Ventilation Test. This new temporary procedure was written to measure the actual airflow developed by either one or two of the Auxiliary Building Ventilation exhaust fans with the supply fan shut down. The procedure includes temperature monitoring and test termination instructions. The ventilation system retains its ability to perform its safety function during this test.

This procedure revision does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.

Therefore, this procedure revision does not involve an Unreviewed Safety Question.

UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during June, 1997.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during June, 1997.

Other Summary of Safety Evaluation There were no changes in this category implemented during June, 1997.

e OPERATING DATA REPORT e Docket No: 50-311.

Date: 07/10/97 completed by: Robert Phillips ~ Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period June 1997

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) NIA

10. Reasons for Restrictions, if any NA This Month Year to Date cumulative

11. Hours in Reporting Period 720 4343 144949

12. No. of Hrs. Rx. was Critical 0 0 78083.6

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 0 75229.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 187781005.0

17. Gross Elec. Energy Generated (MWH) 0 0 78648598

-*18. Net Elec. Energy Gen. (MWH) -13045 -50940 74629659

19. Unit Service Factor 0 0 51. 9

20. Unit Availability Factor 0 0 51. 9

21. Unit capacity Factor (using MDC Net) 0 0 46.5

22. Unit Capacity Factor (using DER Net) 0 0 46.2

23. Unit Forced Outage Rate 100 100 33.3

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

Forced outage extension.

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

3rd quarter, 1997.

8-1-7.R2

~RAGE DAILY UNIT POWER LE~

Docket No.: 50-311 Unit Name: Salem #2 Date: 07/10/97 completed by: Robert Phillips (}J,p Telephone: 339-2735 Month June 1997 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 16 0 P. 8.1-7 R1

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH June 1997 DOCKET NO. 5D-311 UNIT NAME Salem #2 DATE 07-10-97 COMPLETED BY Robert Phillips TELEPHONE 609-339-2735 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 4092 6-1-97 F 744 F,C 4 ----------- 2422 Refueling Outage Extension 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-Refueling 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) 9-0ther H-Other (Explain)

Refueling Information Docket No. 50-311 Month: June, 1997 Unit Name: Salem 2

Contact:

D. Tisdel Telephone: 609-339-1538 Month: June, 1997

1. Refueling information has changed from last month: Yes: No: X

2. Scheduled date for next refueling: Currently in outage.

Scheduled date for restart following refueling: To Be Determined

3. a. Will Technical Specification changes or other license amendments be required?

Yes: X No: Not Determined to Date:

b. Has the reload fuel design been reviewed by the Station Operating Review Committee?

Yes: X (for upcoming cycle) No: If no, when is it scheduled?

4. Scheduled date (s) for submitting proposed licensing action: N/A -

previously submitted

5. Important licensing considerations associated with refueling:

6. Number of Fuel Assemblies:

a. Incore: 193

b. In Spent Fuel Storage: 584

7. Present Licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632

8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: October, 2016

SALEM GENERATING STATION MQNTHLY OPERATING

SUMMARY

- UNIT 2 JUNE 1997 SALEM UNIT 2 The unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:

• Appropriately address long standing equipment reliability and operability issues.

• After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.

• After the restart review, meet with the NRC and communicate the results of that review.