ML18102B583

Monthly Operating Rept for Aug 1997 for Salem,Unit 2. W/970915 Ltr

ML18102B583
Person / Time
Site:	Salem
Issue date:	08/31/1997
From:	Garchow D, Hnieriem R, Phillips R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970621, NUDOCS 9709230086
Download: ML18102B583 (11)

Text

e .e OPS~G P~blic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 15 1997 LR-N970621 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 August, 1997, is attached.

I Sincerely (JJ;p David F. G rchow General Manager -

Salem Operations RBK/tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

- - -- -~ - ---

9709230086 970831 PDR ADOCK 05000311 R PDR 1111111111111111111111111111111111111111

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The power is in your hands.

95-2168 REV. 6/94 L

Refuelipg Information Docket No. 50-311 Month: August, 1997 Unit Name: Salem 2

Contact:

R. B. Knieriem Telephone: 609-339-1782 Month: August, 1997

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

2. Scheduled date for next refueling: January 6, 1999 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 MpNTHLY OPERATING

SUMMARY

- UNIT 2 August 1997 SALEM UNIT 2 Salem Unit 2 was synchronized to the electric power grid at 0330 on August 30. The unit was operating at approximately 19%

reactor power at the time of synchronization. Operators successfully conducted integrated testing and continued to increase power. At the end of the month, reactor power was at approximately 33%.

Additional testing will be conducted, with a final hold at 90%

power for NRC review. Following NRC concurrence, the reactor power will be increased to 100%.

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 09/15/97 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH AUGUST 1997 The following items completed during August 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 2EC-3407, Pkg. 1, Steam Traps Replacement Project. This design change will replace steam traps associated with the Main Steam system with a more reliable design to reduce the dumping of excessive quantities of steam directly to the condenser when steam traps fail and are bypassed. It will also reduce the potential for water hammer.

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-3334, Pkg. 1, Salem Rod Cluster Control Assembly (RCCA)

Replacement. This design change replaces RCCA with a design which incorporates the following features: (1) Single piece

absorber rod with reduced tip diameter to allow for increased swelling of the absorber rod within the clad. (2)

Different composition of stainless steel for cladding and end plugs to improve wear resistant treatment and weldability. (3) Ion-nitriding surface treatment to improve wear resistance.

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 A Fully Integral Design This design change modifies the Circulating Water system controls. It involves the removal and replacement of the existing Low Pressure Turbine Rotors with new Mono-block design rotors. The design incorporates the latest turbine design technology that provides improved efficiency with improved exhaust flow guides to allow operation at condenser back pressures up to 8 in. HG absolute.

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-3395, Pkg. 1, Moisture Separator Reheater (MSR) Drain and Vent System Modifications. This design change involves piping replacement and rerouting changes for the MSR drain and vent system to reduce excessive vibration.

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-3402, Pkg. 1, Main Turbine Lube Oil Separator Replacement. This modification replaces the existing centrifugal type separator with a coalescing filter type separator to simplify drive train maintenance and to reduce oil leaks caused by drive train vibration.

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-3449, Pkg. 1, Steam Generator Tube Leak Detection Main Steam Line N-16 Monitors. This design change installs a Main Steam Line N-16 monitoring system. The system will utilize detectors mounted adjacent to the main steam lines to monitor for the presence of N-16 in the steam that would indicate a primary to secondary leak.

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-3471, Pkg. 1 Reconfiguration of Main Generator Water Cooling System Runback Logic. This modification will upgrade the Main Generator non-safety related water cooling system runback logic from one (1) out of one (1) to a two (2) out of three (3) logic to minimize unnecessary generator trips.

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.

2EE-0119, Pkg. 1 Steam Generator Feed Pump Vibration Monitoring Update. This modification replaces the obsolete vibration monitoring equipment associated with the Steam Generator Feed pump with new equipment that has additional monitoring and analytical capabilities. It also replaces the existing L&N two pen chart recorders with new Yokogawa twelve point recorders.

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.

2EE-0276, Pkg. 1 Steam Generator Blowdown Sample Line Pressure Regulator Replacement. This modification replaces the existing pressure regulators for the steam generator

blowdown sample lines to the 2R19A-D radiation monitors.

It will incorporate design improvements which improve the overall maintainability of the regulators.

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.

2EE-0317, Pkg. 1 Modify Controls to 2CH168 Valve. This modification eliminates a single failure vulnerability concern related to the 2CH168 valve (Temperature Control Isolation Valve in the Emergency Air Conditioning System)

Failure of this valve to open could lead parts of the combined control room envelope to exceed temperature limits imposed by section 3.11 of the UFSAR. This modification will be accomplished by permanently removing the pneumatic control to the valve, permanently placing the valve in the full open 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.

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

Procedures Summary of Safety Evaluations There were no changes in this category implemented during August, 1997.

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

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

I I

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

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 9/11/97 COMPLETED BY: R. Phillips TELEPHONE: ( 609) 339-27 35 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period August 1997 Hours in Report 744 Period 2 Currently Authorized Power Level (MWt) 3411 Max Dependable Capacity (MWe-Net) 1106 Design Electrical Rating (MWe-Net) 1115 3 Power level to which restricted (if any) (MWe Net) None 4 Reason For Restriction (if any)

This Month Yr To Cumulati Date 5 No. of hours reactor was critical 283 283 78366.6 6 Reactor reserve shutdown hours 0.0 0.0 0.0 7 Hours generator on line 45 45 75274.5 8 Unit reserve shutdown hours 0. 0 0. 0 0.0 9 Gross thermal energy generated (MWH) 75146 75146 18785615 10 Gross electrical energy generated (MWH) 8230 8230 78656828 11 Net electrical energy generated (MWH) -17592 -91119 74611515 12 Unit Service Factor 6. 0% 0.8% 49.9%

13 Unit Availability Factor 6.0% 0.8% 49.9%

14 Unit Capacity Factor (MDC) 0.0% 0.0% 44.7%

15 Unit Capacity Factor (DER) 0.0% 0.0% 44.3%

16 Unit Forced Outage Rate 93.9% 99.2% 34.1%

17 Shutdowns scheduled over next 6 months (type, date, duration) : None 18 If shutdown at end of report period, estimated date of Startup:

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 9/ 11/ 97 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH AUGUST 1997 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F=FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S=SCHEDULED (HOURS) ( 1) POWER ACTION/COMMENT (2) 4092 8/1 F 744 F, c 4 Refueling

- Outage 8/31 Extension (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip C - Refueling 3 - Automatic Trip/Scram D - Regulatory Restriction 4 - Continuation E - Operator Training/License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 9/11/ 97 COMPLETED BY: R. Phillips TELEPHONE: ( 609) 339-2735 AVERAGE DAILY UNIT POWER LEVEL MONTH AUGUST 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 73 15 0 31 191 16 Q