ML18102B584
| ML18102B584 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/31/1997 |
| From: | Garchow D, Knieriem R Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N970620, NUDOCS 9709230178 | |
| Download: ML18102B584 (11) | |
Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 15 1997 LR-N970620 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 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 General Man ger -
Salem Operations RBK/tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046
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Refueling Information Docket No. 50-272 Month: August, 1997 Unit Name: Salem 1
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: To Be Determined 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: No: X If no, when is it scheduled? To be Determined
- 4. Scheduled date (s) for submitting proposed licensing action: To be Determined
- 5. Important licensing considerations associated with refueling:
- 6. Number of Fuel Assemblies:
- a. Incore: 0
- b. In Spent Fuel Storage: 953
- 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: April 2012
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 AUGUST 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and 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.
DOCKET NO.: 50-272 UNIT: Salem l DATE: 09/15/97 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT l 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 lEC-3310, Pkg. 1, Emergency Diesel Generator Low Lube Oil Temperature Setpoint Change. This design change revises the Emergency Diesel Generator (EDG) lube oil low temperature setpoint to 100°F. Raising the low lube oil temperature from 80°F to 100°F is conservative and will more promptly alert the operators of a failed heater.
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.
lEC-3438, Pkg. 1, "A Emergency Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modifications. This design change installs two voltage sensing relays and an auxiliary relay to monitor the output voltage of the "A" Emergency Diesel Generator (EDG) .
Contacts from the auxiliary relay replace the voltage permissive contact in the closing circuit of the main circuit breaker for the EDG. The setpoints of the voltage sensing relays are at a higher voltage than the previous relays and will prohibit the EDG main circuit breaker from closing when the EDG output is less than the required voltage. This design change also installs indicating lights on the generator control panel to identify when the voltage and speed permissives are satisfied.
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.
lEC-3401, Pkg. 1, Emergency Diesel Generator Starting Air &
Turbo Boost System Upgrade. This design change upgrades the Starting Air and Turbo Boost system by the installation of stainless steel piping and components for corrosion resistance. It also provides for replacement of obsolete components to upgrade the system to reflect current industry practice.
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.
lEC-3529, Pkg. 1, Modify Emergency Diesel Generators (EDG)
To Increase Vibration Tolerance. This design change modifies EDG design by modifying EDG engine, generator, and auxiliary components to increase the EDG's tolerance to vibration. These changes include: (1) Installation of elastomeric flexhose on components with relative motion mounted on the engine, engine skid, and engine foundation, piping, or tubing, (2) Braces components with a configuration with a natural frequency near that of the engine dominant frequency of vibration, (3) Strengthens certain components to withstand vibration, (4) Relocates and rigidly mounts cantilever-mounted valves on the engine and auxiliary components, (5) Removes existing EDG engine and generator mounted vibration switches.
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.
lEC-3525, Pkg. 1, Relief Valve 1CV141 Replacement. This design change replaces and relocates the No. 13 Positive Displacement Charging pump (PDP) discharge relief valve (1CV141) with a bellows style relief valve which is better suited for this application.
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.
lEE-0333, Pkg. 1, Replace Service Water Pump Strainer Backwash Valve 11SW24. This design change replaces the existing Service Water Pump Strainer Backwash Diaphragm Valve (11SW24) . The valve will be replaced with a ball valve which has a longer service life between preventive maintenance and is better suited for the frequent cycling of backwash service. The existing fast actuating air operator is being replaced with a Bettis piston type actuator to slow the closure time of the valve to mitigate existing water hammer in this portion of the system.
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.
lEE-0349, Pkg. 1, Replace Circulating Pump Bearing Lube Relief Valve. This design change replaces the existing Circulating Pump Bearing Lube Relief valve with a model of increased size and increased set pressure. The size of the relief valve will be increased to accommodate a higher calculated flow rate and the set pressure will be increased to ensure that the valve does not lift due to pressure surges and flow induced vibrations which occur when the screen wash pumps are used to supply Circulating pump bearing lubrication water.
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 TMR 97-023, 4KV "A" Vital Bus Undervoltage Relay Tie-Ins.
This temporary modification installs steel plates, terminal blocks, circuit breakers, fuse holders, and wiring to eliminate the need for additional bus outages. The additional bus outages would be required to support the installation of the Service Water Accumulator Tank Discharge Valve modification.
This temporary modification does not negatively impact any accident response. This temporary modification does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this temporary modification does not involve an Unreviewed Safety Question.
Procedures Summary of Safety Evaluations Sl.OP-SO.ABV-OOOl(Q), Rev. 5, Auxiliary Building Ventilation (ABV) System Operation. This new maintenance procedure was written to allow the Unit 1 ABV system to be operated outside the normal arrangement to allow for equipment maintenance which cannot be performed effectively with the normal system operating (one supply and two exhaust fans in service). The building pressure will remain negative with respect to the atmosphere with no supply fan and only one exhaust fan operational.
Since any one of the three exhaust fans will be in service during this duration, the Auxiliary Building will continue to be maintained at a negative pressure and any source of contamination will be filtered through the ABV filtration units prior to being released offsite. Since the plant is defueled, the potential for increased contamination and the migration of any contamination will be minimized.
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 August, 1997.
Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during August, 1997.
Other Summary of Safety Evaluation There were no changes in this category implemented during August, 1997.
I I
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 9/11/ 97 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 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 0.0 0.0 104380.5 6 Reactor reserve shutdown hours 0.0 0.0 0. 0 7 Hours generator on line 0 0 100338.3 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 0 0 31806229 10 Gross electrical energy generated (MWH) 0 0 10530100 11 Net electrical energy generated (MWH) -3655 -22468 10015226 12 Unit Service Factor 0.0% 0.0% 52.1%
13 Unit Availability Factor 0.0% 0.0% 52.1%
14 Unit Capacity Factor (MDC) 0.0% 0.0% 47.0%
15 Unit Capacity Factor (DER) 0.0% 0.0% 46.6%
16 Unit Forced Outage Rate 100.0% 100.0% 37.8%
17 Shutdowns scheduled over next 6 months (type, date, duration) :
18 If shutdown at end of report period, estimated date of Startup: Under Review
- DOCKET NO.:
UNIT:
50-272 Salem 1 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) 3859 8/1 F 744 F, c 4 Steam
- Generator 8/31 Replacement (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.: 50-272 UNIT: Salem 1 DATE : 9 I 11 I 9 7 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 0 15 0 31 0 16 0