ML18102B308
| ML18102B308 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1997 |
| From: | Garchow D, Ritzman R Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9705220290 | |
| Download: ML18102B308 (9) | |
Text
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- PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAY 15 1997 LR-N970311 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 April, 1997, is attached.
RAR:tcp Enclosures c
Mr. H. J. Miller avid F. Ga General Man ger -
Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9705220290 970430 PDR ADOCK 05000311 R
.. 0 0 c::,-
22,,n.)0 The power is in your hands.
I/ t I
95-2168 REV. 6/94
DOCKET NO.:
UNIT:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH APRIL 1997 50-311 Salem 2 05/15/97 R. Ritzman (609) 339-1445 The following items completed during April 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... pl.ant. 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-3329, Pkg. 1, Condenser Hotwell Level Control Modifications.
This design change removes the condenser hotwell level instrumentation and installs new instrumentation.
The instrumentation has experienced the need for increased maintenance, the modification is intended to result in a more reliable condenser hotwell monitoring and control system.
The operation of the condenser level indication and alarm system will not change as a result of this design change. This replacement does not change the function of the affected systems.
The affected systems will function in accordance with the original design and licensing basis of the plant.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
2EC-3332, Pkg. 2, Emergency Lighting Inverter Logic Card Modification.
This design change modifies the emergency lighting inverters.
Inverter lighting electronic logic control cards are being replaced and/or added to each emergency lighting inverter to change the normal and back-up power source selections.
This modification removes the bulk of the emergency lighting inverter load from the battery chargers during a battery system recharge.
The emergency lighting inverters are non safety-related and Seismic category II/I.
The emergency lighting system is a non safety-related system.
The interfaces to plant systems, structures, and analyses are not adversely impacted by this modification.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
2EC-3370, Pkg. 1, Replacement of the Main Steam Coil Drain Tank Dump Valves.
The Main Steam Coil Drain Tank High Level Dump Valves draw suction from the bottom of the Main Stearn Coil Drain Tanks.
This design change replaces the dump valve~ with improved dump valves. and installs new "y" st;ralners before each dump valve.
This design change also replaces piping in the vicinity of the dump valves. The des1gn change does not reduce the margin of safety and decreases the potential for a pipe leak.
The design change is not safety-related, does not interact with safety-related equipment, and is not important to safety.
Malfunction of the dump valves, strainers, isolation valves, or piping would not directly affect the operation of any safety-related systems.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
2EC-3449, Pkg. 1, Steam Generator Tube Leak Detection Main Steam Line Nitrogen 16 Monitors.
This design change installs a steam generator Nitrogen 16 monitoring system to provide additional information to assess and characterize Steam Generator tube leaks.
The system monitors for the presence of Nitrogen 16 in the steam as a result of carry-over from a primary to secondary leak.
These monitors are non-safety related and seismic II/I.
The monitors provide information to operations, but do not provide any automatic control functions.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
Temporary Modifications Summary of Safety Evaluations TMR 96-026, Chilled Water Supply to Containment Fan Cooler Units for Containment Cooling.
This temporary modification provides chilled water as an independent closed-loop to two Containment Fan Cooler Units (CFCUs).
The fan cooler units are used to lower the containment temperature for personnel comfort.
The implementation of this temporary modification does not affect the operating characteristics or performance objectives of the Service Water System components or circuits.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
Procedures Summary of :safety,Evaluations There were no changes in this category implemented during April, 1997.
UFSAR Change Notices Summary.of.Safety Evaluations There were no changes in this category implemented during April, 1997.
Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during April, 1997.
Other Summary of Safety Evaluation There were no changes in this category implemented during April, 1997.
OPERATING DATA REPORT
- Docket No:
50-311 Date:
05/10/97 Completed by:
Robert Phillips Telephone:
339-2735 Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period April 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.~~~~~--=N~A=-~~~~~~~~~~~~~~~~~~~
- 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 719 2879 140606
- 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
- 17. Gross Elec. Energy Generated (MWH) 0 0
78648598
- 18. Net Elec. Energy Gen.
(MWH)
-7064
-30231 78618637
- 19. Unit Service Factor 0
0 53.5
- 20. Unit Availability Factor 0
0 53.5
- 21. Unit Capacity Factor (using MDC Net) 0 0
48.0
- 22. Unit Capacity Factor (using DER Net) 0 0
47.6
- 23. Unit Forced Outage Rate 100 100 32.4
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling extension.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Third quarter of 1997.
8-1-7.R2
.ERAGE DAILY UNIT POWER L~
Docket No.:
50-311 Unit Name:
Salem #2 Date:
05/10/97 Completed by:
Robert Phillips Telephone:
339-2735 Month April 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
P. 8.1-7 Rl
NO.
DATE 4092 4-1-97 F
1 2
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH April 1997 DURATION TYPE 1
(HOURS)
REASON 2 744 F,C Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR 4
E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
LICENSE EVENT SYSTEM REPORT #
CODE4 2422 3
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE:
50*311 Sal ent*#2 05*10*97 Robert Phillips 609-339-2735 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 5 TO PREVENT RECURRENCE Refueling Outage Extension Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source
'°Refueling Information Month:
April, 1997 Month:
April, 1997 Docket No.
Unit Name:
Contact:
Telephone:
50-311 Salem 2 D. Tisdel 609-339-1538
- 1.
Refueling information has changed from last month: Yes:
No: X
- 2.
Scheduled date for next refueling:
Currently in outage.
- 3.
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:
- b.
In Spent Fuel Storage:
- 7.
Present Licensed spent fuel storage capacity:
Future spent fuel storage capacity:
193 584 1632 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 MONTHLY OPERATING
SUMMARY
- UNIT 2 APRIL 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.