LR-N970382, Monthly Operating Rept for May 1997 for Salem Unit 2
| ML18102B401 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1997 |
| From: | Garchow D, Ritzman R Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N970382, NUDOCS 9706250085 | |
| Download: ML18102B401 (10) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit
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~-131997 LR-N970382 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 May, 1997, is attached.
RAR:tcp Enclosures*
C Mr. H. J. Miller Sincerely yours,
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General Manager -
Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 The power is in your hands.
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I 95-2168 REV. 6/94
DOCKET NO.:
UNIT:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 Salem 2 06/13/97 R. Ritzman (609) 339-1445
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH MAY 1997 The following items completed during May 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 S97-063, Removal of the 21 Turbine Auxiliary Cooling Heat Exchanger.
This design change removes a non-safety related 20 inch valve in the Service Water outlet from the 21 Turbine Auxiliary Cooling Heat Exchanger (21ST900).
Due to its location, this valve is subjected to high turbulence and frequent maintenance.
The removal of this valve will reduce the maintenance requirements of the Service Water System.
The valve was originally installed to allow isolation and maintenance of the pipe between itself and the Turbine Auxiliary Cooling Heat Exchanger Outlet Valve (21ST64).
Due to the installation of the upgraded Service Water System piping, this capability is no longer required.
The two valves are redundant.
The safety evaluation concluded that this design change to the non-safety related, seismic Class 3 Service Water piping in the Turbine Building did not result in an Unreviewed
Safety Question.
The Turbine Building Service Water System is not safety related, nor does it support any safety related equipment.
Therefore, this design change will have no affect on the ability of the Service Water System to provide cooling water to either safety related or non-safety related equipment.
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.
S97-064, Removal of the 22 Turbine Auxiliary Cooling Heat Exchanger.
This design change removes a non-safety related 20 inch valve in the Service Water outlet from the 22 Turbine Auxiliary Cooling Heat Exchanger (22ST900).
Due to its location, this valve is subjected to high turbulence and frequent maintenance.
The removal of this valve will reduce the maintenance requirements of the Service Water System.
The valve was originally installed to allow isolation and maintenance of the pipe between itself and the Turbine Auxiliary Cooling Heat Exchanger Outlet Valve (22ST64).
Due to the installation of the upgraded Service Water System piping, this capability is no longer required.
The two valves are redundant.
The safety evaluation concluded that this design change to the* non-safety related, seismic Class 3 Service Water piping in the Turbine Building did not result in an Unreviewed Safety Question.
The Turbine Building Service Water System is not safety related, nor does it support any safety related equipment.
Therefore, this design change will have no affect on the ability of the Service Water System to provide cooling water to either safety related or non-safety related equipment.
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-3396, Pkg. 1, 10CFRSO, Appendix R Alternate Shutdown Methodology - Installation of Transfer Switches.
This design change modifies a motor control center and control panel circuits to include local switches that isolate component wiring from the Control Room, the Relay Room, and the ceiling area of the 460/230 Switchgear Room.
These modifications preclude the necessity of electrical wiring modifications and jumpers to operate equipment to achieve Hot Standby in the event of a fire in these areas.
This modification is an operational improvement.
The control circuit configuration changes will provide a permanently installed capability to achieve Hot Standby.
These modifications are enveloped by existing analysis and no 'additional failures modes are postulated. Therefore, this design change will have no affect on the ability of the Service Water System to provide cooling water to either safety related or non-safety related equipment.
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-3590, Pkg. 14, Protection for Service Water Accumulator Tanks and Associated Equipment.
This design change installs a gated security barrier in the area leading up to the Service Water Accumulator Vessels enclosure, and a tornado missile barrier on the roof of the Auxiliary Building Diesel Area.
This will provide protection for the vessels and their associated equipment.
The UFSAR describes the use of concrete barriers as the basis for protection from tornado generated missiles.
The barrier provided by this design change is constructed from structural steel; therefore, requirements for steel barriers are being added to the UFSAR.
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-3620, Pkg. 2, Add Fuses to Pressurizer Heater Circuits to Protect Penetrations.
This design change returns electrical circuit breaker settings on two pressurizer heater supply circuit breakers to their original settings and returns two feeder breakers to service.
The addition of cable limiter fuses to each heater circuit provides back-up electrical overcurrent protection for the containment penetrations, while maintaining proper electrical system coordination.
The addition of the fuses as back-up overcurrent and fault protection for the pressurizer heater containment penetrations provides redundant electrical protection.
This redundant protection improves the probability of maintaining pressurizer heater circuit containment integrity during all operating and design basis modes.
The portion of the electrical distribution system being modified is non-safety related and does not have any safety related functions or important to safety equipment.
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-3624, Pkg. 1, Steam Generator Level Sensing Line.
This de~ign change modifies the steam generator narrow and wide range instrumentation sensing lines to ensure that the ANSI allowable stress limits are not exceeded.
The stress limits were reduced by removing portions of the sensing line thermal insulation, relocating the first sensing line restraint, and rerouting the sensing line.
This safety evaluation addressed the impact of the design change on the safety functions of the steam generator level instrumentation and concluded that the sensing line modifications and thermal insulation removal do not change or affect these safety functions.
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 There were no changes in this category implemented during May, 1997.
Procedures Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
Deficiency Reports Summary of Safety Evaluations Other There were no changes in this category implemented during May, 1997.
Summary of Safety Evaluation There were no changes in this category implemented during May, 1997.
OPERATING DATA REPORT Docket No:
Date:
Completed by:
Robert Phillips Telephone:
Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period May 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)
Report, Give Reason NA
- 9.
Power Level to Which Restricted, if any (Net MWe)
- 10. Reasons for Restrictions, if any
- 11. Hours in Reportirig Period
- 12. No. of Hrs. Rx. was Critical
- 13. Reactor Reserve Shutdown Hrs.
- 14. Hours Generator on-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Elec. Energy Generated (MWH)
- 18. Net Elec. Energy Gen. (MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net)
- 23. Unit Forced Outage Rate This Month 744 0
0 0
0 0
0
-7624 0
0 0
0 100 NA Year to Date 3623 0
0 0
0 0
0
-37895 0
0 0
0 100 50-311 06/10/97 339-2735 since Last N/A Cumulative 144229 78083.6 0
75229.5 0
187781005 78648898 74642704 52.2 52.2 46.8 46.4 32.8
- 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:
Under review.
8-1-7.R2 I
~RAGE DAILY UNIT POWER LEV.
Docket No.:
50-311 Unit Name:
Salem #2 Date:
06/10/97 Completed by:
Robert Phillips Telephone:
339-2735 Month May 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 5-1-97 F
1 2
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH May 1997 DURATION TYPE1 (HOURS)
REASON 2 744 F.C Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing 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.: _,5=-=0:..,.-=-31'-'1'"""" __ _
UNIT NAME:
Salem #2 DATE:
06-10-97 COMPLETED BY:
Robert Phi.ll.i.E!§.
TELEPHONE:
609-339-2735 COMPONENT CAUSE AND CORRECTIVE ACTlON 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:
May, 1997 Month:
May, 1997 Docket No.
50-311 Unit Name:
Salem 2
Contact:
D. Tisdel Telephone:
609-339-1538
- 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 MONTHLY"OPERATING
SUMMARY
- UNIT 2 MAY 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.
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