ML18096A141
| ML18096A141 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1991 |
| From: | Fest J, Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9107190118 | |
| Download: ML18096A141 (9) | |
Text
- ops~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 15, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of June 1991 are being sent to you.
RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours,
/J/~tPoL~-
f;Y C7'
~~
General Manager _/;,} ~
Salem Operations cc:
Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 1 !tl~&fMmy People r&~'f Q\\07t90j 1R 910630
~b~ *~tdcR 05000272 R
PDR I I I 95-2189 (10M) 12-89
AV~GE DAILY UNIT POWER LEVEre Docket No.:
50-272 Unit Name:
Salem #1 Date:
7/10/91 Completed by:
Mark Shedlock Telephone:
339-2122 Month June Day Average Daily (MWe-NET) 1 1067 2
1069 3
1079 4
1111 5
1090 6
1084 7
1082 8
1099 9
1106 10 1096 11 1087 12 1098 13 877 14 1089 15 1101 16 909 P. 8.1-7 Rl 1991 Power Level Day Average Daily Power Level (MWe-NET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 834 26 1094 27 1096 28 1106 29 1083 30 1091 31
9°PERATING DATA REPORT
~
Docket No:
50-272 Date:
7/10/91 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period June 1991
- 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)
- 10. Reasons for Restrictions, if any
- 11. Hours in Reporting 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 N/A This Month Year to Date 720 4343 553.8 2439.9 0
0 525.5 2324.5 0
0 1758972 7723245.6 584500 2562570 555164 2436235 73.0 53.5 73.0 53.5 69.7 50.7 69.2 50.3 27.0 7.7 N/A Cumulative 122736 79403.4 0
76892.0 0
241785630.8 80275210 76404907 62.6 62.6 56.3 55.8 22.1
- 24. Shutdowns scheduled over next 6 months {type, date and duration of each)
None
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA 8-1-7.R2
-1
NO.
DATE 0036 06/13/91 0035 06/13/91 0037 06/13/91 0038 06/16191 1
2 F:
Forced S: Scheduled DURATION TYPE1 (HOURS)
REASON2 F
4.6 F
22.2 F
11.9 F
194.5 Reason A-Equipment Failure (explain)
B*Maintenance or Test C*Refueling D*Requlatory Restriction B
B A
A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1991.
METHOD OF SHUTTING DOWN REACTOR 5
5 5
3 3
LICENSE EVENT REPORT #
Method:
1-Manual 2-Manual Scram SYSTEM COOE4 18 HH PE EA E-Operator Training & License Examination F-Adninistrative 3-Automatic scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-oPerational Error (Explain)
H-Other (Explain)
DOCKET NO.: ~5~0"""-=27~2"'::-:---
UNl T NAME:
Salem #1 DATE:
7/10(91 COMPLETED BY:
Mark Shedloc~
TELEPHONE:
339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION COOE6 TO PREVENT RECURRENCE RELAYX
- 18 SEC PUMPXX
- 11 HEATER DRAIN PUMP HTEXCH
- 12 EAST HYDROGEN COOLER LEAK TRANSF PHASE B MAIN POWER TRANF.
4 Exhibit G - Instructions for Preparation of Data
- Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit 1 - Same Source
SAFETY RELATED MAINTENANCE MONTH: -
JUNE 1991 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 DATE:
COMPLETED BY:
TELEPHONE:
JULY 10, 1991 J. FEST (609)339-2904
~-------------------------------------------------
WO NO UNIT 901025170 1
910131114 1
910211211 1
910604100 1
910604129 1
EQUIPMENT IDENTIFICATION SERVICE WATER SPOOL 1S27C FAILURE DESCRIPTION:
SPOOL 1S27C DEFECTIVE -
REPLACE SPOOL SOLENOID VALVE 1SV595 FAILURE DESCRIPTION:
SOLENOID VALVE 1SV595 DEFECTIVE -
REPLACE VALVE 1SW169 FAILURE DESCRIPTION:
VALVE INLET FLANGE LEAKS -
REPAIR 1R41C NOBLE GAS MONITOR FAILURE DESCRIPTION:
1R41C NOBLE GAS MONITOR FAILED -
INVESTIGATE 11 H2 ANALYZER FAILURE DESCRIPTION:
11 H2 ANALYZER SUSPECTED FAILURE TROUBLESHOOT
10CFR50.59 EVALUATIONS MONTH: -
JUNE 1991
- DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1991 J. FEST (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
The Station Operations Review Committee has reviewed these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).
ITEM A.
Design Change Packages lEC-3089 Pkg. 3 lEC-3091 Pkg. 1
SUMMARY
"Reactor Coolant Pump Oil Lift Pump & Motor Assembly Enclosure Modifications" -
Package 3 proposes the modification of the existing No. 13 RCP oil lift pump & motor assembly enclosure to close up some gaps that exist in the enclosure.
This will ensure the oil lift pump motor is completely isolated from the enclosure.
Additional mounting bolt holes will be drilled into the RCP motor flange to adequately support the modified enclosure.
The additional mounting bolts are needed to meet seismic II/I criteria.
There is no change in either the RCP system operation or testing procedure.
(SORC 91-038)
"Removal of the BIT Tank Relief Valve lSJlO" -
Package 1 proposes the removal of Boric Acid Injection (BIT) tank relief valve lSJlO and the installation of a blank flange to eliminate a potential leakage path from the Charging System to the Waste Holdup Tanks.
In addition, valve 1SJ77, which had previously been blanked off, will be removed and the pipe will be capped.
the removal of lSJlO will eliminate a potential leakage path from the CVCS.
The 1SJ77 valve will be removed to simplify stress analysis calculations.
There is no chance of system overpressurization since the highest discharge pressure of the pumps against a shutoff head has been shown to be below the system design pressure.
Based on information supplied by Westinghouse, this modification conforms to the latest revision of the Code.
In the event newer, stronger pumps were installed, protection from overpressurization would still be maintained by the operating procedure.
The maximum discharge pressure allowed by the procedure is well below the system design pressure.
(SORC 91-038)
10CFR50.59 EVALUATIONS MONTH:
~ JUNE 1991 (Cont'd)
ITEM DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JULY 10, 1991 J. FEST (609)339-2904
~----------------------------------------------------
B.
Deficiency Reports (DRs) Use-As-Is Dispositions DR # SMT 91-212A "11 Steam Generator (S/G)" -
This is a resubmittal of DR SMT 91-190.
The tube located at Row 1 Column 2 is not ruptured, as previously thought.
Further investigation has shown the tube was apparently cut by a grinder.
The indication is through wall.
The cut in the tube is not a safety concern as the tube is already plugged and there is no evidence of expansion of the indication.
In the event of a tube failure the situation would already be bounded by existing safety analysis.
The wording of the safety evaluation for thi~ DR was slightly revised from that of DR SMT 91-190 to incorporate information received from the vendor in regard to the use of explosive plugs.
Essentially, the evaluation concludes the affected tube is not expected to leak.
This is based on the good service record of explosive plugs during the last fourteen years both at Salem and throughout the industry.
In cases where fishmouthing of plugged tubes has occurred, the evidence indicates the explosive plugs reseal, terminating or reducing the leakage to below the detection threshold.
(SORC 91-036)
1-1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 JUNE 1991 SALEM UNIT NO. 1 The Unit began the period operating at full power and continued to operate at full power until June 13, 1991, when a shutdown was commenced due to loss of power to the lB Safeguards Equipment Cabinet (SEC).
Power was restored to the SEC and the Unit returned to full power on June 14, 1991, following SEC functional testing.
The Unit continued to operate at full power until June 16, 1991, when the Reactor tripped due to a lightning strike on the phase B main power transformer.
The Unit was returned to full power on June 25, 1991, following replacement of the phase B main power transformer high voltage bushing and related maintenance.
The Unit continued to operate at essentially full power throughout the remainder of the period.
REFUELING INFORMATION MONTH: -
JUNE 1991 MONTH JUNE 1991 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
APRIL 18, 1992 50-272 SALEM 1 JULY 10, 1991 J. FEST (609)339-2904
- 3.
Scheduled date for restart following refueling:
JUNE 12, 1992
- 4.
a)
Will Technical Specification changes or other license amendments be required?:
YES NO NOT DETERMINED TO DATE ~-x~-
b)
Has the reload fuel design been reviewed by the Station Operating Review Committee?:
YES NO x
If no, when is it scheduled?:
- 5.
Scheduled date(s) for submitting proposed licensing action:
N/A
- 6.
Important licensing considerations associated with refueling:
- 7.
Number of Fuel Assemblies:
- a.
Incore 193
- b.
In Spent Fuel Storage 588
- 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170
- 9.
Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7.R4