ML18096B195
| ML18096B195 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/31/1992 |
| From: | Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9301220162 | |
| Download: ML18096B195 (11) | |
Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 January 14, 1993 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 December 1992 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
~'rely yours, g~
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
,,.:a " 0 4,.
~uU*
1~
The Enerov Peoole.
9301220162 PDR ADOCK R
921231 05000272 PDR 95-2189 (10M) 12-8
. 8-1-7.R2 AVERAGE DAILY UNIT POWER LEVEL Completed by:
Mark Shedlock Month December 1992 Day Average Daily Power Level (MWe-NET) 1 1114 2
1124 3
1120 4
1108 5
1051 6
1069 7
1124 8
1111 9
1098 10
.1116 11 1122 12 1071 13 1123 14 1109 15 1076 16 1056 Day Docket No.:
- 50-212 Unit Name:
Salem #1 Date:
1/11/93 Telephone:
339-2122 Average Daily Power Level (MWe-NET) 17 1124 18 1122 19 1064 20 1129 21 1127 22 1035 23 1018 24 519 25 0
26 0
27 0
28 0
29 272 30 927 31 1097
OPERATING DATA REPO~
Docket No:
50-272 Date:
01/11/93 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period December 1992
- 3.
Licensed Thermal Powe+ (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:..i-=.A-=----~~~~~~~~~~~~~~~~~~~~~~~-
2
- 9.
Power Level to Which Restricted, if any (Net MWe)
N/A
- 10. Reasons for Restrictions, if any ~~~~~~~N~=A'--~~~~~~~~~~~
- 12. 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 This Month 744 717.0 0
632.8 0
2091727.2 701310 669573 85.0 85.0 81.4 80.7 15.0 Year to Date 8784 5581.7 0
5092.5 0
16701463.2 5568360 5295086 58.0 58.0 54.5 54.1 24.2 Cumulative 135937 89182.0 0
86140.4 0
272198608.4 90372990 86071659 63.4 63.4 57.2 56.8
- 21. 5
- 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
NO.
DATE 0059 12/24/92 F
0060 12/26/92 F
1 2
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1992 DURATION TYPE 1 (HOURS)
REASON 2 49.1 62.1 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction A
A METHOD OF SHUTTING DOWN REACTOR 1
1 E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
LICENSE EVENT SYSTEM REPORT #
CODE4 3
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther HF CH COMPONENT CODE6 DOCKET NO.:
~5=-'0..,.-=27~2'"=""" __ _
UNIT NAME:
Salem #1 DATE:
01/11/93 COMPLETED BY:
Mark Shedlock TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE FILTER CIRC. WATER INTAKE DEBRIS HTEXCH FEEDWATER CHEMISTRY 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source
e e
SAFET~ RELATED MAINTENANCE DOCKET NO:
50-272 SALEM 1 MONTH: -
UECEMBER 1992 UNIT NAME:
WO NO UNIT 910304157 1
930112006 1
DATE:
COMPLETED BY:
TELEPHONE:
JANUARY 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION VALVE 1CH232 FAILURE DESCRIPTION:
VALVE 1CH232 FAILED FLOW TEST -
REPAIR 12 AUXILIARY FEEDWATER PUMP FAILURE DESCRIPTION:
RECALIBRATE PUMP SUCTION PRESSURE TRANSMITTER AND INDICATION
e 10CFR5~.59 EVALUATIONS M0NTH: -
DECEMBER 1992 DOCK' NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JANUARY 10, 1993 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 and concurs with these evaluations.
ITEM
SUMMARY
A.
Design Change Packages (DCPs) lEC-3211 Pkg. 1 lEC-3210 Pkg. 1 "Circulating Water System Bearing Lube Water Instrumentation" - This design change will install flow switches in the Circulator bearing water lines to provide an alarm if bearing cooling water flow is low and the pump is running.
These flow switches will alarm at two new annunciators, one on the Unit 1 side and one on the Unit 2 side, that will also be installed by this DCP.
Existing trip alarms from the bearing water pumps will also provide alarms at the new annunciators.
A summary alarm from the new annunciator will provide an alarm to the Main Control Room annunciator.
The addition of bearing flow alarms has no affect on the margins of safety that are the basis for Technical Specifications.
The Technical Specifications do not address the non-safety related circulating Water System.
(SORC 92-119)
"Circulating Water Vacuum Breakers, Control Air and Station Air Modifications" -
The purpose of this design change is as follows: 1.) The CA distribution headers adjacent to the Units 1 and 2 CW vacuum breakers will be buried on the East side of the standpipes.
The CA supply to the Unit 1 vacuum breakers will be rerouted and two new header isolation valves will be added to the piping; 2.) Circulating Water Pump Discharge Piping Vacuum Breaker instrumentation will be replaced in kind.
The new instrumentation will be enclosed in new NEMA 4 instrument enclosures. 3.)
The existing electrical junction at the vacuum breakers will be replaced with a new enclosure; 4.) A french drain will be constructed adjacent to the vacuum breakers to provide drainage for the area.
The modifications proposed by this design change have no affect on the margins of safety that are the basis for the Technical Specifications.
These modifications will only affect non-safety related portions of the Chilled Water and Station Air systems.
(SORC 92-120)
e 10CFR90.59 EVALUATIONS MONTH: -
D.ECEMBER 1992 (cont'd)
ITEM lEC-3205 Pkg. 1 lEC-3135 Pkg. 1 lEA-1035 Pkg. 1 DOCKI NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JANUARY 10, 1993 J. FEST (609)339-2904 "RVLIS Refueling" -
The purpose of this design change is to rescale the RVLIS level transmitter and correct program valves for proper refueling mode RVLIS operation.
This change also modifies the head vent sensors isolation valve to drain the sensor for refueling mode.
The proposed change makes no alteration to the margin of safety as defined in the bases for the Technical Specifications.
{SORC 92-122)
"Salem Emergency Response Data System" - This design change will implement the Emergency Response Data System, ERDS, for both Salem Units.
The ERDS computer system will be installed in the Salem TSC, and will receive point data from the SPDS computer and transmit this data to the NRC.
computer.
The SPDS computers will be modified to transmit plant data to the ERDS computer, and to give the capability to activate the ERDS transmissions from the control room SPDS CRTs.
Activation of ERDS will occur within one hour of an alert of higher emergency action level being declared.
The ERDS and SPDS systems are not Technical Specification items.
The proposed changes will not reduce the margin of safety as defined in the bases for the Technical Specifications.
{SORC 92-122)
"Chemistry Laboratory Floor Drains" -
The floor drains in the radiochemistry laboratory on Elevation 100 1 of the Auxiliary Buildings are covered and sealed by an epoxy resin floor which has been installed in the lab.
The floor drain grates were taped over so that the self-leveling floor could be poured over the existing lab floor.
Thus, the floor drains have been permanently plugged.
The radiochemistry laboratory and floor drain system are not discussed in the Technical Specifications.
The proposed changes will not reduce the margin of safety as defined in the bases for the Technical Specifications.
{SORC 92-127)
e 10CFR5~.59 EVALUATIONS MONTH: -
D.ECEMBER 1992 (cont'd)
ITEM DOCK' NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JANUARY 10, 1993 J. FEST (609)339-2904 B.
Procedures and Revisions Sl.OP-SO.eVe-0006(Q)
"Boron Concentration Control" -
The purpose of this change is as follows: 1.)0perate the eves Makeup Control System in automatic, manual, dilute, borate and alternate dilute modes; 2.) Use the eves Makeup Control system to makeup to the RWST or eves Holdup Tank; 3.) Use the Demineralized Water System as a source of primary Grade water for RCS makeup when the Primary Water Storage Tank is not available.
Reg. Guide 1.33 requires there be procedures for operation of the Chemical and Volume Control System.
Therefore, this is a procedure described in the SAR.
The changes in this revision were made in accordance with Ne.NA-AP.ZZ-0032(Q) and include the following: 1.) Reduction of minimum required RHR flow to 1000 gpm in accordance with Tech Spec 3.9.8.1; 2.) Deletion of instructions for filling the RWST of eves Holdup Tanks from the Deroin Water System; 3.) Addition of instruction which alters the alternate dilution method for more rapid dilution.
Operability of the systems/components as defined in the Technical Specifications is not affected.
Therefore, the margin of safety as defined in the bases of the Technical Specifications is not reduced.
(SORC 92-121)
C.
Temporary Modification Requests T-Mod #
92-111 "Portable Temporary Station Air Supply to SWIS" -
The purpose of this modification is to connect a temporary supply of compressed air to maintain service air and control air supply to the No. 1 &
2 Units Service Water Intake Structure (SWIS).
This temporary connection will supply 5 hose station with service air and, by means of existing dryers in the SWIS building, control air to 12 chlorination system valves.
The modification will only be in place during installation of lEe-3210, which will modify the service air at the Circulating Water Intake Structure.
This modification does not have any adverse impact on the margins of safety as defined in the bases for the Technical Specifications.
(SORC 92-120)
e 10CFR50.59 EVALUATIONS MONTH: -
OECEMBER 1992 (cont'd)
ITEM T-Mod #
92-118 T-Mod #
92-128 DOCK. NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JANUARY 10, 1993 J. FEST (609)339-2904 (also: 92-119;92-120; 92-121,92-122 and 92-123)
"Temporary Modifications in Support of DCP lEC-3212 11 The purpose of these modifications is to install a nitrogen bottle to provide a temporary air source to travelling backwash valves.
The existing sources of air for these valves are located in panels which must be isolated while performing the implementation of DCP lEC-3212.
These TMODs will provide for continuous backwash operation and proper operation of the travelling screens.
The proposed changes do not alter the original function for which the Control Air system is analyzed.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-120)
"Temporary Bearing Lube Piping to 12A Circulating Water Pump" - The purpose of this TMOD is to bypass bearing lube isolation valve 12CW911, which is stuck closed.
This modification will restore bearing lube flow to 12A Circulator.
The water supply will be from the 1CW902 valve.
There are no Technical Specifications addressing Circulating Water or Bearing Lubrication nor the base.s of these systems.
Therefore, the margin of safety as defined in the basis of the Technical Specifications is not reduced.
(SORC 92-126)
~.
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 DECEMBER 1992 The Unit began the period operating at full power.
Several minor load reductions were performed during December due to heavy grass and debris in the river resulting in high circulator discharge Delta T.
On December 24, 1992, the Unit was removed from service due to a loss of the circulators, caused.by severe grass and debris at the intake structure.
The Unit was synchronized on December 26, 1992, and wa.s increasing in power when a condenser tube leak in 12A condenser required a plant shutdown due to chemistry limitations.
The Unit was synchronized and returned to full power on December 29, 1992.
The Unit continued to operate at full power throughout the remainder of the period.
\\
'J
-1
I I
REFUELING INFOF.MATION~
MONTH: -
OECEMBER 1992 MONTH DECEMBER 1992 DOCK.NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
OCTOBER 2, 1993 50-272 SALEM 1 JANUARY 10, 1993 J. FEST
{609)339-2904
- 3.
Scheduled date for restart following refueling:
DECEMBER 13, 1993
- 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 656
- 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