ML18100A378
| ML18100A378 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1993 |
| From: | Fest J, Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9305200063 | |
| Download: ML18100A378 (17) | |
Text
..
PS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 14, 1993 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 April 1993 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 cc:
Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4 The Energy Pe_oole _
_,---------9305200063 930430.....
~. O r*,.0 PDR ADOCK 0500027~
-~ \\J 1
- J ' 0 R
PDR 95-2189 (10M) 12-89
~RAGE DAILY UNIT POWER LE~
Docket No.:
50-272 Unit Name:
Salem #1 Date:
5/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month April 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET)'
1 1125 17 850 2
1073 18 675 3
1013 19 682 4
883 20 890 5
1004 21 651 6
985 22 724 7
757 23 593 8
831 24 649 9
766 25 917 10 776 26 1045 11 760 27 1024 12 769 28 1093 13 822 29 1023 14 902 30 783 15 815 31 16 914 P. 8.1-7 Rl
OPERATING DATA REPORT Docket No:
50-272 Date:
05/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period April 1993
- 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 NA 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 719 719 0
719 0
1958695.2 649580 618040 100 100 77.7 77.1 0
Year to Date 2879 2622.91 0
2537.35 0
7944417.6 2666710 2541922 88.1 88.1 79.8 79.2
- 11. 9 Cumulative 138816 91804.89 0
88677.76 0
280143026.0 93040700 88613581 63.9 63.9 57.7 57.3
- 21. 2
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling, 10-02-93 approximately 72 days.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA 8-l-7.R2
NO.
DATE 0032 03/31/93 F
0033 04/01/93 F
0064 04/02/93 F
0034 04/03/93 F
0035 04/04/93 F
0037 04/04/93 F
0036 04/05/93 F
0040 04/06/93 F
0038 04/07/93 F
0039 04/07/93 F
0041 04/08/93 F
0065 04/08/93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE1 (HOURS)
REASON2 6.22 A
4.67 D
9.90 A
1.17 B
2.83 B
22.17 B
6.28 B
57.80 D
7.0 B
0.78 B
117.98 D
49.83 A
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS 5
5 5
5 5
4 5
5 5
5 5
5 REPORT MONTH APRIL 1993 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT #
HF HF HF HF HF HF HF HF HF HF HF HF 3
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain)
COMPONENT CODE 5 PUMP XX PUMP XX PUMPXX PUMP XX PUMP XX PUMP XX PUMP XX PUMP XX PUMP XX DEMINX PUMP XX PUMP XX 4
DOCKET NO.: _5""0""--=2,_,72=-=----
UNIT NAME:
Salem #1 DATE:
05/10/93 COMPLETED BY:
Mark Shedlock TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CIRCULATING WATER PUMPS STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
CIRCULATING WATER PUMPS CONDENSER TUBE/WATER BOX CLEANING CONDENSER TUBE/WATER BOX CLEANING CONDENSER TUBE/WATER BOX CLEANING CONDENSER TUBE/WATER BOX CLEANING STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
CONDENSER TUBE/WATER BOX CLEANING FEEDWATER CHEMISTRY STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
CIRCULATING WATER PUMPS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Exhibit 1 - Same Source Event Report CLER) File (NUREG-0161)
NO.
DATE 0066 04/11/93 F
0042 04/13/93 F
0043 04/14/93 F
0044 04/14/93 F
0045 04/16/93 F
0046 04/17/93 F
0047 04/17/93 F
0048 04/17/93 F
0049 04/17/93 F
0050 04/17/93 F
0051 04/17/93 F
0067 04/17/93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE1 (HOURS)
REASON 2 4.93 A
19.68 D
15.17 D
39.38 D
17.25 D
4.25 D
1.50 D
4.0 D
3.48 D
3.48 D
7.33 D
0.17 A
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS 5
5 5
4 4
4 4
4 4
5 4
5 REPORT MONTH APRIL 1993 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT #
HF HF HF HF HF HF HF HF HF HF HF HF 3
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain)
COMPONENT CODE 5 PUMPXX PUMP XX PUMP XX PUMPXX PUMP XX PUMPXX PUMPXX PUMP XX PUMPXX PUMPXX PUMP XX PUMP XX 4
DOCKET NO.:
~5~0'-=-*=27~2"'=" __ _
UNIT NAME:
Salem #1 DATE:
05/10/93 COMPLETED BY:
Mark Shedlock TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CIRCULATING WATER PUMPS STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
CIRCULATING WATER PUMPS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161)
Exhibit 1 - Same Source
NO.
DATE 0052 04/18/93 F
0053 04/18/93 F
0068 04/19/93 F
0069 04/19/93 F
0070 04/20/93 F
0054 04/22/93 F
0055 04/22/93 F
0056 04/26/93 F
0057 04/27/93 F
0058 04/27/93 F
0059 04/27/93 F
0060 04/27/93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE 1 (HOURS)
REASON2 1.85 D
108.37 D
3.95 A
3.20 A
4.70 B
5.80 D
57.75 D
2.82 A
4.43 A
2.25 A
.058 A
1.95 A
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS 5
4 5
5 5
5 4
5 4
4 4
4 REPORT MONTH APRIL 1993 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT #
HF HF HF HF HF HF HF HF 3
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 E-Operator Training & License Examination F-Admini strative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain)
COMPONENT CODE5 PUMP XX PUMP XX PUMP XX PUMPXX PUMP XX PUMPXX PUMPXX PUMPXX 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50*272 Salem #1 05/10/93 Mark Shedlock 339*2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CONDENSER TUBE/WATER BOX CLEANING STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
INTAKE SYS. PROBLEMS OTHER THAN TRVL SCREENS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 - Same Source CNUREG-0161) l
NO.
DATE 0061 04/27/93 0071 04/29/93 0062 04/29/93 0063 04/30/93 1
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1993 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE 1 (HOURS)
REASON 2 REACTOR REPORT #
CODE4 F
4.22 A
4 HF F
2.02 A
5 HF F
4.93 D
5 HF F
3.0 D
4 HF 2
3 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther COMPONENT CODE 5
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 05/10/93 Mark Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMPXX INTAKE SYSTEM PROBLEMS PUMPXX CIRCULATING WATER PUMPS PUMPXX STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
PUMPXX STM UNITS THERMAL DISCHARGE LIMIT ENVIRON.
4 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 - same Source
.SAFETY RELATED MAINTEN..
E MONTH: -
APRIL 1993 DOCKET.a:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 911104153 1
930105141 1
930316127 1
DATE:
COMPLETED BY:
TELEPHONE:
MAY 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION 11 CHILLED WATER PUMP FAILURE DESCRIPTION:
11 CHILLED WATER PUMP LEAKING OIL REPAIR AS REQUIRED 856 AMSAC FAILURE DESCRIPTION:
856 AMSAC DEFECTIVE POWER SUPPLY REPLACE VALVE 12SW38 FAILURE DESCRIPTION:
FAILED PERFORMANCE TEST -
OPEN AND INSPECT
.10CFR50.59 EVALUATIONS e MONTH: -
APRIL 1993 DOCKET.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 MAY 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-3208 Pkg 1 lSC-2164 Pkgs 1-3 "Salem Fire Damper Upgrade" -
The design scope for the fire damper project provides for the upgrading of Salem Unit 1 and Unit 2 fire dampers to meet the fire protection license conditions.
Numerous plant HVAC System fire dampers and ductwork require rating upgrades; numerous fire dampers will be replaced with upgraded components, some existing fire dampers will be modified to obtain the required rating, some new fire dampers will be installed in the established fire barrier and some existing dampers and ductwork will be fire wrapped to obtain necessary ratings.
The design scope for this package includes the replacement, relocation, and/or modification of existing fire dampers to the Unit l's Auxiliary Building Ventilation (ABV)
System.
The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply.
The margin of safety is not reduced because the modifications are enhancing the Fire Protection System to meet the criteria of 10CFR50 Appendix R.
(SORC 93-029)
"Installation of Synchronizing Permissive Devices for No. 1 Unit Emergency Diesel Generator" - This change will provide permissives to allow the operator to synchronize the Diesel Generators (D/G) with their associated vital busses.
The permissives will be enabled during a specific closing phase angle range, slip limit (F limit),
and voltage range.
The permissive will be blocked when out of these specific ranges.
In addition, the syncrocloser check relay will permit dead bus closure of the diesel generator breaker.
These change packages will consist of the modification of the Design Generator Control Panels to add syncroclose check relays, auxiliary relays, test switches and green indicating lights, in order to accomplish the above changes.
The implementation
, J,_OCFR50. 59. EVALUATIONS e MONTH: -
APRIL 1993 (cont'd)
ITEM lSC-2163 Pkg 1 lEC-3226 Pkg 1 DOCKET.a:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MAY 10, 1993 J. FEST (609)339-2904 of this package will not reduce the margin of safety as defined in the basis for any Technical Specification.
Failure of the synchronizing permissive circuit will not render the D/G inoperable or affect the limiting conditions for station operations.
Existing surveillance and operating procedures include manual synchronizing of the D/G.
(SORC 93-029)
"Installation of Synchronizing Permissive Devices to Main Generator" - This change will provide a permissive to allow the operator to synchronize the Main Generator to the power grid.
The permissive will be enabled during a specific closing phase angle range, slip limit (F limit),
and voltage range.
The permissive will be blocked when out of these specific ranges.
This change package will consist of (1) the modification of the Unit 1 Control Console to add a green light and keylock switch, (2) the modification to Relay Rack [R2] to add a syncrocloser check relay, test switch, and (3) the modifications to Relay Cabinet Rll-4 to add four auxiliary relays.
Three new cables will be required.
The implementation of this DCP will not reduce the margin of safety as defined in the basis for any Technical Specification.
Failure of the synchronizing permissive circuit will not render the main generator inoperable or affect the limiting conditions for station operations.
Existing surveillance and operating procedures include manual synchronizing of the D/G.
(SORC 93-029)
"Unit 1 - Auxiliary Feedwater and Steam Generator Blowdown Modifications" - This design change package replaces the internals of the steam generator blowdown containment isolation valves (11-14GB4) with new plug and trim that is hardfaced with stellite over the full surface of the plug and seat; it also replaced the GB4 actuators with equivalent component.
The design change further replaces the AF23 valves with Edward 4-inch Univalve Y-Pattern Stop Check, Fig.
No. D36268T1.
The proposed change does not alter the original design intent or modes of operation
- ~O~FR50. 59, EVALUATIONS e MONTH: -
APRIL 1993 (cont'd)
ITEM lEC-3209 Pkg 1 5EC-3029 Pkg 1 lEC-3208 Pkg 3 DOCKET.a:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE,:
SUMMARY
50-272 SALEM 1 MAY 10, 1993 J. FEST (609)339-2904 or function for which both systems are currently analyzed.
Therefore, the margin of safety basis for the Technical Specifications will not be reduced.
(SORC 93-029)
""Galtronics Page-Party System Modifications" -
This change package will upgrade the single page-party system presently in use at Salem Generating Station to a multiple party line system, with line 1 being dedicated to the Unit 1 Control Room, line 2 dedicated to the Unit 2 Control Room and party lines 3, 4 and 5 utilized throughout the Salem plant.
This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification because the reliability of the communication system will be improved.
The quality of the equipment is also being improved by replacing mechanical switch hooks with proximity sensors.
(SORC 93-029)
"Automated Accountability Computer System" -
An Automated Accountability Computer System is to be installed in the Secondary Alarm station (SAS) in the basement of the Security Center.
The new computer is to interface with five new card readers, located in the badge issue area, the Salem Security Computer and the local terminal/printer stations that are to be installed in the SAS and in the Salem and Hope Creek Technical Support Centers.
The Technical Specifications were reviewed and it was found that there are no applicable sections that reference the emergency plan, security computer or the accountability system.
Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-029)
"Salem Fire Damper Upgrade" -
The design scope for this package includes the replacement, relocation, addition and/or deletion of existing fire dampers to Unit l's Diesel Fuel Oil Storage Area Ventilation (DFSAV) Subsystem of the Diesel Generator Area Ventilation (DGV) System.
The function, basic configuration and operation of the
-10CFR50.59 EVALUATIONStl MONTH~ -
APRIL 1993 (cont'd)
ITEM 1EC-3189 Pkg 1 1EC-3208 Pkg 7 1SC-2296 Pkg 1 DOCKET.a:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MAY 10, 1993 J. FEST (609)339-2904 system will not be altered and the codes, standards, qualifications and design criteria of the original system will apply.
The design parameters for the modifications to the ductwork, co2 piping and electrical cable and conduit envelope the existing design requirements.
There is no change to the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-029)
"Installation of Unit Heaters in 1C Battery Room"
- Convection heaters will be installed in the 1C battery room at el. 64 1-0 11
- These heaters will be of an explosion proof, NEC Code Class I, Division I and Group B design.
The local Non-1E lighting panel A11A will be modified to provide power supplies for these heaters.
This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-031)
"Salem Fire Damper Upgrade" -
The design scope for this package includes the addition of a new fire damper and modification of an existing fire dampers in the Control Area Air Conditioning System (CAACS) Subsystem of the Control Area Ventilation (CAV) System.
The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply.
The basis for the Technical Specifications does not address the fire protection features.
Since replaced or modified fire dampers associated with the CAAC system perform no safety related functions; these modifications do not affect a safety related system which is required for safe shutdown.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-033)
"Travelling Screen Blowdown Piping Installation and Waterbox Modifications" - This DCP proposes to Modify Unit 1 and 2 circulation water travelling screens by installing 2 11 stainless steel blowdown
- iO~FR50.59_ EVALUATIONS~
MONTH: -
APRIL 1993 (cont'd)
ITEM 1EC-3193 Pkg 1 1EC-3225 Pkg 1 lEC-3099 Pkg 1 DOCKET.a:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MAY 10, 1993 J. FEST (609)339-2904 lines, associated shutoff valves and supports from the three spray wash headers located on 11A, 11B, 12A, 12B, 13A, 21A, 21B, 22A, 22B, 23A, and 23B travelling screens in the Circulating Water Intake Structure (CWIS).
The blowdown piping, valves and supports will also be installed on the two spare travelling screens.
This DCP will also modify Unit 1 condenser waterboxes by installing patches on corroded external stiffeners, adding extensions to existing external stiffeners and attaching five new stiffeners on both sides of each inlet waterbox.
The addition of blowdown piping has no effect on the margins of safety that are the basis for the Technical Specifications.
(SORC 93-033)
"Oil Water Separator System" - This change package will upgrade Salem Generating Station, Units 1 &
2, Oil-Water Separator System to ensure the effluents being discharged into the river via drainage system through manhole #15 meet the regulatory limits mandated by state statutes.
The proposed change does not reduce the margin of safety as defined in the basis for any Technical Specification as the Oil/Water Separator system is not specifically covered by the Technical Specifications.
Also, the proposed change only improves the existing Oil/Water Separator system.
(SORC 93-036)
"RG 1.97 EQ Valve Limit switch and Solenoid Modifications" - This design change package modifies the existing power, wiring and electrical protective devices of Environmentally Qualified (EQ) solenoids and valve position limit switches to provide electrical separation from Non-Environmentally Qualified (Non-EQ) solenoids and valve position limit switches.
The proposed change does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-036)
"Replacement of Rosemount Electronic Transmitters"
- This modification replaces 55 Rosemount electronic transmitters with new transmitters having improved performance under harsh
-10CFR50.59 EVALUATIONS~
MONTH~ -
APRIL 1993 (cont'd)
ITEM lEC-3208 Pkg 6 DOCKET.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MAY 10, 1993 J. FEST (609)339-2904 environmental conditions.
The new transmitters are seismically and environmentally qualified for the installed locations.
The tubing and valving arrangements will be standardized for all transmitters of the same type.
Where space is available, differential pressure transmitters will be equipped with calibration volume chambers.
These chambers allow calibration with pneumatic signals without the incursion of air into the transmitters or impulse tubing.
The modification also replaces the electronics assemblies on 16 Rosemount transmitters in accumulator level (8) and pressure {8) service.
Each of the 73 transmitters affected by this modification will be equipped with a qualified electrical connector to facilitate maintenance.
The new or modified transmitters are equal to or better than the previous instruments under all conditions.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
{SORC 93-038)
"Salem Fire Damper Upgrade" -
The design scope for this package includes the replacement, relocation, and/or modification of existing fire dampers to the Unit l's Switchgear and Penetration Area Ventilation {SPAV) System.
The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply.
The basis for the Technical Specifications does not address the fire protection features.
since replaced or modified fire dampers associated with the SPAV system perform no safety related functions; these modifications do not affect a safety related system which is required for safe shutdown.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
{SORC 93-038)
B.
Procedures and Revisions NC.NA-AP.ZZ-0015{Q)
"Safety Tagging Program" Rev. 1 -
The purpose of this revision is to provide clarification for when more than one (1) supervisor performs tagging
-10CFR50.59 EVALUATIONS--
MONTH~ -
APRIL 1993 (cont'd)
ITEM
- c.
Safety Evaluations lEC-3217 Pkg 1 DOCKET.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MAY 10, 1993 J. FEST (609)339-2904 verification prior to performing the work.
There are no specific sections addressing the details of safety in the Technical Specifications.
There is no reduction in the margin of safety as defined in the basis for any Technical Specifications.
(SORC 93-029)
"Replacement of No. 1 Fire Diesel Fire Pump" Rev.
1 -
The purpose of this revision is to address the new fire pump controller being added by this DCP.
The new controller has been chosen so that its normal operating functions will be the same as the functions of the existing controller.
The new controller configuration will be compatible with the existing No. 2 Fire Pump as well as Control Room alarms.
In addition, the new controller provides several features not included in the original controller.
These include an "Engine Test" push button which can be used to create a loss of pressure condition at the pressure transducer to cause an auto engine start sequence; a "Minimum Run time" option which allows the engine to shutdown either automatically after 5 or 30 minutes if system pressure has been restored, or manually; and safe engine shutdown circuits which cause engine shutdown to occur if the engine is running due to loss of AC start signal or test push button and either an engine low oil pressure or high temperature signal is received.
The Fire Protection Program was reviewed and it was determined that no concerns pertaining to system integrity exist.
There is no reduction in the Margin of safety as defined in the basis for any Technical Specification.
(SORC 93-029)
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 APRIL 1993 The Unit began the period operating at 100% power.
Power reductions were performed throughout the period due to waterbox fouling, travelling screen problems, and loss of circulating water pumps resulting from an excessive influx of swamp grass.
-REFUELING INFORMATION
' MONTH-: - APRIL 19 9 3 MONTH APRIL 1993 DOCKET.O:
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 MAY 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-l-7.R4