ML20127L454
| ML20127L454 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1985 |
| From: | Ronafalvy J, Zupka J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8505220347 | |
| Download: ML20127L454 (14) | |
Text
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- t AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date May 10,1985 Completed by.
J. P. Ronafalvy Telephone 609-935-6000 Extension 4455
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Month April 1985 Day Average Daily Power Level-Day Average Daily Power Level (MWe-NET)
(MWe-NET)
'1' 1077 17 1100
.2
-1107 18 1093
-3 1095 19 1102 4
1092 20-986 5
1099 21 1099 6-1095 22 1039' 7
1107 23 1079 8-1114 24 1109 9-1093 25 1100 10 1103 26 1096 11 1084 27 1107 12-1113 28 1089 13 1095 29
-1109 14 1106 30-1090 15 1100 31 16 1107 P. 8,1-7 R1 h
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. OPERATING. DATA REPORT-Docket No.50-272 as,
.Date May 10, 1985 Telephone 935-6000 y
P. Ronafalvy Extension ~4455 Completed by
-J.
sOperating Status
' Salem No.'1' Notes 1.
Unit Name.
- April 1985 2.
- Reporting Period
- 3.. Licensed Thermal Power (Mit)~
-3338 L4..
Nameplate Rating (Gross MWe)
T176
- 5.. Design Electrical l Rating (Net MWe)
T5T6 6.
' Maximum Dependable Capacity (Gross MWe)IT2T
- 17. ~ Maximum Dependable Capacity (Net MWe) T67T
'8.
If. Changes Occur in Capacity Ratings (items 3 through 7).since Last Report,.Give' Reason-N/A 9..LPower Level to which Restricted, if any (Net MWe)
N/A
- 10. Reasons 1for Restrictions, if any N/A This Month Year to Date Cumulative
'11.LHours in Reporting Period 719 2879 68688 11:2. ENo. of. Hrs. Reactor was Critical 719 2861.6 38685.1 13.-Reactor Reserve' Shutdown Hrs. 0 3088.4 14-. Hours Generator >On-Line 719 2858.7 37017.3 L15. Unit Reserve Shutdown' Hours 0
0 0
- 16. Gross Thermal Energy Generated Dem) 2394694 9477598-112245595
- 17. Gross Elec. Energy Generated 37159800 100G1) 818610 3243750 18.LNet'Elec.-Energy Generated (MWH) 787467 3118672 35216654 ly
- 19. Unit ~ Service Factor 100 99.3 53.9
- 20. Unit.-Availability Factor 100 99.3 53.9
- 21. Unit Capacity Factor'
-(using MDC Net)-
101.5 100.4 47.5
- 22. Unit Capacity Factor
-(using DER Net) 100.5 99.4 47.0
- 23. Unit-Forced-Outage Rate 0
0.7 31.5
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A 2..-If shutdown at end of Report Period, Estimated Date of Startup:
5 N/A
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved i
Initial. Criticality 9/30/76 12/11/76 i
Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76
-6/30/77 8-1-7.R2-Page of
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Dockrit No.'50-272'
' UNIT' SHUTDOWN AND POWER REDUCTIONS
. REPORT MONTH April 1985 Unit'Name S'ilem No.1 Date May 10,1985 Completed.by -J.P.-Ronafalyy'
. Telephone 609-935-6000 ExtensionL 44 55 Method of Duration
. Shutting
-License Cause and Corrective No.
Date Type-Hours Reason Down LEvent System
. Component-Action to 1-2 Reactor Report Code 4 Code 5 Prevent Recurrence
- There were no outages in April-resulting-in load. reductions greater than 20%._
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1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as
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S: Scheduled B-Maintenance or Test 2-Manual. Scram.
for Prepara ' Source 3-Automatic. Scram. tion of Data C-Refueling 4-Continuation of Entry Sheets D-Regulatory.. Restriction E-Operator Training & Licensing Exam'
' Previous Outage for Licensee
-F-Administrative' 5-Load Reduction' Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain-
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(NUREG 0161)-
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' MAJOR PLANT MODIFICATIONS
-DOCKET NO.:
50-272 REPORT 1 MONTH' APRIL 1985 UNIT NAME:
Salem-1 DATE:.May-10, 1985 COMPLETED BY:
J. Ronafalvy TELEPHONE:
609/339-4455
- DC R NO. -
PRINCIPLE SYSTEM
Security Erect a subcontractors' security gatehouse.
- 14 Fan Coil Unit-Add. temperature connections to
- 14 FCU motor housing.
1EC-1264A Moisture Separator Modify existing HP-channels.to LReheater Steam ~and reflect.the design (that was Drains performed,cnl the Unit 2'HP channels.
This includes the following:
- 1) Modify 4th pass drain connection to conform to the tube sheet ligament-configuration and seal using Kalrex "O" ring.
- 2) Modify the 3rd pass connection ~as in
-item (1)-above.
- 3) Modify channel cover to accept Kalrez "O"
ring.
- 4) Re-route 4th pass drain and vent.
- 1EC-1611 Safety Injection Change valve packing for valves 1SJ4, 5,:12 and 13
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(Valve Mark No.. FA-46). from existing " John Crane 187-I"
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packing to new "Grafoil Halogenated Valve Stem Die Molded Ring Sets."
1EC-1810 Miscellaneous Change range of 1PL3325 and Condensate 1PL33 26 from 0-3004 to 0-6004.
11EC-1847' Generator Rewind of No. 1 Generator.
1EC-1929A Circulating Water Upgrade the material of construction of Circulating Water Pump 13A.
1EC-1948 Main Generator Replace existing hydrogen Hydrogen dryer with a larger capacity dual tower dryer..
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- DCR NO.
PRINCIPLE SYSTEM SUBJECT
-1MD-0091 Communications Implement Suggestion 77-159 to install interfacing relay _
between phone and P.A. system.
1SC-0159 Main Steam Provide low temperature alarm
-in north and south penetration.
1SC-0363 Condensate Modify condenser, heater drain and circulating water pump motors to allow filling of oil reservoirs.
Circulating Water Provide.the following changes:
Traveling Screens
- 1) Stainless steel chain.
- 2) Fill in. unused fish trough.
- 3) Install trolley beam for basket removal.
- 4) Install access holes in head section.
1SC-0967 Potable Water
. Install screening on potable water tank overflow line.
1SC-1272 Auxiliary Feedwater The.#13-Aux Feedwater Pump Trip Valve 1 MSS 2 presently I
does not provide indication'in the Control Room when it is reset and latched.
Provide-indication-on the controls bezel to indicate when trip valve is reset and latched.
1SC-1305 Security (Barriers)
Make additions and modifications to provide security barriers on outside air intake / exhaust openings on ventilation systems at 130' El. South Penetration.
1SC-1385 Heater Drain Pump Provide gland leak off' lines from all three heater drain pumps to the Turbine Building flood sumps.
1SC-1411A Annunciator System Delete-vacuum switch 1PD188.
Install an (actual trip) alarm actuated by vacuum trip solenoid.
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l MAJOR-PLANT MODIFICATIONS" DOCKET-NO.:
50-272 REPORT MONTH ~ APRIL 1985 UNIT NAME:
- Salem 1 DATE:
May 10, 1985 COMPLETED BY:
J.-- Ronafalvy TELEPHONE:
609/339-4455
- DC R. NO. -
SAFETY EVALUATION 10 CFR 50.59 1BC-0743A' 1The erection of a steel building will neither effect any previously performed safety analysis nor affect the safe operation of the plant.
No unreviewed safety or environmental questions are involved.
1ET-1165 The addition of' thermometer connections to the Fan Coil housing'does not effect the safe shutdown of the plant.
No unreviewed safety or environmental questions are involved.
1BC-1264A.This change does not affect presently. performed safety
. analysis nor does it create any new hazards.
The system involved is not safety related.
No unreviewed safety or
-environmental questions are involved.
'1BC-1611 The replacement of the existing valve packing will
' increase the reliability of the affected valves.
No
- unreviewed safety or environmental questions are involved.
R, 1EC-1810
- This change does not affect the intended function of the system.
It will not change the plant process or discharge
-and will not affect the' existing plant impact.
No unreviewed safety or environmental questions are involved.
1EC-1847 This change is a conventional installation which does not interface or alter any safety related equipment.
No unreviewed safety or environmental questions are involved.
1EC-1929A This part changeout of Circulating Water Pump Nos. 13A, 11B, 12A and 13B.does not affect the present safety analysis nor does-itLcreate any new hazards.
The basis for.the Tech.~ Specs. remains unchanged.
No unreviewed
, safety or environmental questions are involved.
This change is a conventional installation which does not interface or alter any safety related equipment.
No unreviewed safety or environmental questions are involved.-
- DCR - Design Change Request
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- DCR NO.
SArr.ii EVALUATION 10 CFR 50.59 i
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1MD-0091 This is a non-safety related change which ties together
=the N.J. Bell Telephone-system with the Station PA System.
No unreviewed safety or~ environmental questions are-involved.
's 19C-0159 The thermostats being added were-not used in the calculation for 'any presently performed safety. analysis.
Their failure does not constitute a new hazard not-.
- previously analyzed.. The thermostats do not'enterLinto the logic for the basis of any of the Technical Specifications.
No unreviewed safety or. environmental:
questions are involved.
The change in the upper and. lower bearing oil fill piping will Lnot affect' the operation of the motors.
No unreviewed. safety or environmental questions are involved.
I 1SC-0909-This system is not safety.related.
No unreviewed safety or environmental questions are involved.
1SC-0967 The addition of screening material within the overflow of the Portable Water Tank does not affect'any previously performed = safety analysis.- No unreviewed safety or
-environmental questions are involved.
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This' change enhances the operators control Room indication for the 13 Aux Feedwater status.
The change does not alter any automatic control system or' adversely affect the capability 1to safely shut /down the plant.
No unreviewed safety-or environmental questions'are involved.
ISC-13 05
.This change provides a more adequate security system by.
bringing a vent opening into compliance with,10CFR73.55.
No unreviewed safety or environmental questions are involved.
1SC-1385 This change does not affect any previously performed safety analysis nor does it create any new hazards.
The E
basis for the Tech. Specs.' remains unchanged.
No unreviewed safety or environmental questions are' involved.
'1SC-1411A The moving of an annunciator window to a new location does not affect any safety functions or safety related equipment.
No unreviewed safety or environmental questions are involved.
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- DCR - Design Change Request i
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PSEEG SALEM-GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO-DEPT UNIT EQUIPMENT. IDENTIFICATION
.8504240860 SMD 1'
14MS131, PRESS TAP -ISOL. -
FAILURE DESCRIPTION:
14MS131, (l" PRESS. TAP ISOLATION VALVE) ~ HAS A BAD
. PACKING-LEAK.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
FURMANITED GLAND PER PROCEDURE T-161.
8504230678 SIC 1
13 C.F.C.U.. FLOW TRANS.
FAILURE DESCRIPTION:
PLEASE BLOWDOWN'#13 C.F.C.U. FLOW TRANSMITTER.
CORRECTIVE ACTION:
FOUND FLOW TRANSMITTER PLUGGED.
CLEARED BLOCKAGE.
8504230562 SMD 1
1CV268 POSITION IND FAILURE DESCRIPTION:
THERE IS A SCREW MISSING FROM THE POSITION IND ON THE REACH ROD AND WE ARE UNABLE TO DETERMINE THE VALVE POSITION.
CORRECTIVE ACTION:
DRILLED AND TAPPED HOLE INSERTED SCREWS.
t 8504161200 SMD 1
llSW303 FAILURE DESCRIPTION:
HEAT TRACE ON LINE FROM 11SW303 TO LOCAL GAUGE IS COLD.
PLEASE REPAIR.
CORRECTIVE ACTION:
HEAT TRACE WAS CUT - SPLICED NEW LENGTH OF HEAT TRACE.
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t SALEM UNIT 1-WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8504081443 SIC 1
FAILURE DESCRIPTION:
COMPARATOR TRIPPING OUT OF SPEC. RECAL AS'NECESSARY.
CORRECTIVE ACTION:
REPLACED CAPACITORS IN 1PM-514B AND CALIBRATED.
8504050092 SMD 1
CVCS BORIC ACID FAILURE DESCRIPTION:
SHAFT SEAL APPEARS TO BE LEAKING.
PLEASE REPAIR.
CORRECTIVE ACTION:
REPLACED SEAL.
8504010741 SMD 1
13 GB4 FAILURE DESCRIPTION:
VALVE HAS A BODY TO BONNET LEAK.
MAINT DEPT PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
FURMANITE VALVE PER - T16 0 PROCEDURE.
8502140922 SMD 1
13 ' CFCU FAN FAILURE DESCRIPTION:
I/O #251580:
REPACK AND REGREASE PILLOW BLOCK BEARINGS AND LABYRINTH SEALS DURING MOTOR BEARING INSPECTION.
CORRECTIVE ACTION:
REPACKED AND REGREASED PILLOW BLOCK BEARING.
PERFORMED VIBRATION - OK 8502210084 SMD 1
1 CC 364
-FAILURE DESCRIPTION:
REPACK VALVE AND PUT ON NEW GLAND NUTS.
COULD NOT TAKE UP ANY MORE ON PACKING.
CORRECTIVE ACTION:
REPLACED GLAND NUT AND PACKING.-
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION -
0099161125 SIC 1
15' CFCU FAILURE-DESCRIPTION:
15 CFCU - NO FAST' SPEED SW FLOW INDICATION-IN CONTROL ROOM - PLEASE REPAIR.
CORRECTIVE ACTION:
CLEARED CLOGGED SENSING LINE TO FLOW TRANSMITTER.
0099005603 SMD 1
12 BAT PMP FAILURE DESCRIPTION:
INSUFFICIENT FLOW AND DISCHARGE PRESS FROM PUMP.
CORRECTIVE ACTION:
READJUSTED IMPELLER CLEARANCE TO.008.
0099014505 SMD 1
11SW303 FAILURE DESCRIPTION:
GAUGE LINE DOWNSTREAM OF 11SW303 BROKEN.
REPAIR.
0099015021 SMD 1
VITAL HEAT TRACE FAILURE DESCRIPTION:
HEAT TRACE CIRCUIT 701 AND 704 ON BORIC ACID EVAP SKID REQUIRES INSULATION TO MAINTAIN PROPER
-TEMPERATURE.
CORRECTIVE ACTION:
BOTH 701 AND 704 SATISFACTORY.
FOUND THERMOCOUPLE IN WRONG LOCATION.
MOVED TO PROPER LOCATION.
0099018659 SIC 1
11 RX COOL LOOP DELTA T FAILURE DESCRIPTION:
1BS-411D TRIPPING OUT OF SPEC.
RECAL AS NECESSARY.
CORRECTIVE ACTION:.
FUNCTION GENERATOR 10M-411A OUT OF SPEC.
ADJUSTED TO SPEC.
RETURNED TO SERVICE.
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. SALEM UNIT 1
. WO NO DEPT UNIT EQUIPnt;nT IDENTIFICATION
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~0099157519 SIC 1
1B DIESEL SPEED IND.-
= FAILURE DESCRIPTION:
PAINTER STEPPED.ON PICK-UP, PLEASE INVESTIGATE AND
-REPAIR AS NEEDED.
CORRECTIVE ACTION:
REPLACED BROKEN SPEED PICKUP.
REPAIRED BROKEN FLEX.
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT-NO. 1 APRIL 1985 SALEM NO. 1 The Unit began the' period operating at full power.
On 4/20/85 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, load was reduced to 80% to support Turbine / Generator vibration testing.
The Unit was returned to full power operation by 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on 4/20/85 and continued to operate at full power for the remainder of the period.
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.f, e
y REFUELING INFORMATION DOCKET NO. :
50-272-
[ COMPLETED BY:
J. Ronafalvy UNIT NAME:
Salem 1 DATE:
May 10, 1985 TELEPHONES :609/935-6000 EXTENSION:
4455 t
t
. Month April 1985 1.
Refueling' information has changed from last month:
t YES NO X
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- Scheduled date for next~ refueling:
February 22, 1986
'3.
Scheduled date for restart following refueling:
May 4,1986 4.
A)
'WilliTechnical Specification changes or other license amendments be required?
YES.
NO NOT NRMINED TO DATE B)~
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES-
- NO X
If no, when is it scheduled?
January 1986 5.
Scheduled date(s) for submitting proposed licensing action:
January 1986 if required 6.
Important licensing considerations associated with refueling:
NONE 7. -.
Number of Fuel Assemblies:
- A)
Incore.
193 B)
In Spent Fuel Storage 296
- 8.
Present licensed spent fuel storage capacity:
1170 Future spent. fuel storage capacity:
1170 9.
Date of last refueling that can be discharged to spent fuel pool assuming the present
- licensed capacity:
September 2001 8-1-7.R4
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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station.
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g,y 10,'1985 Director, Office-of Inspection and. Enforcement U.S.'. Nuclear Regulatory Commission washington', DC 20555
Dear Sir:
MONTNLYLOPERATING REPORT S ALEN ' NO. 1 DOCKET NO. 50-272.
- In compliance with Section 6.9, Reporting Requirements for the Salem-Technical-Specifications,10 copies of the following. monthly operating' reports..for the month of April 1985.are being sent to you.
Average Daily Unit Power Level s
Operating Data Report ~
Unit Shutdowns and Power Reductions Major Plant Modification
. Safety.Related Work Orders Operating Summary Refueling'Information Sincerely yours, 44 n f s4 J. M. Zupko, Jr.
General Manager - Salem Operations JR sbh
- cc t -
Dr. Thomas E. Murley LRegional Administrator USNRC Region I
.631 Park' Avenue
- . King'of Prussia,, PA 19406
. Director, Office of Management Information'and. Program Control U.S.. Nuclear Regulatory; Commission Washington, DC' 20555 i
< Enclosures
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The Enorgy Peoplo 95 2189 (20M) I188 S=t
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