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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 | |||
~ | |||
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 | |||
<f6 I | |||
ggsaago?35,%2g2 R | |||
m . | |||
'C' | |||
-'' ' , . OPERATING. DATA REPORT-Docket No.50-272 as, , | |||
.Date May 10, 1985 y . | |||
Telephone 935-6000 Completed by -J. P. Ronafalvy Extension ~4455 sOperating Status | |||
: 1. Unit Name . . | |||
' Salem No.'1' Notes | |||
: 2. ; Reporting Period : April 1985 | |||
: 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 _ | |||
100G1) 818610 3243750 37159800 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 5 shutdown at end of Report Period, Estimated Date of Startup: | |||
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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+ . , | |||
' UNIT' SHUTDOWN AND POWER REDUCTIONS Dockrit No.'50-272' , | |||
. 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%._ | |||
1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 1-Manual Instructions Salem as | |||
~ | |||
F: Forced A-Equipment Failure-explain S: Scheduled B-Maintenance or Test 2-Manual. Scram. for Prepara ' Source C-Refueling . | |||
3-Automatic. Scram. tion of Data D-Regulatory.. Restriction 4-Continuation of Entry Sheets 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- (NUREG 0161)- | |||
...m _ _ _ -J | |||
~ | |||
' 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 . SUBJE CT 1BC-0743A-. Security Erect a subcontractors' security gatehouse. | |||
1ET-11657 #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 performed,cnl the Unit 2'HP Drains 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 | |||
~ | |||
(Valve Mark No. . FA-46) . from existing " John Crane 187-I" + | |||
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.. | |||
_ _ _._' . . _ , _ s | |||
M v.... | |||
*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. | |||
1SC-0909. 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. | |||
L . | |||
is | |||
(( 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. | |||
1EC-1948. 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 | |||
? | |||
( v s 1 | |||
*DCR NO. SArr.ii EVALUATION 10 CFR 50.59 | |||
~ | |||
1MD-0091 i | |||
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. | |||
1SC-0363: 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. | |||
1SC-1272~ 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. | |||
l | |||
*DCR - Design Change Request i | |||
~ | |||
~ | |||
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. | |||
J | |||
-1 4 | |||
t SALEM UNIT 1-WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8504081443 .. | |||
SIC 1 12 S/G STM PRESS CH 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. | |||
..j | |||
<"26. | |||
. SALEM UNIT 1 . | |||
. WO NO DEPT UNIT EQUIPnt;nT IDENTIFICATION | |||
~ | |||
~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 hours, load was reduced to 80% to support Turbine / Generator vibration testing. The Unit was returned to full power operation by 1900 hours on 4/20/85 and continued to operate at full power for the remainder of the period. | |||
t | |||
4 . '~ . | |||
.f, y e $ | |||
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 t | |||
: 1. Refueling' information has changed from last month: | |||
YES NO X | |||
~ 2.. - 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 | |||
' o n ,' . | |||
~ | |||
..t r | |||
i O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station . | |||
~ | |||
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. | |||
s Average Daily Unit Power Level | |||
, 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 | |||
' Page ' of | |||
~8-1-7.R4'. - | |||
.. h | |||
\ \^ | |||
The Enorgy Peoplo 95 2189 (20M) I188 S=t}} |
Latest revision as of 16:16, 23 July 2020
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
,
- 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
~
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
<f6 I
ggsaago?35,%2g2 R
m .
'C'
- ' , . OPERATING. DATA REPORT-Docket No.50-272 as, ,
.Date May 10, 1985 y .
Telephone 935-6000 Completed by -J. P. Ronafalvy Extension ~4455 sOperating Status
- 1. Unit Name . .
' Salem No.'1' Notes
- 2. ; Reporting Period : April 1985
- 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 _
100G1) 818610 3243750 37159800 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 5 shutdown at end of Report Period, Estimated Date of Startup:
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
(
p- -- . .
+ . ,
' UNIT' SHUTDOWN AND POWER REDUCTIONS Dockrit No.'50-272' ,
. 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%._
1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 1-Manual Instructions Salem as
~
F: Forced A-Equipment Failure-explain S: Scheduled B-Maintenance or Test 2-Manual. Scram. for Prepara ' Source C-Refueling .
3-Automatic. Scram. tion of Data D-Regulatory.. Restriction 4-Continuation of Entry Sheets 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- (NUREG 0161)-
...m _ _ _ -J
~
' 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 . SUBJE CT 1BC-0743A-. Security Erect a subcontractors' security gatehouse.
1ET-11657 #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 performed,cnl the Unit 2'HP Drains 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
~
(Valve Mark No. . FA-46) . from existing " John Crane 187-I" +
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..
_ _ _._' . . _ , _ s
M v....
- 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.
1SC-0909. 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.
1EC-1948. 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
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1MD-0091 i
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.
1SC-0363: 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.
1SC-1272~ 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 12 S/G STM PRESS CH 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
~
~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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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 t
- 1. Refueling' information has changed from last month:
YES NO X
~ 2.. - 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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i O PSEG 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.
s Average Daily Unit Power Level
, 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