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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.                         50-293 UNIT                               Pilerim 1 DATE           ., Jay _13.198L COMPLETED BY_f., HamiltoD TELEPHONE _f617)746-7900 NONTH                 April 1995 l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
DAY     AVERAGE DAILY POWER LEVEL                     DAY AVERAGE DAILY POWER LEVEL l                           (MWe-Net)                               (MWe-Net) l
50-293 UNIT Pilerim 1 DATE
!  1                          661.                       17           669, 2                         653.                       le           670.                               _
., Jay _13.198L COMPLETED BY_f., HamiltoD TELEPHONE _f617)746-7900 NONTH April 1995 l
3                         666.                       19           657, 4                         300.                       20           394.                                     __          r 5                           St.                       21           639, 6                         562.         . _ _
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
22           660.
(MWe-Net)
7                         154,                       23           667.
(MWe-Net) l 1
f 8                         595.                       24           630.
661.
9                           654,                       26           667, 10                       660.         _,,
17
26           660.
: 669, 2
11                       669.                       27           660, 12                       6_69.                     20           639.                                 ___
653.
i 13                       669.                       29           (18.                                                 r i
le 670.
14                       667.               _ _ _
3 666.
30           669 15                       669.                       31           N/A 16                       669.                 __
19
: 657, 4
300.
20 394.
r 5
St.
21
: 639, 6
562.
22 660.
7
: 154, 23 667.
f 8
595.
24 630.
9
: 654, 26
: 667, 10 660.
26 660.
11 669.
27
: 660, 12 6_69.
20 639.
i 13 669.
29 (18.
r i
14 667.
30 669 15 669.
31 N/A 16 669.
i.
i.
L99TRUCTIO49 On this format, list the average daily unit power level in MWe-Net for each                                               l day in the reporting month. Compute to the nearest whole megawatt.                                                       ;
L99TRUCTIO49 On this format, list the average daily unit power level in MWe-Net for each l
day in the reporting month. Compute to the nearest whole megawatt.
I 3
I 3
Mql.
Mql.
VI
VI


e OPERATING DATA REPORT DOCKET NO. __  _ 50-293 DATE             May 13.1985; COMPLETED BY     P. Hamilton TELEPHONE         (617)746-7900 OPERATING STATUS
e OPERATING DATA REPORT DOCKET NO.
: 1. Unit Name                 Pilgrim 1                         Notes
_ 50-293 DATE May 13.1985; COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.
: 2. Reporting Period           April 1995
Unit Name Pilgrim 1 Notes 2.
: 3. Licensed Thermal Power (MWt)               1998
Reporting Period April 1995 3.
: 4. Nameplate Rating (Gross MWe)               678
Licensed Thermal Power (MWt) 1998 4.
: 5. Design Electrical Rating (Not MWe)         655
Nameplate Rating (Gross MWe) 678 5.
: 6. Maximum Dependablo Capacity (Gross MWe) 683
Design Electrical Rating (Not MWe) 655 6.
,  7. Maximum Dopondable Capacity (Net MWe)       663
Maximum Dependablo Capacity (Gross MWe) 683 7.
: 8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Roasons:
Maximum Dopondable Capacity (Net MWe) 663 8.
L None
If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Roasons:
: 9. Power Level To Which Restricted, If Any (Not NWo)         None                         ,
L None 9.
: 10. Reasons for Restrictions, If Any                           N/A Ihis Month Yr-to-Date Cumulative
Power Level To Which Restricted, If Any (Not NWo)
: 11. Hours In Reporting Period                         719.0_ ,  2979.0_       108623.0_
None
: 12. Number Of Hours Reactor Was Critical             700.0       2437.0         72348.6
: 10. Reasons for Restrictions, If Any N/A Ihis Month Yr-to-Date Cumulative
: 13. Reactor Reserve Shutdown Hours                     0,0         0.0             0.Q.
: 11. Hours In Reporting Period 719.0_
: 14. Hours Generator On-Line                           681.0       7335,8         69904.3
2979.0_
: 15. Unit Reserve Shutdown Hours                         0,0_
108623.0_
0,0_             0.0_
: 12. Number Of Hours Reactor Was Critical 700.0 2437.0 72348.6
: 16. Gross Thermal Energy Generated (MWH)         L299816,0, 4134170.0_ 171085979.0
: 13. Reactor Reserve Shutdown Hours 0,0 0.0 0.Q.
: 17. Gross Electrical Energy Generated (MWH)       _449570.0_ 14215501 0, 40653764,0
: 14. Hours Generator On-Line 681.0 7335,8 69904.3
: 18. Not Electrical Energy Generated (MWH)         437756.0_ 1)66700,0 _39063635.0
: 15. Unit Reserve Shutdown Hours 0,0_
: 19. Unit Service Factor                               94.f_       81.1_             6413
0,0_
: 20. Unit Availability factor                           94.7         91.1 _           64.4
0.0_
: 21. Unit Capacity factor (Using MDC Net)               902 8,       71,6             54,2
: 16. Gross Thermal Energy Generated (MWH)
: 22. Unit Capacity factor (Using DER Not)               91.9         72,5             54.9
L299816,0, 4134170.0_ 171085979.0
: 23. Unit forced Outage Rate                             513_        ll22,              99 1
: 17. Gross Electrical Energy Generated (MWH)
_449570.0_ 1421550 0, 40653764,0 1
: 18. Not Electrical Energy Generated (MWH) 437756.0_
1)66700,0 _39063635.0
: 19. Unit Service Factor 94.f_
81.1_
: 20. Unit Availability factor 94.7 91.1 _
64 3 1
64.4
: 21. Unit Capacity factor (Using MDC Net) 90 8, 71,6 54,2 2
: 22. Unit Capacity factor (Using DER Not) 91.9 72,5 54.9 5 3_
: ll22,
: 23. Unit forced Outage Rate 99 1
1
: 24. Shutdowns Scheduled Over Nost 6 Months (Type, Date, and Duration of Each):
: 24. Shutdowns Scheduled Over Nost 6 Months (Type, Date, and Duration of Each):
Mon.
Mon.
: 25. If Shut Down At End Of Report Porlod, Estimated Date of Startup                 -
: 25. If Shut Down At End Of Report Porlod, Estimated Date of Startup
: 26. Units In Test Status (Prior to Commercial Operation):
: 26. Units In Test Status (Prior to Commercial Operation):
forecast       Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COPMERCIAL OPERAIION (9/77)
forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COPMERCIAL OPERAIION (9/77)


REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to DECO, dated January 18, 1978:
REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to DECO, dated January 18, 1978:
For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.
For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.
: 1. The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293,
1.
: 2. Scheduled date for next Refueling Shutdown:     August 1986
The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293, 2.
: 3. Geheduled date for restart following refueling: November 1986 4.
Scheduled date for next Refueling Shutdown:
: 5. Due to their similarity, requests 4, 5, & 6 are responded to collectively:
August 1986 3.
: 6. The new fuel, which was loaded during the 1983-84 refueling outage, is of the same P8x8R design, as loaded the previous outage and consists of 160 P90R8202 assemblies. In addition, 32 GE68-P80RB282 assemblies were also loaded.
Geheduled date for restart following refueling: November 1986 4.
: 7. (a) There are 580 fuel assemblies in the core.
5.
Due to their similarity, requests 4, 5, & 6 are responded to collectively:
6.
The new fuel, which was loaded during the 1983-84 refueling outage, is of the same P8x8R design, as loaded the previous outage and consists of 160 P90R8202 assemblies.
In addition, 32 GE68-P80RB282 assemblies were also loaded.
7.
(a) There are 580 fuel assemblies in the core.
(b) There are 1,128 fuel assemblies in the spent fuel pool.
(b) There are 1,128 fuel assemblies in the spent fuel pool.
: 8. (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual spent fuel storage capacity is 17/0 fuel assemblies at present.
8.
(a) The station is presently licensed to store 2320 spent fuel assemblies. The actual spent fuel storage capacity is 17/0 fuel assemblies at present.
(b) The planned spent fuel storage capacity is 2320 fuel assemblies.
(b) The planned spent fuel storage capacity is 2320 fuel assemblies.
: 9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 642 fuel assemblies.
9.
With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 642 fuel assemblies.
-m


BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION 00CNET NO. 50-293                           !
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION 00CNET NO. 50-293 Oserational Summarv for April 1985 The month' commenced with the unit operating at 100% power until the fourth when a reactor scram occurred as the result of a turbine high vibration signal (Ref.: LER 85-009)..After satisfactory completion of turbine vibration detection equipment repairs, the unit was returned to service on the fifth.
Oserational Summarv for April 1985 The month' commenced with the unit operating at 100% power until the fourth     !
On the seventh, the turbine was removed from the grid at 0352 hours to investigate a Hi/Lo oil level alarm on the "B" recirculation pump motor, repair a reactor water sample system valve (A0-220-44), and investigate a
when a reactor scram occurred as the result of a turbine high vibration signal !
(
(Ref.: LER 85-009). .After satisfactory completion of turbine vibration detection equipment repairs, the unit was returned to service on the fifth.
turbine high vibration alarm (#9 bearing).
On the seventh, the turbine was removed from the grid at 0352 hours to         !
After successful completion of L
investigate a Hi/Lo oil level alarm on the "B" recirculation pump motor,     !
these tasks, the unit was synchronized to the grid on the same day (seventh) t at approximately 1740 hours.
repair a reactor water sample system valve (A0-220-44), and investigate a     (
An average daily power level of 100% was achieved on the tenth and essentially maintained until the twentieth when power was reduced to backwash and heat treet the main condenser. Full power was achieved on the twenty-first and maintained through the end of the month, with the exception of the
turbine high vibration alarm (#9 bearing). After successful completion of     L these tasks, the unit was synchronized to the grid on the same day (seventh)   t at approximately 1740 hours.
[
An average daily power level of 100% was achieved on the tenth and essentially maintained until the twentieth when power was reduced to backwash and heat treet the main condenser. Full power was achieved on the twenty-first and     .
maintained through the end of the month, with the exception of the             [
twenty-eighth when a slight power reduction was made to backwash the main condenser.
twenty-eighth when a slight power reduction was made to backwash the main condenser.
Safety Relief Valve Challenges Month of April 1995 Requirement: NUREG-0737             T.A.P.               II.N.3.3 I
Safety Relief Valve Challenges Month of April 1995 Requirement: NUREG-0737 T.A.P.
II.N.3.3 I
There were no safety relief valve challenges during the month.
There were no safety relief valve challenges during the month.
l l
l l
4 L
4 L
  . _______._m___._
. m


UNIT SHUTD0kmS AND P0hER REDUCTIONS                                 DOCKET ND.         50-293 UNIT NAFE         Pilerim 1 DATE               May 13, 1985 COWLETED BY       P. Hamilton TELEPHONE         (617) 746-7900 REPORT MONTH             April 1985 METHOD OF                 LICENSE                                           CAUSE & CORRECTIVE DURATION                             SHUTTING                   EVENT             SYSTER CONONENT                     ACTION TO ND. DATE     TYPEI                 (HOURS) REASON 2                   D0hWI REACTOR 3             REPORT #             CODE 4         CODES       PREVENT RECURRENCE 10   4/4/85       F                   27.0                     A                 3             85-009                   JJ             DET       Rx scram on turbine high vibration signal due to inadequate-wibration detector lubrication. Restored L.O. flow to detector and replaced detector.
UNIT SHUTD0kmS AND P0hER REDUCTIONS DOCKET ND.
11   4/7/85       F                   11.0                     H                 I             N/A                     ZZ             N/A       Shutdown to check "B" RFP Hi/Lo oil alarm and turbine high wibration alarm.
50-293 UNIT NAFE Pilerim 1 DATE May 13, 1985 COWLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH April 1985 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTER CONONENT ACTION TO ND.
12   4/20/85       S                   0.0                     H                 1             N/A                     ZZ             N/A       Reduced power for heat treating and condenser backwash.
DATE TYPEI (HOURS) REASON 2 D0hWI REACTOR 3 REPORT #
1               2                                               2                         3                           4&5 I
CODE 4 CODES PREVENT RECURRENCE 10 4/4/85 F
j               F-Forced A-Equip Failure                                         F-Admin             1-Manual                         Exhibit F & H L
27.0 A
S-Sched     B-Maint or Test                                       G-Oper Error         2-Manual Scram                   Instructions for C-Refueling                                           H-Other             3-Auto Scram                     Preparation of D-Regulatory Restriction                                                   4-Continued                     Data Entry Sheet E-Operator Training                                                       5-Reduced Load                   Licensee Event Report
3 85-009 JJ DET Rx scram on turbine high vibration signal due to inadequate-wibration detector lubrication. Restored L.O. flow to detector and replaced detector.
            ,                & License Examination                                                   9-Other                         (LER) File (NUREG-1022)
11 4/7/85 F
                                          . , _ - . ~         ~ - - - ,__ _ _.                            _ .. _ .      _ _ _ - _ - -            - _ _ .                _- _        --    ..
11.0 H
I N/A ZZ N/A Shutdown to check "B" RFP Hi/Lo oil alarm and turbine high wibration alarm.
12 4/20/85 S
0.0 H
1 N/A ZZ N/A Reduced power for heat treating and condenser backwash.
1 2
2 3
4&5 I
j F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H L
S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for l
C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report
& License Examination 9-Other (LER) File (NUREG-1022)
., _ -. ~
~ - - -,__ _ _.


1 Month     April 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM   COMPONENT     MALFUNCTION       CAUSE           MAINTENANCE         TO PREVENT         ASSOCIATED RECURRENCE           LER HPCI       Connector     Overspeed         Faulty         Replaced connector. N/R                   85-008 on EG/R       Trip                                                                                     j HPCI       Rupture       Ruptured         Age             Replaced rupture     N/R                   85-008 Disc, PSD-68                                   disc.
1 Month April 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER HPCI Connector Overspeed Faulty Replaced connector.
HPCI       HPCI Turbine Broken Snubber   Suspected       Rebuilt snubber. Increased             85-008 Steam Exhaust Shaft             Water Hammer   Tested the           frequency and                     ;
N/R 85-008 on EG/R Trip j
Line Snubber                   (Engineering   " mating" snubber   duration of the                   )
HPCI Rupture Ruptured Age Replaced rupture N/R 85-008 Disc, PSD-68 disc.
Review in       satisfactorily.     exhaust line                     l Progress)                           purging.                         1 Surveillance of line after each operation.
HPCI HPCI Turbine Broken Snubber Suspected Rebuilt snubber.
HPCI       PS-2389A     Would Not Trip   Balance Level   Cleaned and         Routine surveillance. N/R Low Pressure                   Binding         lubricated lever -   Switch to be Isolation                                       Recalibrated to     replaced during Switch                                         correct setpoint. EQ project.
Increased 85-008 Steam Exhaust Shaft Water Hammer Tested the frequency and Line Snubber (Engineering
Turbine   Vibration     Faulty           Obstructed     Replaced detector   N/R                   85-009 Detector                       Lube Oil       and cleaned lube Orifice         oil orifice &
" mating" snubber duration of the
)
Review in satisfactorily.
exhaust line l
Progress) purging.
1 Surveillance of line after each operation.
HPCI PS-2389A Would Not Trip Balance Level Cleaned and Routine surveillance. N/R Low Pressure Binding lubricated lever -
Switch to be Isolation Recalibrated to replaced during Switch correct setpoint.
EQ project.
Turbine Vibration Faulty Obstructed Replaced detector N/R 85-009 Detector Lube Oil and cleaned lube Orifice oil orifice &
flushed line.
flushed line.
Secondary Dampers       Inoperable       Faulty Gears   Replaced gears.     Plan to replace       85-010 Cont.     AON-82 & 83                                                         dampers.
Secondary Dampers Inoperable Faulty Gears Replaced gears.
    . Isol.                                                                           Increased surveillance frequency.
Plan to replace 85-010 Cont.
AON-82 & 83 dampers.
. Isol.
Increased surveillance frequency.


                                                                                                                        ' Month     April 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM       COMPONENT                 MALFUNCTION           CAUSE           MAINTENANCE               TO PREVENT         ASSOCIATED RECURRENCE-           LER PCIS           PS-261-23A               Setpoint Drift     Unknown           Re-calibrated           Routine                   N/R switch.                 surveillance.
' Month April 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE-LER PCIS PS-261-23A Setpoint Drift Unknown Re-calibrated Routine N/R switch.
surveillance.
Switch to be
Switch to be
                                                                                          /-                             replaced during-
/-
                                                                                                                      ; EQ project.
replaced during-
N/R -- Routine
; EQ project.
                                                                                                                  ~
Diesel "B" Diesel Loose Fuel Oil Worn Replaced belt as y N/R -- Routine N/R
Diesel         "B" Diesel               Loose Fuel Oil     Worn               Replaced belt as y                               N/R Gen.           F.O. Belt                 Pump Drive Belt                       preventive             Maintenance maintenance.             '
~
Rx Water       AO-220-44                 Inoperable         Did not meet     Replaced solenoid.     N/R                       N/R Sample                 -  ..
Gen.
closure time.                                                           ~ .
F.O. Belt Pump Drive Belt preventive Maintenance maintenance.
System                         -
Rx Water AO-220-44 Inoperable Did not meet Replaced solenoid.
r                                                                                             1 Post-         1001-606A     s
N/R N/R Sample closure time.
                                                    ~
~
Bad Power Supply Unknown             Replaced power         Routine. calibration     N/R                   '
System 1
Accident                     '
r Post-1001-606A Bad Power Supply Unknown Replaced power Routine. calibration N/R s
Accident
~
supply; recalibrated once/ cycle.
supply; recalibrated once/ cycle.
F.or:itoring                                                                   drawer.
F.or:itoring drawer.
4 4
4 4
_-..---_.--_--.A__.___-__----                         ____    _
_-..---_.--_--.A__.___-__----


D                 -/
D
M-x y
-/
J t                    BOSTON EDISON COMPANY B00 BOYLSTON STREET BasTON, MAaBACHUS ETTE O2199 WILUAM D. HARRINGTON seweenwees ensessaut enom May 13,1985 BECo Ltr. #85- 086 Director Office of Inspection and Enforcement _
M-x J
U.S. Nuclear Regulatory Commission Washington, D.C.         20555 Attn: Document Control DesN License No. DPR-35 Docket No. 50-293
y BOSTON EDISON COMPANY t
B00 BOYLSTON STREET BasTON, MAaBACHUS ETTE O2199 WILUAM D. HARRINGTON seweenwees ensessaut enom May 13,1985 BECo Ltr. #85- 086 Director Office of Inspection and Enforcement _
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn: Document Control DesN License No. DPR-35 Docket No. 50-293


==Subject:==
==Subject:==
Line 145: Line 226:


==Dear Sir:==
==Dear Sir:==
In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.
In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.
1                           i Respectfully submitted,
1 i
(
(
W         D l                                                                         W. D. Harrington s
Respectfully submitted, W
i f                 : caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA   19406 SE3+
D l
                                                                                                        'Io}}
W. D. Harrington s
i f
: caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SE3+
'Io
__}}

Latest revision as of 15:00, 12 December 2024

Monthly Operating Rept for Apr 1985
ML20128A940
Person / Time
Site: Pilgrim
Issue date: 04/30/1985
From: Hamilton P, Harrington W
BOSTON EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-086, 85-86, NUDOCS 8505240369
Download: ML20128A940 (8)
v • d • e


Text

_ _ _ _ _ _

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-293 UNIT Pilerim 1 DATE

., Jay _13.198L COMPLETED BY_f., HamiltoD TELEPHONE _f617)746-7900 NONTH April 1995 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net) l 1

661.

17

669, 2

653.

le 670.

3 666.

19

657, 4

300.

20 394.

r 5

St.

21

639, 6

562.

22 660.

7

154, 23 667.

f 8

595.

24 630.

9

654, 26
667, 10 660.

26 660.

11 669.

27

660, 12 6_69.

20 639.

i 13 669.

29 (18.

r i

14 667.

30 669 15 669.

31 N/A 16 669.

i.

L99TRUCTIO49 On this format, list the average daily unit power level in MWe-Net for each l

day in the reporting month. Compute to the nearest whole megawatt.

I 3

Mql.

VI

e OPERATING DATA REPORT DOCKET NO.

_ 50-293 DATE May 13.1985; COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.

Unit Name Pilgrim 1 Notes 2.

Reporting Period April 1995 3.

Licensed Thermal Power (MWt) 1998 4.

Nameplate Rating (Gross MWe) 678 5.

Design Electrical Rating (Not MWe) 655 6.

Maximum Dependablo Capacity (Gross MWe) 683 7.

Maximum Dopondable Capacity (Net MWe) 663 8.

If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Roasons:

L None 9.

Power Level To Which Restricted, If Any (Not NWo)

None

10. Reasons for Restrictions, If Any N/A Ihis Month Yr-to-Date Cumulative
11. Hours In Reporting Period 719.0_

2979.0_

108623.0_

12. Number Of Hours Reactor Was Critical 700.0 2437.0 72348.6
13. Reactor Reserve Shutdown Hours 0,0 0.0 0.Q.
14. Hours Generator On-Line 681.0 7335,8 69904.3
15. Unit Reserve Shutdown Hours 0,0_

0,0_

0.0_

16. Gross Thermal Energy Generated (MWH)

L299816,0, 4134170.0_ 171085979.0

17. Gross Electrical Energy Generated (MWH)

_449570.0_ 1421550 0, 40653764,0 1

18. Not Electrical Energy Generated (MWH) 437756.0_

1)66700,0 _39063635.0

19. Unit Service Factor 94.f_

81.1_

20. Unit Availability factor 94.7 91.1 _

64 3 1

64.4

21. Unit Capacity factor (Using MDC Net) 90 8, 71,6 54,2 2
22. Unit Capacity factor (Using DER Not) 91.9 72,5 54.9 5 3_
ll22,
23. Unit forced Outage Rate 99 1

1

24. Shutdowns Scheduled Over Nost 6 Months (Type, Date, and Duration of Each):

Mon.

25. If Shut Down At End Of Report Porlod, Estimated Date of Startup
26. Units In Test Status (Prior to Commercial Operation):

forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COPMERCIAL OPERAIION (9/77)

REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to DECO, dated January 18, 1978:

For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.

1.

The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293, 2.

Scheduled date for next Refueling Shutdown:

August 1986 3.

Geheduled date for restart following refueling: November 1986 4.

5.

Due to their similarity, requests 4, 5, & 6 are responded to collectively:

6.

The new fuel, which was loaded during the 1983-84 refueling outage, is of the same P8x8R design, as loaded the previous outage and consists of 160 P90R8202 assemblies.

In addition, 32 GE68-P80RB282 assemblies were also loaded.

7.

(a) There are 580 fuel assemblies in the core.

(b) There are 1,128 fuel assemblies in the spent fuel pool.

8.

(a) The station is presently licensed to store 2320 spent fuel assemblies. The actual spent fuel storage capacity is 17/0 fuel assemblies at present.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 642 fuel assemblies.

-m

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION 00CNET NO. 50-293 Oserational Summarv for April 1985 The month' commenced with the unit operating at 100% power until the fourth when a reactor scram occurred as the result of a turbine high vibration signal (Ref.: LER 85-009)..After satisfactory completion of turbine vibration detection equipment repairs, the unit was returned to service on the fifth.

On the seventh, the turbine was removed from the grid at 0352 hours0.00407 days <br />0.0978 hours <br />5.820106e-4 weeks <br />1.33936e-4 months <br /> to investigate a Hi/Lo oil level alarm on the "B" recirculation pump motor, repair a reactor water sample system valve (A0-220-44), and investigate a

(

turbine high vibration alarm (#9 bearing).

After successful completion of L

these tasks, the unit was synchronized to the grid on the same day (seventh) t at approximately 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />.

An average daily power level of 100% was achieved on the tenth and essentially maintained until the twentieth when power was reduced to backwash and heat treet the main condenser. Full power was achieved on the twenty-first and maintained through the end of the month, with the exception of the

[

twenty-eighth when a slight power reduction was made to backwash the main condenser.

Safety Relief Valve Challenges Month of April 1995 Requirement: NUREG-0737 T.A.P.

II.N.3.3 I

There were no safety relief valve challenges during the month.

l l

4 L

. m

UNIT SHUTD0kmS AND P0hER REDUCTIONS DOCKET ND.

50-293 UNIT NAFE Pilerim 1 DATE May 13, 1985 COWLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH April 1985 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTER CONONENT ACTION TO ND.

DATE TYPEI (HOURS) REASON 2 D0hWI REACTOR 3 REPORT #

CODE 4 CODES PREVENT RECURRENCE 10 4/4/85 F

27.0 A

3 85-009 JJ DET Rx scram on turbine high vibration signal due to inadequate-wibration detector lubrication. Restored L.O. flow to detector and replaced detector.

11 4/7/85 F

11.0 H

I N/A ZZ N/A Shutdown to check "B" RFP Hi/Lo oil alarm and turbine high wibration alarm.

12 4/20/85 S

0.0 H

1 N/A ZZ N/A Reduced power for heat treating and condenser backwash.

1 2

2 3

4&5 I

j F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H L

S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for l

C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-1022)

., _ -. ~

~ - - -,__ _ _.

1 Month April 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER HPCI Connector Overspeed Faulty Replaced connector.

N/R 85-008 on EG/R Trip j

HPCI Rupture Ruptured Age Replaced rupture N/R 85-008 Disc, PSD-68 disc.

HPCI HPCI Turbine Broken Snubber Suspected Rebuilt snubber.

Increased 85-008 Steam Exhaust Shaft Water Hammer Tested the frequency and Line Snubber (Engineering

" mating" snubber duration of the

)

Review in satisfactorily.

exhaust line l

Progress) purging.

1 Surveillance of line after each operation.

HPCI PS-2389A Would Not Trip Balance Level Cleaned and Routine surveillance. N/R Low Pressure Binding lubricated lever -

Switch to be Isolation Recalibrated to replaced during Switch correct setpoint.

EQ project.

Turbine Vibration Faulty Obstructed Replaced detector N/R 85-009 Detector Lube Oil and cleaned lube Orifice oil orifice &

flushed line.

Secondary Dampers Inoperable Faulty Gears Replaced gears.

Plan to replace 85-010 Cont.

AON-82 & 83 dampers.

. Isol.

Increased surveillance frequency.

' Month April 1985 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE-LER PCIS PS-261-23A Setpoint Drift Unknown Re-calibrated Routine N/R switch.

surveillance.

Switch to be

/-

replaced during-

EQ project.

Diesel "B" Diesel Loose Fuel Oil Worn Replaced belt as y N/R -- Routine N/R

~

Gen.

F.O. Belt Pump Drive Belt preventive Maintenance maintenance.

Rx Water AO-220-44 Inoperable Did not meet Replaced solenoid.

N/R N/R Sample closure time.

~

System 1

r Post-1001-606A Bad Power Supply Unknown Replaced power Routine. calibration N/R s

Accident

~

supply; recalibrated once/ cycle.

F.or:itoring drawer.

4 4

_-..---_.--_--.A__.___-__----

D

-/

M-x J

y BOSTON EDISON COMPANY t

B00 BOYLSTON STREET BasTON, MAaBACHUS ETTE O2199 WILUAM D. HARRINGTON seweenwees ensessaut enom May 13,1985 BECo Ltr. #85- 086 Director Office of Inspection and Enforcement _

U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn: Document Control DesN License No. DPR-35 Docket No. 50-293

Subject:

April 1985 honthly Report i

Dear Sir:

In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.

1 i

(

Respectfully submitted, W

D l

W. D. Harrington s

i f

caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SE3+

'Io

__

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