ML20153C704: Difference between revisions

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              ,                  AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.       50-293 UNIT             Pilgrim 1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
                                                              'DATE           February 13, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH   January 1986 DAY   AVERAGE DAILY POWER LEVEL     DAY   AVERAGE DAILY POWER LEVEL (MWe-Net)                               (MWe-Net) 1               667.                 17                     0.
50-293 UNIT Pilgrim 1
2               667.                 18                   112.
'DATE February 13, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH January 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
3               667.                 19                   600.
(MWe-Net) 1 667.
4                 62.                 20                   595.
17 0.
5-                 O.                 21                   668.
2 667.
6                 0.                 22                   670.
18 112.
7               162.                 23                   668.
3 667.
8               497.                 24                   670.
19 600.
9               528.                 25                   668.
4 62.
10               650.                 26                   670.
20 595.
11               669.                 27                   668.
5-O.
12               667.                 28                   668.
21 668.
13               669.                 29                   645.
6 0.
14               669.                 30                   668.
22 670.
15               668                 31                   670.
7 162.
16               635.
23 668.
This format, lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to the nearest whole megawatt-       .
8 497.
8602210518 860131 PDR  ADOCK 0 % p R
24 670.
M
9 528.
                                                      - _ - -_ _ - _ - _ _ -- - - _ _ _ _ _ _ _ _ - _- _ _ _ J/ L _
25 668.
10 650.
26 670.
11 669.
27 668.
12 667.
28 668.
13 669.
29 645.
14 669.
30 668.
15 668 31 670.
16 635.
This format, lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to the nearest whole megawatt-.
8602210518 860131 ADOCK 0 % p PDR R
M J/ L


OPERATING DATA REPORT DOCKET NO.         50-293 DATE           February 13, 1986 COMPLETED BY P. Hamilton TELEPHONE       (617)746-7900 OPERATING STATUS
OPERATING DATA REPORT DOCKET NO.
: 1. Unit Name               Pilgrim 1                         Notes
50-293 DATE February 13, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.
: 2. Reporting Period         January 1986
Unit Name Pilgrim 1 Notes 2.
: 3. Licensed Thermal Power (MWt)             1998
Reporting Period January 1986 3.
: 4. Nameplate Rating (Gross MWe)             678
Licensed Thermal Power (MWt) 1998 4.
: 5. Design Electrical Rating (Net MWe)       655
Nameplate Rating (Gross MWe) 678 5.
: 6. Maximum Dependable Capacity (Gross MWe) 690
Design Electrical Rating (Net MWe) 655 6.
.                    7. Maximum Dependable Capacity (Net MWe)     670
Maximum Dependable Capacity (Gross MWe) 690 7.
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
Maximum Dependable Capacity (Net MWe) 670 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None 9.
Power Level To Which Restricted, If Any (Net MWe)
None
None
: 9. Power Level To Which Restricted, If Any (Net MWe)          None
: 10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative
: 10. Reasons For Restrictions, If Any                             N/A This Month Yr-to-Date Cumulative
: 11. Hours In Reporting Period 744.0 744.0 115248.0
: 11. Hours In Reporting Period                         744.0         744.0     115248.0
: 12. Number Of Hours Reactor Was Critical 655.5 655.5 78731.1
: 12. Number Of Hours Reactor Was Critical               655.5         655.5       78731.1
: 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
: 13. Reactor Reserve Shutdown Hours                       0.0           0.0           0.0
: 14. Hours Generator On-Line 629.0 629.0 76212.3
: 14. Hours Generator On-Line                           629.0         629.0       76212.3
: 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
: 15. Unit Reserve Shutdown Hours                         0.0           0.0           0.0
: 16. Gross Thermal Energy Generated (MWH) 1191408.0 1191408.0 133096872.0
: 16. Gross Thermal Energy Generated (MWH)           1191408.0     1191408.0 133096872.0
: 17. Gross Electrical Energy Generated (MWH) 411960.0 411960.0 44788564.0
: 17. Gross Electrical Energy Generated (MWH)         411960.0     411960.0 44788564.0
: 18. Net Electrical Energy Generated (MWH) 396440.0 396440.0 43044338.0
: 18. Net Electrical Energy Generated (MWH)           396440.0     396440.0 43044338.0
: 19. Unit Service Factor 84.5 84.5 66.1
: 19. Unit Service Factor                                 84.5           84.5           66.1
: 20. Unit Availability Factor 84.5, 84.5 66.1
: 20. Unit Availability Factor                     _
: 21. Unit Capacity Factor (Using MDC Net) 79.5 79.5 55.7
84.5,         84.5           66.1
: 22. Unit Capacity Factor (Using DER Net) 81.4 81.4 57.0
: 21. Unit Capacity Factor (Using MDC Net)               79.5           79.5           55.7
: 23. Unit Forced Outage Rate 7.7 7.7 8.9
: 22. Unit Capacity Factor (Using DER Net)               81.4           81.4           57.0
: 23. Unit Forced Outage Rate                             7.7           7.7           8.9
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None
None
: 25. If Shut Down At End Of Report Period, Estimated Date of Startup                 -
: 25. If Shut Down At End Of Report Period, 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 COMMERCIAL OPERATION (9/77)
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)


b REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 13, 1978:
b REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 13, 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 -
1.
The name of this facility is Pilgrim Nuclear Power Station, Docket Number -
50-293.
50-293.
: 2.         Scheduled date for next Refueling Shutdown:                                                         September 1986
2.
: 3.         Scheduled date for restart following refueling: November 1986
Scheduled date for next Refueling Shutdown:
: 4.         Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6:
September 1986 3.
: 5.         See #6.                                                                                                                                               ,
Scheduled date for restart following refueling: November 1986 4.
!.                  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 P8DRB282 assemblies.       In addition, 32 GE6B-P8DRB282 assemblies were also l                               loaded.
Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6:
: 7.         (a) There are 580 fuel assemblies in the core.
5.
I                               (b) There are 1,128 fuel assemblies in the spent fuel pool.
See #6.
: 8.         (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual spent fuel storage capacity is M1942 fuel assemblies at present.
6.
l                               (b) The planned spent fuel storage capacity is 2320 fuel assemblies.
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 P8DRB282 assemblies.
: 9.       With present spent fuel in storage, the spent fuel pool now has the i                             capacity to accommodate an additional M814 fuel assemblies.
In addition, 32 GE6B-P8DRB282 assemblies were also l
loaded.
7.
(a) There are 580 fuel assemblies in the core.
I (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 M1942 fuel assemblies at present.
l (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 i
capacity to accommodate an additional M814 fuel assemblies.
I I
I I
s i
s i
Line 92: Line 119:
l MFuel pool rerack to 2320 is in progress.
l MFuel pool rerack to 2320 is in progress.


BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for January 1986 The unit was operated at full power until the fourth when a planned shutdown was made to investigate high vibration on the #9 turbine bearing. Subsequent to maintenance activities, including realignment of the exciter, an unplanned scram occurred while starting up. The unit was returned to service on the seventh with satisfactory turbine vibration.
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for January 1986 The unit was operated at full power until the fourth when a planned shutdown was made to investigate high vibration on the #9 turbine bearing. Subsequent to maintenance activities, including realignment of the exciter, an unplanned scram occurred while starting up.
From the eighth through the tenth, reactor power was increased slowly as limited by new and more stringent water chemistry guidelines. Full power was reached on the eleventh and maintained until the sixteenth when a reactor scram occurred due to a false high reactor pressure signal.
The unit was returned to service on the seventh with satisfactory turbine vibration.
The unit was returned to service on the eighteenth and achieved full power on the twentieth. Full power was essentially maintained through the end of the month with the exception of the twenty ninth when a slight power reduction was made to investigate high vibration on the #9 turbine bearing. The vibration problem was quickly resolved.
From the eighth through the tenth, reactor power was increased slowly as limited by new and more stringent water chemistry guidelines.
* An unusual event was declared on the tenth due to a fire at the hydrogen storage tank area. The fire was extinguished within approximately 30 minutes with essentially no injury, damage or loss of generation.
Full power was reached on the eleventh and maintained until the sixteenth when a reactor scram occurred due to a false high reactor pressure signal.
a Safety Relief Valve Challenges Month of January 1986 Requirement: NUREG-0737               T.A.P.               II.K.3.3.
The unit was returned to service on the eighteenth and achieved full power on the twentieth.
Full power was essentially maintained through the end of the month with the exception of the twenty ninth when a slight power reduction was made to investigate high vibration on the #9 turbine bearing.
The vibration problem was quickly resolved.
An unusual event was declared on the tenth due to a fire at the hydrogen storage tank area.
The fire was extinguished within approximately 30 minutes with essentially no injury, damage or loss of generation.
a Safety Relief Valve Challenges Month of January 1986 Requirement: NUREG-0737 T.A.P.
II.K.3.3.
There were no safety relief valve challenges during the month.
There were no safety relief valve challenges during the month.


nonu,_   January, 1986 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM           COMPONENT     MALFUNCTION       CAUSE             MAINTENANCE         TO PREVENT           ASSOCIATED RECURRENCE               LER Turbine         #9 Bearing     High Vibration   Exciter         Realigned Exciter   Increased               N/R Alignment                           Monitoring Reactor         Reactor High   Tripped           Hypersensitive See LER             Revised setpoints         86-002 Protection     Press. Switches                   to Vibration                       & operating           to be issued System         263-SSC50                                                             parameters (See LER 86-002)
January, 1986 nonu,_
Main           Main Steam     Did not meet     faulty           Replaced           Rebuilt each             N/R Steam           Isolation       timing           control valve   control           refueling Valve A0203-10 requirements                       valve             outage HVAC           Isolation       Gears             Worn gear       Changed gears     New dampers on           N/R Secondary       Damper         misaligned                                           order Containment AON-82 9
PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER Turbine
#9 Bearing High Vibration Exciter Realigned Exciter Increased N/R Alignment Monitoring Reactor Reactor High Tripped Hypersensitive See LER Revised setpoints 86-002 Protection Press. Switches to Vibration
& operating to be issued System 263-SSC50 parameters (See LER 86-002)
Main Main Steam Did not meet faulty Replaced Rebuilt each N/R Steam Isolation timing control valve control refueling Valve A0203-10 requirements valve outage HVAC Isolation Gears Worn gear Changed gears New dampers on N/R Secondary Damper misaligned order Containment AON-82 9
9 9
9 9
* O e
O e
9 4
9 4


UNIT SHUTDOWNS AND POWER REDUCTIONS         DOCKET NO.       50-293 UNIT NAME       Pilgrim 1 DATE           2/13/86 COMPLETED BY   P. Hamilton TELEPHONE     (617) 746-7900 REPORT MONTH January       1986 METHOD OF       LICENSE                           CAUSE & CORRECTIVE DURATION               SHUTTING         EVENT       SYSTEM COMPONENT           ACTION TO NO. DATE     TYPEI   (HOURS) REASON 2     DOWN REACTOR 3     REPORT #     CODE 4   CODES     PREVENT RECURRENCE 01   1/4/86     S       62.5       B             1           N/A         TA       EXC             Unit shutdown on 1/4/86 for planned turbine mainten-ance. Realigned exciter to resolve high vibration on
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
                                                                                                                #9 bearing 02   1/6/86     F       14.5       G             3             86--001     N/A       N/A             Unit scrammed while starting up prior to going on line from 1/4/86 outage.
50-293 UNIT NAME Pilgrim 1 DATE 2/13/86 COMPLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH January 1986 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO NO.
See LER for detail 03   1/16/06     F       38.0       A             3             86-002     JC       63             Unit scrammed from 100% power due to false Rx high pressure signal.
DATE TYPEI (HOURS) REASON 2 DOWN REACTOR 3 REPORT #
CODE 4 CODES PREVENT RECURRENCE 01 1/4/86 S
62.5 B
1 N/A TA EXC Unit shutdown on 1/4/86 for planned turbine mainten-ance.
Realigned exciter to resolve high vibration on
#9 bearing 02 1/6/86 F
14.5 G
3 86--001 N/A N/A Unit scrammed while starting up prior to going on line from 1/4/86 outage.
See LER for detail 03 1/16/06 F
38.0 A
3 86-002 JC 63 Unit scrammed from 100% power due to false Rx high pressure signal.
See LER for detail
See LER for detail
                                                                                                                                  ~
~
1             2                       2                 3                 4&5 F-Forced A-Equip Failure             F-Admin         1-fianual           Exhibit F & H S-Sched     B-Maint or Test           G-Oper Error     2-tianual Scram     Instructions for C-Refueling               H-Other         3-Auto Scram       Preparation of a'
1 2
* O-Regulatory Restriction                   4-Continued         Data Entry Sheet E-Operator Training                       5-Reduced Load     Licensee Event Report
2 3
                    & License Examination                   9-Other             (LER) File (NUREG-lO22)
4&5 F-Forced A-Equip Failure F-Admin 1-fianual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-tianual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of a'
O-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report
& License Examination 9-Other (LER) File (NUREG-lO22)


EOSTON EOlBON COMPANY 800 BOVLaTON STREET BOSTON. M AssAcHusETTs 02199 wituAN o. NAmmiNGTON c.....   .. ........e                                                 Y
EOSTON EOlBON COMPANY 800 BOVLaTON STREET BOSTON. M AssAcHusETTs 02199 wituAN o. NAmmiNGTON c.....
    .. 6...                                                        BECo Ltr. #86- 013 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn:     Document Control Desk License No. DPR-35 Docket No. 50-293
..........e Y
BECo Ltr. #86- 013 6...
Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
Document Control Desk License No. DPR-35 Docket No. 50-293


==Subject:==
==Subject:==
Line 121: Line 173:


==Dear Sir:==
==Dear Sir:==
In accordance with PNPS Technical Specification 0.9. 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 0.9. A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.
Respectfully submitted, W
Respectfully submitted, W
W. D. Harrington
W. D. Harrington PJH: caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
* PJH: caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA     19406
/
                                                                                  /
*,I l}}
                                                                                      * ,I l}}

Latest revision as of 03:05, 11 December 2024

Monthly Operating Rept for Jan 1986
ML20153C704
Person / Time
Site: Pilgrim
Issue date: 01/31/1986
From: Hamilton P, Harrington W
BOSTON EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-013, 86-13, NUDOCS 8602210518
Download: ML20153C704 (7)


Text

-

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-293 UNIT Pilgrim 1

'DATE February 13, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 MONTH January 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 667.

17 0.

2 667.

18 112.

3 667.

19 600.

4 62.

20 595.

5-O.

21 668.

6 0.

22 670.

7 162.

23 668.

8 497.

24 670.

9 528.

25 668.

10 650.

26 670.

11 669.

27 668.

12 667.

28 668.

13 669.

29 645.

14 669.

30 668.

15 668 31 670.

16 635.

This format, lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to the nearest whole megawatt-.

8602210518 860131 ADOCK 0 % p PDR R

M J/ L

OPERATING DATA REPORT DOCKET NO.

50-293 DATE February 13, 1986 COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.

Unit Name Pilgrim 1 Notes 2.

Reporting Period January 1986 3.

Licensed Thermal Power (MWt) 1998 4.

Nameplate Rating (Gross MWe) 678 5.

Design Electrical Rating (Net MWe) 655 6.

Maximum Dependable Capacity (Gross MWe) 690 7.

Maximum Dependable Capacity (Net MWe) 670 8.

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

None 9.

Power Level To Which Restricted, If Any (Net MWe)

None

10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative
11. Hours In Reporting Period 744.0 744.0 115248.0
12. Number Of Hours Reactor Was Critical 655.5 655.5 78731.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 629.0 629.0 76212.3
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1191408.0 1191408.0 133096872.0
17. Gross Electrical Energy Generated (MWH) 411960.0 411960.0 44788564.0
18. Net Electrical Energy Generated (MWH) 396440.0 396440.0 43044338.0
19. Unit Service Factor 84.5 84.5 66.1
20. Unit Availability Factor 84.5, 84.5 66.1
21. Unit Capacity Factor (Using MDC Net) 79.5 79.5 55.7
22. Unit Capacity Factor (Using DER Net) 81.4 81.4 57.0
23. Unit Forced Outage Rate 7.7 7.7 8.9
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

b REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 13, 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:

September 1986 3.

Scheduled date for restart following refueling: November 1986 4.

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

5.

See #6.

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 P8DRB282 assemblies.

In addition, 32 GE6B-P8DRB282 assemblies were also l

loaded.

7.

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

I (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 M1942 fuel assemblies at present.

l (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 i

capacity to accommodate an additional M814 fuel assemblies.

I I

s i

,i I

l i

i l

l MFuel pool rerack to 2320 is in progress.

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Operational Summary for January 1986 The unit was operated at full power until the fourth when a planned shutdown was made to investigate high vibration on the #9 turbine bearing. Subsequent to maintenance activities, including realignment of the exciter, an unplanned scram occurred while starting up.

The unit was returned to service on the seventh with satisfactory turbine vibration.

From the eighth through the tenth, reactor power was increased slowly as limited by new and more stringent water chemistry guidelines.

Full power was reached on the eleventh and maintained until the sixteenth when a reactor scram occurred due to a false high reactor pressure signal.

The unit was returned to service on the eighteenth and achieved full power on the twentieth.

Full power was essentially maintained through the end of the month with the exception of the twenty ninth when a slight power reduction was made to investigate high vibration on the #9 turbine bearing.

The vibration problem was quickly resolved.

An unusual event was declared on the tenth due to a fire at the hydrogen storage tank area.

The fire was extinguished within approximately 30 minutes with essentially no injury, damage or loss of generation.

a Safety Relief Valve Challenges Month of January 1986 Requirement: NUREG-0737 T.A.P.

II.K.3.3.

There were no safety relief valve challenges during the month.

January, 1986 nonu,_

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED RECURRENCE LER Turbine

  1. 9 Bearing High Vibration Exciter Realigned Exciter Increased N/R Alignment Monitoring Reactor Reactor High Tripped Hypersensitive See LER Revised setpoints86-002 Protection Press. Switches to Vibration

& operating to be issued System 263-SSC50 parameters (See LER 86-002)

Main Main Steam Did not meet faulty Replaced Rebuilt each N/R Steam Isolation timing control valve control refueling Valve A0203-10 requirements valve outage HVAC Isolation Gears Worn gear Changed gears New dampers on N/R Secondary Damper misaligned order Containment AON-82 9

9 9

O e

9 4

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-293 UNIT NAME Pilgrim 1 DATE 2/13/86 COMPLETED BY P. Hamilton TELEPHONE (617) 746-7900 REPORT MONTH January 1986 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO NO.

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

CODE 4 CODES PREVENT RECURRENCE 01 1/4/86 S

62.5 B

1 N/A TA EXC Unit shutdown on 1/4/86 for planned turbine mainten-ance.

Realigned exciter to resolve high vibration on

  1. 9 bearing 02 1/6/86 F

14.5 G

3 86--001 N/A N/A Unit scrammed while starting up prior to going on line from 1/4/86 outage.

See LER for detail 03 1/16/06 F

38.0 A

3 86-002 JC 63 Unit scrammed from 100% power due to false Rx high pressure signal.

See LER for detail

~

1 2

2 3

4&5 F-Forced A-Equip Failure F-Admin 1-fianual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-tianual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of a'

O-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-lO22)

EOSTON EOlBON COMPANY 800 BOVLaTON STREET BOSTON. M AssAcHusETTs 02199 wituAN o. NAmmiNGTON c.....

..........e Y

BECo Ltr. #86- 013 6...

Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn:

Document Control Desk License No. DPR-35 Docket No. 50-293

Subject:

January 1986 Monthly Report

Dear Sir:

In accordance with PNPS Technical Specification 0.9. A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.

Respectfully submitted, W

W. D. Harrington PJH: caw Attachment cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

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