ML20116L084: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:
=Text=
=Text=
{{#Wiki_filter:,
{{#Wiki_filter:,
Tech. Sp:c. 6.9.A.2 Boston Edison                                               :
Tech. Sp:c. 6.9.A.2 Boston Edison Pilgrim Nuclear Power Station f
Pilgrim Nuclear Power Station                                 f Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier Vice President Nuclear Operations                               August 14, 1996                       ,
Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier Vice President Nuclear Operations August 14, 1996 and station oirector BECo Ltr. #96-074 U.S. Nuclear Regulatory Commission Attention: Document Control Desk j
and station oirector                                         BECo Ltr. #96-074 U.S. Nuclear Regulatory Commission Attention: Document Control Desk                                                                     j Washington, DC 20555 Docket No. 50-293 License No. DPR-35 l
Washington, DC 20555 Docket No. 50-293 License No. DPR-35 l
JULY 1996 MONTHLY REPORT in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and     l planning. Should you have any questions conceming this report, please contact me directly.           ;
JULY 1996 MONTHLY REPORT in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and l
                                                                              ,      'o   s
planning. Should you have any questions conceming this report, please contact me directly.
'o s
[ Olivia' i
[ Olivia' i
RLC/dmc/9458 Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
RLC/dmc/9458 Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
      - Senior Resident inspector                                                                           j N
- Senior Resident inspector j
                                                                                                    <m/
N
                                                                                                'p 9608160097 960731 PDR         ADOCK 05000293 R                             PDR                                                               g 160021
<m/
'p 9608160097 960731 PDR ADOCK 05000293 R
PDR g
160021


OPERATING DATA REPORT DOCKET NO.             50-293 NAME:                   Pilorim             !
OPERATING DATA REPORT DOCKET NO.
COMPLETED BY:           R.L. Cannon         I TELEPHONE:             (508) 830-8321 REPORT MONTH           July 1996 OPERAt TING STATUS                                                       NOTES
50-293 NAME:
: 1.       Unit Name                                                     Pilgrim 1
Pilorim COMPLETED BY:
: 2.       Reporting Period                                             July 1996
R.L. Cannon TELEPHONE:
: 3.       Licensed Thermal Power (MWt)                                 1998
(508) 830-8321 REPORT MONTH July 1996 OPERA TING STATUS NOTES t
: 4.       Nameplate Rating (Gross MWe)                                   678
1.
: 5.       Design Electrical Rating (Net MWe)                             655
Unit Name Pilgrim 1 2.
: 6.       Maximum Dependable Capacity (Gross MWe)                         696
Reporting Period July 1996 3.
: 7.       Maximum Dependable Capacity (Net MWe)                           670
Licensed Thermal Power (MWt) 1998 4.
: 8.       If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons:
Nameplate Rating (Gross MWe) 678 5.
No Chanoes
Design Electrical Rating (Net MWe) 655 6.
: 9.       Power Level To Which Restricted, if Any (Net MWe): None
Maximum Dependable Capacity (Gross MWe) 696 7.
  -10.       Reasons For Restrictions, if Any: N/A This Month       Yr-to-Date       Cumulative
Maximum Dependable Capacity (Net MWe) 670 8.
: 11.       Hours in Reporting Period                               744.0           5111.0           207263.0
If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons:
: 12.       Hours Reactor Critical                                   744.0           4996.5           131262.6
No Chanoes 9.
: 13.       Hours Reactor Reserve Shutdown                             0.0               0.0               0.0
Power Level To Which Restricted, if Any (Net MWe): None
: 14.       Hours Generator On-Line                                 744.0           4977.9           126801.8 I
-10.
: 15.       Hours Unit Reserve Shutdown                               0.0               0.0               0.0 l
Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumulative 11.
: 16.       Gross Thermal Energy Generated (MWH)                 1455474.0       9704482.0         226006652.0 ,
Hours in Reporting Period 744.0 5111.0 207263.0 12.
: 17.       Gross Electrical Energy Generated (MWH)               493700.0       3323460.0         76600784.0 ;
Hours Reactor Critical 744.0 4996.5 131262.6 13.
: 18.       Net Electrical Energy Generated (MWH)                 474818.0       3202360.0         73645982.0 l
Hours Reactor Reserve Shutdown 0.0 0.0 0.0 14.
: 19. -     Unit Service Factor                                     100.0               97.4             61.2 '
Hours Generator On-Line 744.0 4977.9 126801.8 15.
: 20.       Unit Availability Factor                                 100.0               97.4             61.2
Hours Unit Reserve Shutdown 0.0 0.0 0.0 16.
: 21.       Unit Capacity Factor (Using MDC Net)                     95.3               93.5             53.0
Gross Thermal Energy Generated (MWH) 1455474.0 9704482.0 226006652.0 17.
: 22.       Unit Capacity Factor (Using DER Net)                     97.4               95.7             54.2
Gross Electrical Energy Generated (MWH) 493700.0 3323460.0 76600784.0 18.
: 23.       Unit Forced Outage Rate                                   0.0               0.0               11.6
Net Electrical Energy Generated (MWH) 474818.0 3202360.0 73645982.0 l
: 24.       Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-               NONE PLANNED
: 19. -
: 25.       If Shutdown at End of Report Period, Estimated Date of Startup-                       UNIT OPERATING l
Unit Service Factor 100.0 97.4 61.2 20.
Unit Availability Factor 100.0 97.4 61.2 21.
Unit Capacity Factor (Using MDC Net) 95.3 93.5 53.0 22.
Unit Capacity Factor (Using DER Net) 97.4 95.7 54.2 23.
Unit Forced Outage Rate 0.0 0.0 11.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-
NONE PLANNED 25.
If Shutdown at End of Report Period, Estimated Date of Startup-UNIT OPERATING l


l l                                          AVERAGE DAILY UNIT POWER LEVEL 1
l AVERAGE DAILY UNIT POWER LEVEL 1
l l                                                                        DOCKET NO.             50-293               l i                                                                         NAME:                   Pilarim               l COMPLETED BY:           R.L. Cannon         )
l DOCKET NO.
TELEPHONE:             (508) 830-8321       J l                                                                         REPORT MONTH           July 1996 DAY       AVERAGE DAILY POWER LEVEL               DAY       AVERAGE DAILY POWER LEVEL l                                 (MWe-Net)                                             (MWe-Net) l l
50-293 i
1                     650                       17                       662 l                 2                     652                       18                       661
NAME:
!                3                      649                       19                       661 l
Pilarim COMPLETED BY:
4                     649                       20                       661 5                     648                       21                       660 l                 6                     649                       22                       660 l
R.L. Cannon
l                 7                     646                       23                       660                       i I
)
8                     647                       24                       658 9                     647                       25                       659 10                     645                       26                       657 11                     645                       27                       658 12                     597                       28                       657 l
TELEPHONE:
I 13                     231                       29                       658 14                     626                       30                       656 15                     662                       31                       657 16                     657
(508) 830-8321 J
:      This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to tha nearest whole megawatt.
l REPORT MONTH July 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net)
(MWe-Net) l l
1 650 17 662 l
2 652 18 661 3
649 19 661 l
4 649 20 661 5
648 21 660 l
6 649 22 660 l
l 7
646 23 660 i
8 647 24 658 9
647 25 659 10 645 26 657 11 645 27 658 12 597 28 657 l
I 13 231 29 658 14 626 30 656 15 662 31 657 16 657 This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to tha nearest whole megawatt.
I 4
I 4
'l
'l
~__                                                                                                                  -
~


                                                                                                                                )
)
OPERATIONAL  
OPERATIONAL  


==SUMMARY==
==SUMMARY==
 
DOCKET NO.
DOCKET NO.         50-293 NAME:             Pilarim COMPLETED BY:     R.L. Cannon TELEPHONE:       (508) 830-8321 REPORT MONTH       July 1996 The unit started the reporting period at 100% core thermal power (CTP) where it was maintained until 2022 hours on July 12,1996. At that time, reactor power was reduced to approximately 50% CTP in supoort of a                     i backwash of the main condenser. During the downpower it was identified that one of the reactor feed flow                     1 indicators was not tracking properly. The flow indicator was replaced and a reactor heat balance was                         j satisfactorily performed. At 1924 hours on July 13,1996, power ascension to 100% CTP commenced. At                           '
50-293 NAME:
0536 hours on July 14, 1996, 100 % CTP was achieved and was maintained for the remainder of the                             ]
Pilarim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 830-8321 REPORT MONTH July 1996 The unit started the reporting period at 100% core thermal power (CTP) where it was maintained until 2022 hours on July 12,1996. At that time, reactor power was reduced to approximately 50% CTP in supoort of a i
backwash of the main condenser. During the downpower it was identified that one of the reactor feed flow indicators was not tracking properly. The flow indicator was replaced and a reactor heat balance was j
satisfactorily performed. At 1924 hours on July 13,1996, power ascension to 100% CTP commenced. At 0536 hours on July 14, 1996, 100 % CTP was achieved and was maintained for the remainder of the
]
reporting period.
reporting period.
J SAFETY RELIEF VALVE CHALLENGES                                                           i MONTH OF JULY 1996 Requirement:         NUREG-0737 T.A.P. II.K.3.3 Thsre were no safety relief valve challenges during the reporting period.
J SAFETY RELIEF VALVE CHALLENGES i
MONTH OF JULY 1996 Requirement:
NUREG-0737 T.A.P. II.K.3.3 Thsre were no safety relief valve challenges during the reporting period.
An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo L tr. #81-01 dated January 5,1981.
An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo L tr. #81-01 dated January 5,1981.
l i
l i
                                                                                            . _ , _        _ . _ , - , . , , 4
4


          ,                                          REFUELING INFORMATION l                                                                         DOCKET NO.             50-293 NAME:                   Pilorim COMPLETED BY:           R.L. Cannon TELEPHONE:             (508) 830-8321 l                                                                         REPORT MONTH           July 1996 Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, d;.t;d January 18,1978:
REFUELING INFORMATION l
DOCKET NO.
50-293 NAME:
Pilorim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 830-8321 l
REPORT MONTH July 1996 Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, d;.t;d 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: February 1,1997.                                         l
The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.
: 3.       Scheduled date for restart following next refueling: March 14,1997.
2.
: 4.       Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6.
Scheduled date for next refueling shutdown: February 1,1997.
: 5.       See #6.
l 3.
: 6.       The new fuelloaded during the 1995 refueling outage (RFO-10)is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.                     >
Scheduled date for restart following next refueling: March 14,1997.
: 7.       (a)     There are 580 fuel assemblies in the core.
4.
(b)     There are 1765 fuel assemblies in the spent fuel pool.                                       1
Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6.
: 8.       (a)     The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.
5.
(b)     The planned spent fuel storage capacity is 3859 fuel assemblies.
See #6.
: 9.       With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.
6.
The new fuelloaded during the 1995 refueling outage (RFO-10)is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.
7.
(a)
There are 580 fuel assemblies in the core.
(b)
There are 1765 fuel assemblies in the spent fuel pool.
1 8.
(a)
The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.
(b)
The planned spent fuel storage capacity is 3859 fuel assemblies.
9.
With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.
l I
l I
i
i


PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE DOCKET NO. 50-293         -
PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE DOCKET NO.
NAME-         Pilarim COMPLETED BY: R.L. Cannon     .
50-293 NAME-Pilarim COMPLETED BY:
TELEPHONE:   (508) 830-8321 REPORT MONTH   July 1996 SYSTEM               COMPONENT       MALFUNCTION                 CAUSE                                                                                                     MAINTENANCE                                 CORRECTIVE           ASSOCIATED ACTION TO           LER PREVENT RECURRENCE No major safety related maintenance was completed during this reporting period.
R.L. Cannon TELEPHONE:
(508) 830-8321 REPORT MONTH July 1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE No major safety related maintenance was completed during this reporting period.
4 1
4 1


UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.                                                                               50-293         -
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
NAME:                                                                                   Pilorim COMPLETED BY:                                                                             R.L. Cannon       .
50-293 NAME:
TELEPHONE:                                                                               (508) 83 4 8321 REPORT MONTH                                                                             July 1996 METHOD OF                                                                                             LICENSE               SYSTEM   COMPONENT             CAUSE & CORRECTIVE TYPE                 DURATION                                                           REASON                                                                       SHUTTING DOWN                                                                                         EVENT                 CODE     CODE                 ACTION TO PREVENT NO.     DATE         1                     (HOURS)                                                                     2                                                                 REACTOR                                                                                               REPORT                 4         5                   RECURRENCE 17   07/12/96       S                             0.0                                                                             B                                                                                                     N/A                                                   N/A                   N/A         N/A             Planned down power to conduct main condenser back wash.
Pilorim COMPLETED BY:
1                         2                                                                                                                                                           3                                                                                                           4&5 F-Forced         A-Equip Failure                                                                                                                                     1-Manual                                                                                                                     - Exhibit F & H                                                                                                                                   i S-Sched           B-Main or Test                                                                                                                                   2-Manual Scram                                                                                                                 Instructions for                                                                                                                                 ,
R.L. Cannon TELEPHONE:
C-Refueling                                                                                                                                       3-Auto Scram                                                                                                                   Preparations of D-Regulatory Restriction                                                                                                                         4-Continued                                                                                                                     Data Entry Sheet E-Operator Training                                                                                                                               5-Reduced Load                                                                                                                 Licensee Event Report
(508) 83 4 8321 REPORT MONTH July 1996 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO.
                            & License Examination                                                                                                                         9-Other                                                                                                                         (LER) File (NUREG-1022) r-Ad m h                                                                                                                                                                                                                                                                                                                                                                                                                             i G Operator Error H-Other
DATE 1
__                              - _ _ _ _ - - - _ _ _ - _ _ - - _ - _ - _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ - _ - _ _ _ _ _ _ - _ _ _ _ _ _ - - _ - _ _ - _ _ _ _ - - _ _ - _ _ - - _ - _ _ - _ _ - - _ _ _ - - _ - _ _ - - _ _ _ _ - - _ _ _ - _ - - - _ - _ _ _}}
(HOURS) 2 REACTOR REPORT 4
5 RECURRENCE 17 07/12/96 S
0.0 B
N/A N/A N/A N/A Planned down power to conduct main condenser back wash.
1 2
3 4&5 F-Forced A-Equip Failure 1-Manual
- Exhibit F & H i
S-Sched B-Main or Test 2-Manual Scram Instructions for C-Refueling 3-Auto Scram Preparations of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report i
& License Examination 9-Other (LER) File (NUREG-1022) r-Ad m h i
G Operator Error H-Other l
-}}

Latest revision as of 22:18, 12 December 2024

Monthly Operating Rept for Jul 1996 for Pilgrim Nuclear Power Station
ML20116L084
Person / Time
Site: Pilgrim
Issue date: 07/31/1996
From: Cannon R, Olivier L
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR#96-074, BECO-LTR#96-74, NUDOCS 9608160097
Download: ML20116L084 (7)


Text

,

Tech. Sp:c. 6.9.A.2 Boston Edison Pilgrim Nuclear Power Station f

Rocky Hill Road Plymouth, Massachusetts 02360 L J. Olivier Vice President Nuclear Operations August 14, 1996 and station oirector BECo Ltr. #96-074 U.S. Nuclear Regulatory Commission Attention: Document Control Desk j

Washington, DC 20555 Docket No. 50-293 License No. DPR-35 l

JULY 1996 MONTHLY REPORT in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and l

planning. Should you have any questions conceming this report, please contact me directly.

'o s

[ Olivia' i

RLC/dmc/9458 Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

- Senior Resident inspector j

N

<m/

'p 9608160097 960731 PDR ADOCK 05000293 R

PDR g

160021

OPERATING DATA REPORT DOCKET NO.

50-293 NAME:

Pilorim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH July 1996 OPERA TING STATUS NOTES t

1.

Unit Name Pilgrim 1 2.

Reporting Period July 1996 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) 696 7.

Maximum Dependable Capacity (Net MWe) 670 8.

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

No Chanoes 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 5111.0 207263.0 12.

Hours Reactor Critical 744.0 4996.5 131262.6 13.

Hours Reactor Reserve Shutdown 0.0 0.0 0.0 14.

Hours Generator On-Line 744.0 4977.9 126801.8 15.

Hours Unit Reserve Shutdown 0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH) 1455474.0 9704482.0 226006652.0 17.

Gross Electrical Energy Generated (MWH) 493700.0 3323460.0 76600784.0 18.

Net Electrical Energy Generated (MWH) 474818.0 3202360.0 73645982.0 l

19. -

Unit Service Factor 100.0 97.4 61.2 20.

Unit Availability Factor 100.0 97.4 61.2 21.

Unit Capacity Factor (Using MDC Net) 95.3 93.5 53.0 22.

Unit Capacity Factor (Using DER Net) 97.4 95.7 54.2 23.

Unit Forced Outage Rate 0.0 0.0 11.6 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-

NONE PLANNED 25.

If Shutdown at End of Report Period, Estimated Date of Startup-UNIT OPERATING l

l AVERAGE DAILY UNIT POWER LEVEL 1

l DOCKET NO.

50-293 i

NAME:

Pilarim COMPLETED BY:

R.L. Cannon

)

TELEPHONE:

(508) 830-8321 J

l REPORT MONTH July 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net) l l

1 650 17 662 l

2 652 18 661 3

649 19 661 l

4 649 20 661 5

648 21 660 l

6 649 22 660 l

l 7

646 23 660 i

8 647 24 658 9

647 25 659 10 645 26 657 11 645 27 658 12 597 28 657 l

I 13 231 29 658 14 626 30 656 15 662 31 657 16 657 This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed to tha nearest whole megawatt.

I 4

'l

~

)

OPERATIONAL

SUMMARY

DOCKET NO.

50-293 NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH July 1996 The unit started the reporting period at 100% core thermal power (CTP) where it was maintained until 2022 hours0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.69371e-4 months <br /> on July 12,1996. At that time, reactor power was reduced to approximately 50% CTP in supoort of a i

backwash of the main condenser. During the downpower it was identified that one of the reactor feed flow indicators was not tracking properly. The flow indicator was replaced and a reactor heat balance was j

satisfactorily performed. At 1924 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.32082e-4 months <br /> on July 13,1996, power ascension to 100% CTP commenced. At 0536 hours0.0062 days <br />0.149 hours <br />8.862434e-4 weeks <br />2.03948e-4 months <br /> on July 14, 1996, 100 % CTP was achieved and was maintained for the remainder of the

]

reporting period.

J SAFETY RELIEF VALVE CHALLENGES i

MONTH OF JULY 1996 Requirement:

NUREG-0737 T.A.P. II.K.3.3 Thsre were no safety relief valve challenges during the reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo L tr. #81-01 dated January 5,1981.

l i

4

REFUELING INFORMATION l

DOCKET NO.

50-293 NAME:

Pilorim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 l

REPORT MONTH July 1996 Tha following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, d;.t;d 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: February 1,1997.

l 3.

Scheduled date for restart following next refueling: March 14,1997.

4.

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

5.

See #6.

6.

The new fuelloaded during the 1995 refueling outage (RFO-10)is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.

7.

(a)

There are 580 fuel assemblies in the core.

(b)

There are 1765 fuel assemblies in the spent fuel pool.

1 8.

(a)

The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.

(b)

The planned spent fuel storage capacity is 3859 fuel assemblies.

9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.

l I

i

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE DOCKET NO.

50-293 NAME-Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH July 1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE No major safety related maintenance was completed during this reporting period.

4 1

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-293 NAME:

Pilorim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 83 4 8321 REPORT MONTH July 1996 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO.

DATE 1

(HOURS) 2 REACTOR REPORT 4

5 RECURRENCE 17 07/12/96 S

0.0 B

N/A N/A N/A N/A Planned down power to conduct main condenser back wash.

1 2

3 4&5 F-Forced A-Equip Failure 1-Manual

- Exhibit F & H i

S-Sched B-Main or Test 2-Manual Scram Instructions for C-Refueling 3-Auto Scram Preparations of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report i

& License Examination 9-Other (LER) File (NUREG-1022) r-Ad m h i

G Operator Error H-Other l

-