ML20094N097: Difference between revisions

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=Text=
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{{#Wiki_filter:g-.
{{#Wiki_filter:g-.
y3                   -    --
y3 AVERAGE DAILY UNIT POWER LEVEL ~
AVERAGE DAILY UNIT POWER LEVEL ~
DOCKET NO.
l DOCKET NO. 50-293 UNIT       Pilaris 1 DATE COMPLETED 8Y P. Hamilton TELEPHONE (6171746-7900 MONTH       July 1984 DAY     AVERAGE DAILY POWER LEVEL         DAY     -AVERAGE DAILY POWER LEVEL (ftee-Net)                               (mfe-Net) 1                       0 .'             17                   0.
50-293 UNIT Pilaris 1 DATE COMPLETED 8Y P. Hamilton TELEPHONE (6171746-7900 MONTH July 1984 DAY AVERAGE DAILY POWER LEVEL DAY
2'                       O.               18                   0.
-AVERAGE DAILY POWER LEVEL (ftee-Net)
                -3                         0.               19                   0.
(mfe-Net) 1 0.'
4                       0.               20                   0.
17 0.
5                       0.               21                   0.
2' O.
6                       0.               22                   0.
18 0.
7                       0.               23                   0.
-3 0.
8                       0.               24                   0.                     '
19 0.
9                       0.               25                   O.
4 0.
10                       0.               26                   0.
20 0.
11                       0.               27                   0, 12                       0.               28                   0.
5 0.
13                       0.               29                   0.
21 0.
:14                       0.               30                   0.
6 0.
15                       0.               31                   0.
22 0.
16                       0.
7 0.
INSTRUCTIONS                                                                               ;
23 0.
On this fo(mat, list-the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
8 0.
h3 h
24 0.
: l.                 O                                                                             l
9 0.
: p.                     PDR                                                           I\     i
25 O.
10 0.
26 0.
11 0.
27 0,
12 0.
28 0.
13 0.
29 0.
:14 0.
30 0.
15 0.
31 0.
16 0.
INSTRUCTIONS On this fo(mat, list-the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
h h3 l.
O p.
PDR I\\
i


(;     =: -                                                                                                                                                         ;
(;
  ,< r..
=: -
                                                                                                                                                                        )
r..
i OPERATING DATA REPORT DOCKET NO.                             50-293 DATE COMPLETED BY                     P. Hamilton TELEPHONE                         (617)746-7900 OPERATING STATUS
)
: 1. Unit Name                     Pilaris 1                                           Notes
i OPERATING DATA REPORT DOCKET NO.
: 2. Reporting Period                     July 1984
50-293 DATE COMPLETED BY P. Hamilton TELEPHONE (617)746-7900 OPERATING STATUS 1.
: 3. Licensed Thermal Power (MWt)                       1998
Unit Name Pilaris 1 Notes 2.
: 4. - Nameplate Rating (Gross MWe)                     678 5.- Design Electrical     Rating (Net MWe)         655
Reporting Period July 1984 3.
: 6. Maximum   Dependable     Capacity (Gross MWe)   690
Licensed Thermal Power (MWt) 1998
: 7. Maximum Dependable Capacity (Net MWe)               670
: 4. - Nameplate Rating (Gross MWe) 678 5.- Design Electrical Rating (Net MWe) 655 6.
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
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
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 5111.0 102071.0
: 11. Hours In' Reporting Period                                 744.0                 5111.0                     102071.0
: 12. Number Of Hours Reactor Was Critical 0.0 0.0 69746.3
: 12. Number Of Hours Reactor Was Critical                               0.0                 0.0                   69746.3
: 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 0.0 0.0 67534.0
: 14. Hours Generator On-Line                                           0.0                 0.0                   67534.0
: 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) 0.0 0.0 116932632.0
: 16. Gross Thermal Energy Generated (MWH)                               0.0                 0.0                 116932632.0
: 17. Gross Electrical Energy Generated (MWH) 0.0 0.0 39228314.0
: 17. Gross Electrical Energy Generated (MWH)                           0.0                 0.0                 39228314.0
: 18. Net Electrical Energy Generated (MWH) 0.0 0.0 37693409.0
: 18. Net Electrical Energy Generated (MWH)                             0.0                 0.0                 37693409.0
: 19. Unit Service Factor 0.0 0.0 66.2
: 19. Unit Service Factor                                               0.0                 0.0                           66.2
: 20. Unit Availability Factor 0.0 0.0 66.2
: 20. Unit Availability Factor                                           0.0                 0.0                           66.2
: 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 55.1
: 21. Unit Capacity Factor (Using MDC Net)                               0.0                 0.0                           55.1
: 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 56.4
: 22. Unit Capacity Factor (Using DER Net)                               0.0                 0.0                           56.4
: 23. Unit Forced Outage Rate 0.0 0.0 9.2 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-
: 23. Unit Forced Outage Rate                                           0.0                 0.0                           9.2 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-
Shutdown for refueline and recirculation eine replacement - Outaae j
Shutdown for refueline and recirculation eine replacement - Outaae                                                                                     j connenced on December 10. 1983.
connenced on December 10. 1983.
: 25. If Shut Down At End Of Report Period Estimated Date of Startup Oct. 1984
: 25. If Shut Down At End Of Report Period Estimated Date of Startup Oct. 1984
: 26. Units In Test Status (Prior to Commercial Operation):
: 26. Units In Test Status (Prior to Commercial Operation):
Forecast                   Achieved INITIAL CRITICALITY l                                 INITIAL ELECTRICITY COMMERCIAL OPERATION l
Forecast Achieved INITIAL CRITICALITY l
(9/77)
INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
I
I
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                                                                                                                                                                                                                                      , .b A 4.,
,.b A 4.,
UNIT SHUTDOWNS AND POWER REDUCTIONS           DOCKET NO.       '50-293 4
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME'     Pilerim 1
'50-293 UNIT NAME' Pilerim 1 4
DATE
^
^
DATE COMPLETED BY   P. Hamilton
COMPLETED BY P. Hamilton TELEPHONE' (617) 746-7900 REPORT MONTH July 1984 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEN COMPONENT ACTION TO NO.
.                                                                                                                                                                                                      TELEPHONE'     (617) 746-7900 REPORT MONTH July 1984 METHOD OF         LICENSE                             CAUSE & CORRECTIVE DURATION               SHUTTING           EVENT     SYSTEN   COMPONENT         ACTION TO NO.                 DATE   TYPEl                           (HOURS) REASON 2     DOWN REACTOR 3       REPORT #     CODE 4     CODES       PREVENT RECURRENCE 16                 83/12/10   S                               744.0   C               1               N/A       N/A       N/A       N/A - Shutdown for-refueling and recirculation .
DATE TYPEl (HOURS)
REASON 2 DOWN REACTOR 3 REPORT #
CODE 4 CODES PREVENT RECURRENCE 16 83/12/10 S
744.0 C
1 N/A N/A N/A N/A - Shutdown for-refueling and recirculation.
pipe replacement.
pipe replacement.
I l
I l
I
I 1
;                                                                      1                          2                                             2                     3               4&5
2 2
.                                                                F-Forced A-Equip Failure                                                     F-Admin             1-Manual         Exhibit F & H S-Sched                   B-Maint or Test                                 G-Oper Error       2-Manual Scram     Instructions for l                                                                                           C-Refueling                                     H-Other           3-Auto Scram       Preparation of 4                                                                                           D-Regulatory Restriction                                           4-Continued       Data Entry Sheet E-Operator Training                                                 5-Reduced Load     Licensee Event Report
3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for l
                                                                                              & License Examination                                             9-Other             (LER) File (NUREG-1022) i i
C-Refueling H-Other 3-Auto Scram Preparation of 4
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) i i


        .~~                                                                                                                 - i 7-
7-
  , a.
- i
.~~
a.
REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BEco, dated January 18, 1978:
REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BEco, 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:     March 1986
The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.
: 3. Scheduled date for restart following refueling: October 1984 4.
2.
: 5. Due to their similarity, requests 4, 5, & 6 are responded to collectively:
Scheduled date for next Refueling Shutdown:
: 6. The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x0R design, as loaded the previous outage consisting of 112 P8DRB282 assemblies and 60 P80RB265 assemblies.
March 1986 3.
: 7. (a) There are fuel assemblies in the core.
Scheduled date for restart following refueling: October 1984 4.
5.
Due to their similarity, requests 4, 5, & 6 are responded to collectively:
6.
The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x0R design, as loaded the previous outage consisting of 112 P8DRB282 assemblies and 60 P80RB265 assemblies.
7.
(a) There are fuel assemblies in the core.
i (b) There are 1,708 fuel assemblies in the spent fuel pool.
i (b) There are 1,708 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 1770 fuel assemblies at present.
8.
(a)
The station is presently licensed to store 2320 spent fuel assemblies. The actual spent fuel storage capacity is 1770 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 j               capacity to accoanmdate an additional 62 fuel assemblies.
9.
With present spent fuel in storage, the spent fuel pool now has the j
capacity to accoanmdate an additional 62 fuel assemblies.
l i
l i
l' i
l' i
Line 107: Line 155:
l u
l u


  +e ..:.
+e BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 9p_erational Summary for Julv M84 The Unit has been shut down all month for Refuel Outage #6 and recirculation pipe replacement.
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 9p_erational Summary for Julv M84 The Unit has been shut down all month for Refuel Outage #6 and recirculation pipe replacement.
All outage work continued.
All outage work continued.
a Safety Relief Valve Challenges Month of July 1984 Requirement:   T.M.I.               T.A.P.               II.K.3.3 Reason: No safety / relief valve challenges occurred during the month of July 1984. Refuel Outage #6 is in progress.
a Safety Relief Valve Challenges Month of July 1984 Requirement:
T.M.I.
T.A.P.
II.K.3.3 Reason: No safety / relief valve challenges occurred during the month of July 1984. Refuel Outage #6 is in progress.
i
i
(
(


s
s
                                                                                                                                  'W s:
'W s:
I Month July 1984 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT           MALFUNCTION       CAUSE         MAINTENANCE           TO PREVENT       ASSOCIATED LER RECURRENCE Main           MSIV's     Failed App. "J" Probable       Continued Repair       Continued       Update to 83-065/
I Month July 1984 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED LER RECURRENCE Main MSIV's Failed App. "J" Probable Continued Repair Continued Update to 83-065/
Steam                     LLRT             Seat Wear     of Valve Internals     Modification   03L-0 to be issued.
Steam LLRT Seat Wear of Valve Internals Modification 03L-0 to be issued.
per PDC 83-48 Main           Safety     Lifted above     Under         Refurbish and Reset   New Pilot Disc 84-005 - Update to Steam         Relief     Specs.           investiga-                           Material -     be issued.
per PDC 83-48 Main Safety Lifted above Under Refurbish and Reset New Pilot Disc 84-005 - Update to Steam Relief Specs.
Valves                       tion                                 Revise Operating Procedures.
investiga-Material -
Recirc.       Piping     Weld Indications Inter-         Continued Welding of   Replacement     83-063/01T-0 granular       Replacement Pipe       of piping.
be issued.
Stress Corrosion Cracking Recirc.       Nozzles     Weld Indications Inter-         Continued Repair of   Under           Ref. I&E Info.
Valves tion Revise Operating Procedures.
granular       Nozzles               investigation. Notice 84-41 Stress Corrosion Cracking PCIS           HFA         Overheating     Generic       Replace               Replace per     LER 84-009 Relay                       Problem                               response to I.E. Bulletin 84-02.
Recirc.
: r.                                                                                               ,
Piping Weld Indications Inter-Continued Welding of Replacement 83-063/01T-0 granular Replacement Pipe of piping.
  'o-. --4) aOSTON EOleON COMPANY soo sovtarow sincer                             l soerow.MassAcwuscrve02:ss w Luau o. wAnniumro" h p d 9, 1984
Stress Corrosion Cracking Recirc.
          *'".2.""*"'""                                                 BEco Ltr. #84-132         !
Nozzles Weld Indications Inter-Continued Repair of Under Ref. I&E Info.
Director Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.       20555 Attn:   Document Control Desk License No. DPR-35 pocket No. 50-293
granular Nozzles investigation.
Notice 84-41 Stress Corrosion Cracking PCIS HFA Overheating Generic Replace Replace per LER 84-009 Relay Problem response to I.E. Bulletin 84-02.
 
r.
'o-.
--4) aOSTON EOleON COMPANY soo sovtarow sincer soerow.MassAcwuscrve02:ss w Luau o. wAnniumro" h p d 9, 1984
*'".2.""*"'""
BEco Ltr. #84-132 Director Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
Document Control Desk License No. DPR-35 pocket No. 50-293


==Subject:==
==Subject:==
Line 132: Line 191:
In accordance with PNPS lechnical Specification 6.9.A.2, a copy of the Operational Statu, Summary for Pilgrim Nuclear Power Station is attached for your information and planning.
In accordance with PNPS lechnical Specification 6.9.A.2, a copy of the Operational Statu, Summary for Pilgrim Nuclear Power Station is attached for your information and planning.
Respectfully submitted, W. D. Harrington
Respectfully submitted, W. D. Harrington
: caw Attachment i                   cc: Regional Administrator, Region I l                         U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA     19406 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 l
: caw Attachment i
l 5     Y
cc: Regional Administrator, Region I l
                                                                                            'll}}
U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 l
5 Y
l
'll
_}}

Latest revision as of 09:12, 13 December 2024

Monthly Operating Rept for Jul 1984
ML20094N097
Person / Time
Site: Pilgrim
Issue date: 07/31/1984
From: Hamilton P, Harrington W
BOSTON EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
84-132, NUDOCS 8408160094
Download: ML20094N097 (7)


Text

g-.

y3 AVERAGE DAILY UNIT POWER LEVEL ~

DOCKET NO.

50-293 UNIT Pilaris 1 DATE COMPLETED 8Y P. Hamilton TELEPHONE (6171746-7900 MONTH July 1984 DAY AVERAGE DAILY POWER LEVEL DAY

-AVERAGE DAILY POWER LEVEL (ftee-Net)

(mfe-Net) 1 0.'

17 0.

2' O.

18 0.

-3 0.

19 0.

4 0.

20 0.

5 0.

21 0.

6 0.

22 0.

7 0.

23 0.

8 0.

24 0.

9 0.

25 O.

10 0.

26 0.

11 0.

27 0,

12 0.

28 0.

13 0.

29 0.

14 0.

30 0.

15 0.

31 0.

16 0.

INSTRUCTIONS On this fo(mat, list-the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

h h3 l.

O p.

PDR I\\

i

(;

=: -

r..

)

i OPERATING DATA REPORT DOCKET NO.

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

Unit Name Pilaris 1 Notes 2.

Reporting Period July 1984 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 5111.0 102071.0
12. Number Of Hours Reactor Was Critical 0.0 0.0 69746.3
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 0.0 0.0 67534.0
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 0.0 0.0 116932632.0
17. Gross Electrical Energy Generated (MWH) 0.0 0.0 39228314.0
18. Net Electrical Energy Generated (MWH) 0.0 0.0 37693409.0
19. Unit Service Factor 0.0 0.0 66.2
20. Unit Availability Factor 0.0 0.0 66.2
21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 55.1
22. Unit Capacity Factor (Using DER Net) 0.0 0.0 56.4
23. Unit Forced Outage Rate 0.0 0.0 9.2 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-

Shutdown for refueline and recirculation eine replacement - Outaae j

connenced on December 10. 1983.

25. If Shut Down At End Of Report Period Estimated Date of Startup Oct. 1984
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY l

INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

'50-293 UNIT NAME' Pilerim 1 4

DATE

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COMPLETED BY P. Hamilton TELEPHONE' (617) 746-7900 REPORT MONTH July 1984 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEN COMPONENT ACTION TO NO.

DATE TYPEl (HOURS)

REASON 2 DOWN REACTOR 3 REPORT #

CODE 4 CODES PREVENT RECURRENCE 16 83/12/10 S

744.0 C

1 N/A N/A N/A N/A - Shutdown for-refueling and recirculation.

pipe replacement.

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I 1

2 2

3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for l

C-Refueling H-Other 3-Auto Scram Preparation of 4

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) i i

7-

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a.

REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BEco, 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:

March 1986 3.

Scheduled date for restart following refueling: October 1984 4.

5.

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

6.

The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x0R design, as loaded the previous outage consisting of 112 P8DRB282 assemblies and 60 P80RB265 assemblies.

7.

(a) There are fuel assemblies in the core.

i (b) There are 1,708 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 1770 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 j

capacity to accoanmdate an additional 62 fuel assemblies.

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+e BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 9p_erational Summary for Julv M84 The Unit has been shut down all month for Refuel Outage #6 and recirculation pipe replacement.

All outage work continued.

a Safety Relief Valve Challenges Month of July 1984 Requirement:

T.M.I.

T.A.P.

II.K.3.3 Reason: No safety / relief valve challenges occurred during the month of July 1984. Refuel Outage #6 is in progress.

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I Month July 1984 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT ASSOCIATED LER RECURRENCE Main MSIV's Failed App. "J" Probable Continued Repair Continued Update to 83-065/

Steam LLRT Seat Wear of Valve Internals Modification 03L-0 to be issued.

per PDC 83-48 Main Safety Lifted above Under Refurbish and Reset New Pilot Disc 84-005 - Update to Steam Relief Specs.

investiga-Material -

be issued.

Valves tion Revise Operating Procedures.

Recirc.

Piping Weld Indications Inter-Continued Welding of Replacement 83-063/01T-0 granular Replacement Pipe of piping.

Stress Corrosion Cracking Recirc.

Nozzles Weld Indications Inter-Continued Repair of Under Ref. I&E Info.

granular Nozzles investigation.

Notice 84-41 Stress Corrosion Cracking PCIS HFA Overheating Generic Replace Replace per LER 84-009 Relay Problem response to I.E.Bulletin 84-02.

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--4) aOSTON EOleON COMPANY soo sovtarow sincer soerow.MassAcwuscrve02:ss w Luau o. wAnniumro" h p d 9, 1984

  • '".2.""*"'""

BEco Ltr. #84-132 Director Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn:

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

Subject:

July 1904 Honthly Report bear Sir:

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

Respectfully submitted, W. D. Harrington

caw Attachment i

cc: Regional Administrator, Region I l

U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555 l

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