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                                                           , O'                                      ,
                                                           , O'                                      ,
  \  ,
  \  ,
* LJ                                        l sosM W so m W L                                              Pilgnm Nuclear Powr station Rocky Hill Road                              !
LJ                                        l sosM W so m W L                                              Pilgnm Nuclear Powr station Rocky Hill Road                              !
  !                                        2    Plymouth, Massachusetts 02360                        l l
  !                                        2    Plymouth, Massachusetts 02360                        l l
L                                                                                                l K. L. Highfill                                                                      l f
L                                                                                                l K. L. Highfill                                                                      l f
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BECo Ltr. #89 151    ,
BECo Ltr. #89 151    ,
U.S. Nuclear Regulatory Commission                                                    .
U.S. Nuclear Regulatory Commission                                                    .
                                                                                                  '
Attention: Document Control Desk Hashington, DC 20555                                                                  !
Attention: Document Control Desk Hashington, DC 20555                                                                  !
l
l License No. DPR-35 Docket No. 50-293-  l
                                                                                                  "
License No. DPR-35 Docket No. 50-293-  l
                                                                                                !


==Subject:==
==Subject:==
September 1989 Honthly Report                                        i
September 1989 Honthly Report                                        i
                                                                                                  !


==Dear Sir:==
==Dear Sir:==


In accordance with PNPS Technical Specification 6.9.A.2, a copy of the              '
In accordance with PNPS Technical Specification 6.9.A.2, a copy of the              '
1          Operational Status Summary for Pilgrim Nuclear Power Station is attached for        j your information and planning. Should you have any questions concerning this report please contact me directly.                                                  l
1          Operational Status Summary for Pilgrim Nuclear Power Station is attached for        j your information and planning. Should you have any questions concerning this report please contact me directly.                                                  l y
                                                                                                !
K.L. Highfill HJH:bal                                                                              ;
y K.L. Highfill HJH:bal                                                                              ;
f        Attachment                                                                            l cc: Regional Administrator, Region 1                                                !
f        Attachment                                                                            l cc: Regional Administrator, Region 1                                                !
U.S. Euclear Regulatory Commission 475 Allendale Rd.                                                            ,
U.S. Euclear Regulatory Commission 475 Allendale Rd.                                                            ,
                                                                                                '
King of Prussia. PA 19406                                                    :
King of Prussia. PA 19406                                                    :
Senior Resident Inspector                                                    -
Senior Resident Inspector                                                    -
Line 55: Line 48:


       .                          AVERAGE DAILY UNIT POWER LEVEL                        '
       .                          AVERAGE DAILY UNIT POWER LEVEL                        '
    .
DOCKET NO. 50-293 UNIT          Pilorim 1
DOCKET NO. 50-293 UNIT          Pilorim 1
                                                                                 ~
                                                                                 ~
  ,
DATE          ownh~ 19 1o og COMPLETED BY _L Munro TELEPHONE    _(508) 747-8474 i
DATE          ownh~ 19 1o og
l      MONTH _ Sentember 1919
  '
COMPLETED BY _L Munro TELEPHONE    _(508) 747-8474
                                                                                          '
i l      MONTH _ Sentember 1919
  ;      DAY      AVERAGE DAILY POWER LEVEL      DAY      AVERAGE DAILY POWER LEVEL      .
  ;      DAY      AVERAGE DAILY POWER LEVEL      DAY      AVERAGE DAILY POWER LEVEL      .
'
(MWe-Net)                              (MWe-Net)
(MWe-Net)                              (MWe-Net)
  !'      1                    0                  17                    433 I                                                                      481 2                    0                  18 9
  !'      1                    0                  17                    433 I                                                                      481 2                    0                  18 9
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1 r
1 r
   .                                        OPERATING DATA REPORT 4
   .                                        OPERATING DATA REPORT 4
    '
DOCKET NO.        50-293                i t
DOCKET NO.        50-293                i t
DATE          n . . m ., , , snen h                                                          COMPLETED BY T M0nfo' " '
DATE          n . . m ., , , snen h                                                          COMPLETED BY T M0nfo' " '
l                                                          TELEPHONE      1108) 747-8474 OPERATING STATUS                                                                                ,
l                                                          TELEPHONE      1108) 747-8474 OPERATING STATUS                                                                                ,
l
l
!
!                                                                Notes                                ,
!                                                                Notes                                ,
: 1. Unit Name _              Pilgrim 1
: 1. Unit Name _              Pilgrim 1
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: 3. Licensed Thermal Power (MHt)                  1938
: 3. Licensed Thermal Power (MHt)                  1938
: 4. Nameplate Rating (Gross MWe)                  618 S. Dr. sign Electrical Rating (Net HHe)          655
: 4. Nameplate Rating (Gross MWe)                  618 S. Dr. sign Electrical Rating (Net HHe)          655
,
: 6. Maximum Dependable Capacity (Gross MHe)        620
: 6. Maximum Dependable Capacity (Gross MHe)        620
: 7. Maximum Dependable Capacity (Net MWe)          670                                        r
: 7. Maximum Dependable Capacity (Net MWe)          670                                        r
Line 105: Line 89:
: 17. Gross Electrical Energy Generated (HHH)          264730.0      904190.0 46348794.0        ,
: 17. Gross Electrical Energy Generated (HHH)          264730.0      904190.0 46348794.0        ,
: 18. Net Electrical Energy Generated (MHH)            _2533 6610      854777.0 JL4510106J        !
: 18. Net Electrical Energy Generated (MHH)            _2533 6610      854777.0 JL4510106J        !
                                                                                                      '
: 19. Unit Service Factor                                    78.6          52.5          54.7
: 19. Unit Service Factor                                    78.6          52.5          54.7
: 20. Unit Availability Factor                              7ad            52.5          54.7    l
: 20. Unit Availability Factor                              7ad            52.5          54.7    l
Line 113: Line 96:
: 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):
Maintenance o m g h October 14. 1989 f_gr a duration of 18 days                                i
Maintenance o m g h October 14. 1989 f_gr a duration of 18 days                                i
                                                              '
         . If Shut Down At End Of Report Period, Estimated Date of Startup -                        .
         . If Shut Down At End Of Report Period, Estimated Date of Startup -                        .
                                                                                                      ;
: 26. Units In Test Stc:tus (Prior to Comtrercial Operation):          N/A Forecast    Achieved INITIAL CRITICALITY INITIAL ELECTRICITY                                                      !
: 26. Units In Test Stc:tus (Prior to Comtrercial Operation):          N/A Forecast    Achieved INITIAL CRITICALITY INITIAL ELECTRICITY                                                      !
COMMERCIAL OPERATION (9/77)
COMMERCIAL OPERATION (9/77)
* Includes adjustment from August 1989 Report.
* Includes adjustment from August 1989 Report.


        '          '
                                               ~DOSTON EDISON COMPANY r ,                                    P!L' IM NUCLEAR POWER STATION DOCKET NO. 50-291L Ooerational summarv for Sepitmht.r_1989 The station started the month in cold shutdown and remained in an outage      !
      .    *
                                               ~DOSTON EDISON COMPANY r ,                                    P!L' IM NUCLEAR POWER STATION
'
DOCKET NO. 50-291L
          ,  ,
                                                                                              '
Ooerational summarv for Sepitmht.r_1989 The station started the month in cold shutdown and remained in an outage      !
[  ,        condition until 2216 hours on September 6. 1989 when the unit was made          <
[  ,        condition until 2216 hours on September 6. 1989 when the unit was made          <
  !            critical. At 1015 hours on September 7, 1989 the turbine generator was          (
  !            critical. At 1015 hours on September 7, 1989 the turbine generator was          (
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b            unit availability due to backwashing and associated power reductions. The
b            unit availability due to backwashing and associated power reductions. The
  ;            unit remained on line for the remainder of the reporting period.
  ;            unit remained on line for the remainder of the reporting period.
                                                                                            !
Safety Relief Valve Challenges
Safety Relief Valve Challenges
  ;                                            Honth of Scottmber 1989                      i
  ;                                            Honth of Scottmber 1989                      i Requirement:    NUREG-0737 T.A.P. II.K.3.3                                    l There were no safety relief valve challenges during the month.                !
                                                                                            ,
An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo  t 1tr. #81-01 dated 01/05/81.
Requirement:    NUREG-0737 T.A.P. II.K.3.3                                    l There were no safety relief valve challenges during the month.                !
1 t
An SRV challenge is defined as anytime an SRV has received a signal to operate
i f
'
a s
via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo  t
k^                                                                          _
.
1tr. #81-01 dated 01/05/81.
1
:
                                                                                            !
                                                                                            !
:
                                                                                            !
                                                                                            !
                                                                                            !
t i
f a
                                                                                            ,
s k^                                                                          _


w
w
   ,.        ey              ;O                RErutLING ItLEORMATION
   ,.        ey              ;O                RErutLING ItLEORMATION
                                                                                                '
            *
>'      c,        l'                                                                            ;
>'      c,        l'                                                                            ;
l . 4"        Thk following refueling information is included in the Monthly Report as        :
l . 4"        Thk following refueling information is included in the Monthly Report as        :
'
          ,
requested in an NRC letter to 8ECo, dated January 18, 1978:                      )
requested in an NRC letter to 8ECo, dated January 18, 1978:                      )
!m                                                                                              i l
!m                                                                                              i l
Line 170: Line 125:
for your convenience, the information supplied has been enumerated so that,      !
for your convenience, the information supplied has been enumerated so that,      !
L,            each number corresponds to equivalent notation utilized in the request.
L,            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  !
l 50-293.                                                                    l
l 50-293.                                                                    l
Line 176: Line 130:
L
L
: 3. Scheduled date for restart following refueling:    Second Quarter 1991    !
: 3. Scheduled date for restart following refueling:    Second Quarter 1991    !
4    Due to their similarity, requests 4, 5, & 6 are responded to collectively
4    Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6.
'
under #6.
L              5. See #6.
L              5. See #6.
: 6. The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.
: 6. The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.
: 7.    (a) There are 580 fuel assemblies in the core.
: 7.    (a) There are 580 fuel assemblies in the core.
(b) There are 1320 fuel assemblies in the spent fuel pool.
(b) There are 1320 fuel assemblies in the spent fuel pool.
'
: 8.    (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies.
: 8.    (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies.
(b) The planned spent fuel storage capacity is 2320 fuel assembliti.
(b) The planned spent fuel storage capacity is 2320 fuel assembliti.
: 9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.
: 9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.
;
J
J


_ _ - - . - - - - - . .
                                                                                                                                                                                                                                ,
                - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -        -
_ - - -  _    _.      -- __ _ . _ _ _ - _ - - - _                ,-    __    . _ _ _ . _ _
                                                                                                                                                                                                              -
Month Sepitigter 1989.
Month Sepitigter 1989.
* PILGRIM NUCLEAR POWER STATION                                                                        ,
PILGRIM NUCLEAR POWER STATION                                                                        ,
Mr.JOR SAFETY RELATED MAI?.TENANCE                                                                          ,  g-
Mr.JOR SAFETY RELATED MAI?.TENANCE                                                                          ,  g-SYSTEM                                                    COMPONENT            PALFUNCTION                          C_AU1E          MAINTENANCE                            CORRECTIVE ACTION TO    ASSOCIATED -
    -
PREVEMT RECUR 8tENCL    .      LER Rasidual                                                  Relay              Unplanned ESF                  Technician        Testing discontinued; Procedure TP 88-78                          LER 89-02L30 Heat                                                        10A-K10A          actuation                      error.            circuitry returned to revised to include Removal                                                                        resulting from                                    normal, affected                          double verification.
SYSTEM                                                    COMPONENT            PALFUNCTION                          C_AU1E          MAINTENANCE                            CORRECTIVE ACTION TO    ASSOCIATED -
PREVEMT RECUR 8tENCL    .      LER
_
Rasidual                                                  Relay              Unplanned ESF                  Technician        Testing discontinued; Procedure TP 88-78                          LER 89-02L30 Heat                                                        10A-K10A          actuation                      error.            circuitry returned to revised to include Removal                                                                        resulting from                                    normal, affected                          double verification.
(RHR)                                                                        jumpering of                                      valves restored to                        (Refer to associated System                                                                        incorrect relay                                    thier normal position, LER).
(RHR)                                                                        jumpering of                                      valves restored to                        (Refer to associated System                                                                        incorrect relay                                    thier normal position, LER).
during logic                                      and diesel generator relay testing,                                    shutdown.
during logic                                      and diesel generator relay testing,                                    shutdown.
Line 209: Line 150:
High                                                        Ramp Generator HPCI system                        Faulty Ramp        The Ramp Generator                        Refer to associated      LER 89-028-00 Pressure                                                  Signal Convert- turbine trip                      Generator Signal Signal Converter                            LER.
High                                                        Ramp Generator HPCI system                        Faulty Ramp        The Ramp Generator                        Refer to associated      LER 89-028-00 Pressure                                                  Signal Convert- turbine trip                      Generator Signal Signal Converter                            LER.
Coolant                                                      er Module        on overspeed                    Converter resul- (RGSC) (Noodward Injection                                                  (Woodward Gov- during routine ting in a mech- Governor Co. Model (HPCI)                                                      ernor Co. Model surveillance                      anical over-      #8271-083) was re-System                                                    #8271-083)          test (Proc.                    speed trip.        placed with a new 8.5.4.1)                                          RGSC module (Model (F&MR 89-339)                                    #9903-015). MPCI turbine speed control system was calibrated per Proc.
Coolant                                                      er Module        on overspeed                    Converter resul- (RGSC) (Noodward Injection                                                  (Woodward Gov- during routine ting in a mech- Governor Co. Model (HPCI)                                                      ernor Co. Model surveillance                      anical over-      #8271-083) was re-System                                                    #8271-083)          test (Proc.                    speed trip.        placed with a new 8.5.4.1)                                          RGSC module (Model (F&MR 89-339)                                    #9903-015). MPCI turbine speed control system was calibrated per Proc.
8.E.23.1
8.E.23.1 l
:
l
___


-                                                                                  . - _ _ .. __ . _ _ - .- _          _ _            ___ _
UNIT SHUTDONNS AND POWE2 REDUCTIONS                DOCKET M9._50-293                            "
UNIT SHUTDONNS AND POWE2 REDUCTIONS                DOCKET M9._50-293                            "
                                                                                                                                                  .
                                                                                                                                                              *
                                                                                                                                                                      -
                                                                                                                                                            '
NAME          Pilaria 1                        "        '    4 DATE m e.w p,7en9                                .
NAME          Pilaria 1                        "        '    4 DATE m e.w p,7en9                                .
COMPLETED BY M.'Mu_nrp                            ,        , .
COMPLETED BY M.'Mu_nrp                            ,        , .
Line 226: Line 159:
I              2                      2                3                  45 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 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
I              2                      2                3                  45 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 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) Flie (NUREG-1022)
               & License Examination                    9-Other          (LER) Flie (NUREG-1022)
                                                                                                                                                                      .
_,        .- , em-me+      me      -  w}}
_,        .- , em-me+      me      -  w}}

Latest revision as of 19:13, 18 February 2020

Monthly Operating Rept for Sept 1989 for Pilgrim Nuclear Power Station.W/891012 Ltr
ML19325D426
Person / Time
Site: Pilgrim
Issue date: 09/30/1989
From: Highfill K, Munro W
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-151, NUDOCS 8910240037
Download: ML19325D426 (7)


Text

F*

  • i l

, O' ,

\ ,

LJ l sosM W so m W L Pilgnm Nuclear Powr station Rocky Hill Road  !

! 2 Plymouth, Massachusetts 02360 l l

L l K. L. Highfill l f

station Director October 12 ,1989  !

BECo Ltr. #89 151 ,

U.S. Nuclear Regulatory Commission .

Attention: Document Control Desk Hashington, DC 20555  !

l License No. DPR-35 Docket No. 50-293- l

Subject:

September 1989 Honthly Report i

Dear Sir:

In accordance with PNPS Technical Specification 6.9.A.2, a copy of the '

1 Operational Status Summary for Pilgrim Nuclear Power Station is attached for j your information and planning. Should you have any questions concerning this report please contact me directly. l y

K.L. Highfill HJH:bal  ;

f Attachment l cc: Regional Administrator, Region 1  !

U.S. Euclear Regulatory Commission 475 Allendale Rd. ,

King of Prussia. PA 19406  :

Senior Resident Inspector -

l ffh 0 '

1 4*A 4 .

i}

9910240037 890930

, PDR ADOCK 05000293 M PNU

. AVERAGE DAILY UNIT POWER LEVEL '

DOCKET NO. 50-293 UNIT Pilorim 1

~

DATE ownh~ 19 1o og COMPLETED BY _L Munro TELEPHONE _(508) 747-8474 i

l MONTH _ Sentember 1919

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

(MWe-Net) (MWe-Net)

!' 1 0 17 433 I 481 2 0 18 9

3 0 19 418

? 4 0 20 482 __

$ 5 0 21 481 L

6 0 22 447 7 61 23 486 ,

8 367 24 486 9 443 25 485 10 401 26 479 11 485 27 482 12 464 28 485 13 457 29 485 14 483 30 485 15 352 31 N/A 16 432 This format lists the average daily unit power level in HWe-Net for each day in the reporting month, computed to the nearest whole megawatt.

l l

1 r

. OPERATING DATA REPORT 4

DOCKET NO. 50-293 i t

DATE n . . m ., , , snen h COMPLETED BY T M0nfo' " '

l TELEPHONE 1108) 747-8474 OPERATING STATUS ,

l

! Notes ,

1. Unit Name _ Pilgrim 1
2. Reporting Period _itpitabn_.lSB9
3. Licensed Thermal Power (MHt) 1938
4. Nameplate Rating (Gross MWe) 618 S. Dr. sign Electrical Rating (Net HHe) 655
6. Maximum Dependable Capacity (Gross MHe) 620
7. Maximum Dependable Capacity (Net MWe) 670 r
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last '

Report, Give Reasons:

None

9. Power Level To Hhich Rettricted If Any (Net MWe) 21%_ Core Thermal Powg.t ,
10. Reasons for Restrictions, If Any Regulatory Restriction. Confirmatory Action Letter 86-10. Power Ascension Phast.

This Mon _th Yr-to-Date Cygtlative

11. Hours In Reporting Period 720.0 6551 0 147359.0
12. Number Of Hours Reactor Has Critical 577.7 4083_J 83874.4 i
13. Reactor Reserve Shutdown Hours 0.0 OJ 020
14. Hours Genetator On-Line 565.7 3437.9 , 80667.2
15. Unit Reserve Shutdown Hours OJ 0.0 0.0
16. Gross Thermal Energy Generated (MHH) 793272.0* 2899680.0 13219351010
17. Gross Electrical Energy Generated (HHH) 264730.0 904190.0 46348794.0 ,
18. Net Electrical Energy Generated (MHH) _2533 6610 854777.0 JL4510106J  !
19. Unit Service Factor 78.6 52.5 54.7
20. Unit Availability Factor 7ad 52.5 54.7 l
21. Unit Capacity Factor (Using HDC Net) _5LS 19.5 45.1
22. Unit Capacity Factor (Using DER Net) 53.7 19.9 46.1
23. Unit Foiced Outage Rate 21.4 29.6 13.0 -
24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):

Maintenance o m g h October 14. 1989 f_gr a duration of 18 days i

. If Shut Down At End Of Report Period, Estimated Date of Startup - .

26. Units In Test Stc:tus (Prior to Comtrercial Operation): N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY  !

COMMERCIAL OPERATION (9/77)

  • Includes adjustment from August 1989 Report.

~DOSTON EDISON COMPANY r , P!L' IM NUCLEAR POWER STATION DOCKET NO. 50-291L Ooerational summarv for Sepitmht.r_1989 The station started the month in cold shutdown and remained in an outage  !

[ , condition until 2216 hours0.0256 days <br />0.616 hours <br />0.00366 weeks <br />8.43188e-4 months <br /> on September 6. 1989 when the unit was made <

! critical. At 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> on September 7, 1989 the turbine generator was (

synchronized to the grid, and by September 8, 1989 the reactor was operating i at 75 percent rated thermal power, in accordance with the approved Power  :

Ascension Plan. However, main condenser vacuum problems continue to impact -

b unit availability due to backwashing and associated power reductions. The

unit remained on line for the remainder of the reporting period.

Safety Relief Valve Challenges

Honth of Scottmber 1989 i Requirement
NUREG-0737 T.A.P. II.K.3.3 l There were no safety relief valve challenges during the month.  !

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo t 1tr. #81-01 dated 01/05/81.

1 t

i f

a s

k^ _

w

,. ey ;O RErutLING ItLEORMATION

>' c, l'  ;

l . 4" Thk following refueling information is included in the Monthly Report as  :

requested in an NRC letter to 8ECo, dated January 18, 1978: )

!m i l

(

for your convenience, the information supplied has been enumerated so that,  !

L, each number corresponds to equivalent notation utilized in the request.

1. The name of this facility is Pilgrim Nuclear Power Station, Docket Number  !

l 50-293. l

2. Scheduled date for next Refueling Shutdown: Second Quarter 1991 )

L

3. Scheduled date for restart following refueling: Second Quarter 1991  !

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

L 5. See #6.

6. The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.
7. (a) There are 580 fuel assemblies in the core.

(b) There are 1320 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies.

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

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.

J

Month Sepitigter 1989.

PILGRIM NUCLEAR POWER STATION ,

Mr.JOR SAFETY RELATED MAI?.TENANCE , g-SYSTEM COMPONENT PALFUNCTION C_AU1E MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED -

PREVEMT RECUR 8tENCL . LER Rasidual Relay Unplanned ESF Technician Testing discontinued; Procedure TP 88-78 LER 89-02L30 Heat 10A-K10A actuation error. circuitry returned to revised to include Removal resulting from normal, affected double verification.

(RHR) jumpering of valves restored to (Refer to associated System incorrect relay thier normal position, LER).

during logic and diesel generator relay testing, shutdown.

(TP 88-78).

(F&MR 89-335)

High Ramp Generator HPCI system Faulty Ramp The Ramp Generator Refer to associated LER 89-028-00 Pressure Signal Convert- turbine trip Generator Signal Signal Converter LER.

Coolant er Module on overspeed Converter resul- (RGSC) (Noodward Injection (Woodward Gov- during routine ting in a mech- Governor Co. Model (HPCI) ernor Co. Model surveillance anical over- #8271-083) was re-System #8271-083) test (Proc. speed trip. placed with a new 8.5.4.1) RGSC module (Model (F&MR 89-339) #9903-015). MPCI turbine speed control system was calibrated per Proc.

8.E.23.1 l

UNIT SHUTDONNS AND POWE2 REDUCTIONS DOCKET M9._50-293 "

NAME Pilaria 1 " ' 4 DATE m e.w p,7en9 .

COMPLETED BY M.'Mu_nrp , , .

TELEPHONE __L506) 747-8474 REPORT MONTH S_gpfgaber 1989 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM ENT ~ ACTION TO PREVENTIVE NO. DATE TYPEI (HOURS) REASON 2 DONN REACTOR 3 REPORT # C00E4 RECURRENCE 12 09/01/89 F 154.3 A 3 89-026-00 EL 60 Failed potential trans-(continued) former combined with main generator voltage balance relay wiring error. Miring error corrected, potential tranformer replaced.

(Ref. LER89-026-00) 13 09/15/89 N/A 0.0 H 5 N/A SG N/A Power reduction to back-wash the condenser.

I 2 2 3 45 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 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) Flie (NUREG-1022)

_, .- , em-me+ me - w