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{{#Wiki_filter:- -   .    .
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5
5
  ..e Consumers
..e
            @rowEmNa       Power MKNWnAN'S Pit lNNtE55                                                                                       ,
@rowEmNa Consumers Power MKNWnAN'S Pit lNNtE55 June 3,1997 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sin Enclosed please find the statist; cal data for the Big Rock Point Nuclear Plant covering the period i
l June 3,1997 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sin Enclosed please find the statist; cal data for the Big Rock Point Nuclear Plant covering the period         i of May 1,1997 through May 31,1997.                                                                         j Sincerely, K J Shields Reactor Engineer                                                                                           !
of May 1,1997 through May 31,1997.
Enclosures cc: Administrator Region Ill, Nuclear Regulatory Commission DR Hahn, Depariment of Enviromental Quality JR Padgett, Michigan Public Service Commission R Aben, Michigan Department of Labor MP Cass, American NuclearInsures B Lewis, McGraw-Hill,Inc.                                                                         #
j Sincerely, K J Shields Reactor Engineer Enclosures cc: Administrator Region Ill, Nuclear Regulatory Commission DR Hahn, Depariment of Enviromental Quality JR Padgett, Michigan Public Service Commission R Aben, Michigan Department of Labor MP Cass, American NuclearInsures B Lewis, McGraw-Hill,Inc.
SM McIntyre, P26-201                                                                       fg KP Powers, Big Rock Point                                                                     / D   l GC Withrow, Big Rock Point                                                                 #
SM McIntyre, P26-201 fg KP Powers, Big Rock Point
NRC Resident inspector, Big Rock Point Document Control, Big Rock Point,740*22*15*10 File 9706100120 970531                                                     * * * * * * *
/ D l
* PDR     ADOCK 05000155 R                     PDR                 ,,j A CAG ENE72GYCOMPANY
GC Withrow, Big Rock Point NRC Resident inspector, Big Rock Point Document Control, Big Rock Point,740*22*15*10 File 9706100120 970531 PDR ADOCK 05000155 R
PDR
,,j A CAG ENE72GYCOMPANY


        ._    _ _ _ - . _ _ _ - .          ._ _ _ _ .        _ _.-_._._                  _ _ _ . _ _ . _ _ _ . - - _ . ~ . _ _ - . . _ . _ _ _ _ . .
_ _ _. _ _. _ _ _. - - _. ~. _ _ -.. _. _ _ _ _..
      ,.                                                                  FORM 16.3.H Operating Status Report - Nuclear Regulatory Commission
FORM 16.3.H Operating Status Report - Nuclear Regulatory Commission 7ade k /9k2 Prepared by:
;          Prepared by:             #                                    Date: 7ade k /9k2
Date:
;          R: viewed b                                                     Date:     b D
b D
R: viewed b Date:
(Reactor Er%lneer or Altemate)
(Reactor Er%lneer or Altemate)
Copy to be sent to the following by the seventh day of each month:
Copy to be sent to the following by the seventh day of each month:
l Nuclear Regulatory Commission                                       Robert Aben, Assistant Chief                                         l Document Control Desk                                               Bureau of Construction Codes
Nuclear Regulatory Commission Robert Aben, Assistant Chief Document Control Desk Bureau of Construction Codes Washington,DC 20555 Michigan Department of Labor 7150 Harris Drive, Box 30015 Lansing,MI 48909 4
,            Washington,DC 20555                                                 Michigan Department of Labor 7150 Harris Drive, Box 30015 Lansing,MI 48909 4           Administrator                                                       American NuclearInsurers
Administrator American NuclearInsurers Region lli-USNRC Att: MP Cass 801 Warrenville Road Town Center, Suite 300S I
!            Region lli- USNRC                                                   Att: MP Cass
Lisle,IL 60532 4351 29 South Main Street i
  ,          801 Warrenville Road                                               Town Center, Suite 300S I             Lisle,IL 60532 4351                                                 29 South Main Street                                                 i West Hartford, CT 06107-2445 4
West Hartford, CT 06107-2445 4
DR Hahn                                                             Barbara Lewis j             Department of Enviromental Gua!ity                                 McGraw-Hill,Inc.
DR Hahn Barbara Lewis j
;            3500 North Logan                                                   1200 G Street, N.W.
Department of Enviromental Gua!ity McGraw-Hill,Inc.
4 Lansing, MI 48906                                                   Suite 1100
3500 North Logan 1200 G Street, N.W.
:                                                                                Washington,DC 20005 I             JR Padgett i             Michigan Public Service Commission
Lansing, MI 48906 Suite 1100 4
!            PO Box 30221
Washington,DC 20005 I
{             Lansing, MI 48909
JR Padgett i
!          Routing Copy:
Michigan Public Service Commission PO Box 30221
',          SM McIntyre, P26-201 4
{
Lansing, MI 48909 Routing Copy:
SM McIntyre, P26-201 4
KP Powers, Big Rock Point Plant CC Withrow, Big Rock Point Plant NRC Resident inspector, Big Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04) Cross Reference 16.3.3-17
KP Powers, Big Rock Point Plant CC Withrow, Big Rock Point Plant NRC Resident inspector, Big Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04) Cross Reference 16.3.3-17


. . . - . . . .                - .    ..-              -.    . .            .                      -. . . - . . __ .                  ..          - - .-              .          .      . _ _ .      _.. .. -.                                              .~.
.~.
causssssmarsgesygy                                                                                                                                                                                                                                   .
causssssmarsgesygy NUCLEAR OPERATIONS DEPARTMENT Unit Shutdown and Power Reductions Report Month Docket Number Unit Date Completed by Telephone May,1997 56-160 Big Rock Point Plant June 3.1997 JR Johnston (614) 547 4 223 Method of Shuttmg Duration Down Licensee Event Systery Cy l
NUCLEAR OPERATIONS DEPARTMENT                                                                                                                                                   >
2 Number Date Type (Hours)
Unit Shutdown and Power Reductions Report Month             Docket Number                           Unit                                               Date                       Completed by                                   Telephone May,1997                 56-160                                 Big Rock Point Plant                               June 3.1997                 JR Johnston                                   (614) 547 4 223                                       ,
Reason p,,,,,,3 Report Number Code Code Cause and Corrective Action To Pnivent Recurrence 97 01 03/02/97 F
Method of Shuttmg Duration                     Down                                 Licensee Event Systery       Cy Number           Date Type l
113.5 Hrs A
(Hours)       Reason p ,,,,,,3                           Report Number   Code             Code           Cause and Corrective Action To Pnivent Recurrence 97 01       03/02/97     F       113.5 Hrs       A               1, 2                                                                       On 034248 at 22:32; The unit was removed from service to
1, 2 On 034248 at 22:32; The unit was removed from service to Thru
                                                                                                                                                                      ^
, " _ and repair leakage from MO-7071 and/or VPl403 on
Thru                                                                                                                            ..      , " _ and repair leakage from MO-7071 and/or VPl403 on 0646/97                                                                                                                         the poet incedent system. ARer the unit was removed from service, the reactor was manually scrammed to fbily insert the remaining withdrawn control rod drives. Alter repairs were complete, the reactor was taken critical on 04/20/97 and ready                                       ,
^
to place the unit on line when the lir2 Reactor recirc pump inner seat failed. The turbine was placed on tuming gear and the reactor was manually cerammed (planned) to fully insert the remainmg withdrawn control rod drives. On 04/28/97 at 05:26; the 116 OCB tripped while trying to place the unit on line.
0646/97 the poet incedent system. ARer the unit was removed from service, the reactor was manually scrammed to fbily insert the remaining withdrawn control rod drives. Alter repairs were complete, the reactor was taken critical on 04/20/97 and ready to place the unit on line when the lir2 Reactor recirc pump inner seat failed. The turbine was placed on tuming gear and the reactor was manually cerammed (planned) to fully insert the remainmg withdrawn control rod drives. On 04/28/97 at 05:26; the 116 OCB tripped while trying to place the unit on line.
During "... _ "c" c. the unit was keep at 3000 RPMs until 04/29/97 at 10:59 when the turbine was placed on tummg gear and at 17:14 the reactor was manually scrammed (planned) to fully insert the remaining withdrawn control rod drives. On 06/05/97 at 18:32; The unit retumed to norrnal servicu after aR repairs wre completed. On 05/27/97 at 17:40; The unit                                               ,
During "... _ "c"
reached the "All Rods - AN Out" mode and started cost down                                           !
: c. the unit was keep at 3000 RPMs until 04/29/97 at 10:59 when the turbine was placed on tummg gear and at 17:14 the reactor was manually scrammed (planned) to fully insert the remaining withdrawn control rod drives. On 06/05/97 at 18:32; The unit retumed to norrnal servicu after aR repairs wre completed. On 05/27/97 at 17:40; The unit reached the "All Rods - AN Out" mode and started cost down towards the 1997 refuelmg outage.
towards the 1997 refuelmg outage.
(Total outage hours: 1,530.9)
(Total outage hours: 1,530.9)
L I
L I
E i
E i
1 F o Forced                    2 Reason:                                                                                  Method:                                                         kxhiNt G = Instructions for l
1 2
S = Scheduled                   A = Equipment Failure (Explain)                                                           i = Manual                                                       Pieparation of Data Entry Sheets                       f B = Maintenance of Test                                                                   2 = Manual Scram                                                 For t.icensee Event Report (LER)
Method:
C = Refueling                                                                             3 = Automatic Scram                                               File (NUREG -0161)
kxhiNt G = Instructions for F o Forced Reason:
D = Regulatory Restriction                                                               4 = Other (Explain)                                                                                                     :
l S = Scheduled A = Equipment Failure (Explain) i = Manual Pieparation of Data Entry Sheets f
E = Regu: story Restnctiori                                                                                                                                 5 Exhibit 1 = Same Source F = Administrative G = Operational Error (Explain)
B = Maintenance of Test 2 = Manual Scram For t.icensee Event Report (LER)
C = Refueling 3 = Automatic Scram File (NUREG -0161)
D = Regulatory Restriction 4 = Other (Explain)
E = Regu: story Restnctiori 5Exhibit 1 = Same Source F = Administrative G = Operational Error (Explain)
H = Other (Explain)
H = Other (Explain)
Form 3156 247
Form 3156 247


1 STATS VER* ION 97.001: EA-8-STATS-97-01           02/06/97 RE]TIMEo06/03/97 07:52:26                                                             Page 4 of 9 b
1 STATS VER* ION 97.001: EA-8-STATS-97-01 02/06/97 RE]TIMEo06/03/97 07:52:26 Page 4 of 9 b
GREY 800K OPERATING DATA REPORT
GREY 800K OPERATING DATA REPORT DOCKET NO. 50-155 DATE:
                                                                                                                                                                        ~
6/ 3 / 97
DOCKET NO. 50-155       DATE:   6/ 3 / 97 BY: JR JOHNSTON OPERATING STATUS                                                                                               PHONE: 616-547-8223
~
: 1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT                                                   NOTES:                                                           -
BY: JR JOHNSTON OPERATING STATUS PHONE: 616-547-8223
: 2. REPORTING PERIOD:     5/97
: 1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT NOTES:
: 3. LICENSED THERMAL POWER (MWT):     240
: 2. REPORTING PERIOD:
: 4. NAMEPLATE RATING (GROSS MWE):     75
5/97
      ~
: 3. LICENSED THERMAL POWER (MWT):
: 5. DESIGN ELECTRICAL RATING (NET MWE):     72
240
: 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):       71.0
~
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):     67.0
: 4. NAMEPLATE RATING (GROSS MWE):
75
: 5. DESIGN ELECTRICAL RATING (NET MWE):
72
: 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
71.0
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
67.0
: 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT. GIVE REASONS:
: 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT. GIVE REASONS:
: 9. POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
: 9. POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
: 10. REASONS FOR RESTRICTIONS IF ANY:
: 10. REASONS FOR RESTRICTIONS IF ANY:
THIS MONTH                                       YEAR-TO-DATE             CUMULATIVE
THIS MONTH YEAR-TO-DATE CUMULATIVE
: 11. HOURS IN REPORTING PERIOD                                                           744.0                     3623.0               299586.0
: 11. HOURS IN REPORTING PERIOD 744.0 3623.0 299586.0
: 12. NUMBER OF HOURS REACTDR WAS CRITICAL                                               644.5                     1398.5               217102.1
: 12. NUMBER OF HOURS REACTDR WAS CRITICAL 644.5 1398.5 217102.1
: 13. REACTDR RESERVE SHUTDOWN HOURS                                                           0.0                   0.0                   0.0
: 13. REACTDR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 14. HOURS GENERATDR ON-LINE                                                             630.5                     1311.5               213688.7
: 14. HOURS GENERATDR ON-LINE 630.5 1311.5 213688.7
: 15. UNIT RESERVE SHUTDOVN HOURS                                                               0.0                   0.0                   0.0
: 15. UNIT RESERVE SHUTDOVN HOURS 0.0 0.0 0.0
: 16. GROSS THERMAL ENERGY GENERATED (MVH)                         128084.0                                     262004.0             41436265.0
: 16. GROSS THERMAL ENERGY GENERATED (MVH) 128084.0 262004.0 41436265.0
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)                             41016.0                                 83734.0             13169403.0
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 41016.0 83734.0 13169403.0
: 18. NET ELECTRICAL ENERGY GENERATED (MWH)                               38881.4                                 79280.9             12460542.2
: 18. NET ELECTRICAL ENERGY GENERATED (MWH) 38881.4 79280.9 12460542.2
: 19. UNIT SERVICE FACTOR                                                                     84.7%                 36.2%                 71.3%
: 19. UNIT SERVICE FACTOR 84.7%
: 20. UNIT AVAILABILITY FACTOR                                                                 84.7%                 36.2%                 71.3%
36.2%
: 21. UNIT CAPACITY FACTOR (USING MDC NET)                                                     78.0%                 32.7%                 61.8%
71.3%
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                                     72.6%                 30.4%                 57.8%
: 20. UNIT AVAILABILITY FACTOR 84.7%
: 23. UNIT FORCED OUTAGE RATE                                                                 15.3%                   63.8%                 12.1%
36.2%
71.3%
: 21. UNIT CAPACITY FACTOR (USING MDC NET) 78.0%
32.7%
61.8%
: 22. UNIT CAPACITY FACTOR (USING DER NET) 72.6%
30.4%
57.8%
: 23. UNIT FORCED OUTAGE RATE 15.3%
63.8%
12.1%
: 24. SHUTD0VNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. & DURATION OF EACH): Refueling, August 31, 1997 60 days.
: 24. SHUTD0VNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. & DURATION OF EACH): Refueling, August 31, 1997 60 days.
: 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:


                                                                                                                                                                -      - .- .      -- . ~..       _ _      . ..- .          - -
. ~..
                                                                                                                                                                                                                            ~
~
1 STATS VERSIC 97.001: EA-8-STATS-97-01                                                                                 02/06/97 RUNTIME=06/03/97 07:52:26                             Ptge 2 of 9 DAY   AVERAGE DAILY POWER (MWT)                                       (MWEN)                                     ( 5/97) - CYCLE 29                                                                                       ,
1 STATS VERSIC 97.001: EA-8-STATS-97-01 02/06/97 RUNTIME=06/03/97 07:52:26 Ptge 2 of 9 DAY AVERAGE DAILY POWER (MWT)
1              0.00                                                     0.00 2               0.00                                                     0.00                                                                                                                         .
(MWEN)
3              0.00                                                     0.00 4               0.00                                                     0.00 5             14.92                                                     1.05
( 5/97) - CYCLE 29 1
* 6              68.42                                                 19.79 7             74.67                                                 21.78 8             149.46                                                 46.25 9             209.67                                                 63.95 10             219.21                                                 66.77 11             217.92                                                 66.45 12             217.79                                                 66.28 13             216.54                                                 66.04 14             217.88                                                 66.29 15             221.29                                                 67.10 16             221.92                                                 67.38 17             220.79                                                 67.43 18             222.67                                                 67.52 19             222.54                                                 67.55 20             221.83                                                 67.44 21             221.75                                                 67.27                                                                                                                                                       ,
0.00 0.00 2
22             219.96                                                 66.86 23             218.83                                                 66.71 24             219.13                                                 66.33 25             218.92                                                 66.71 26             217.88                                                 66.63 27             218.92                                                 66.43 28             217.58                                                 66.39 29             216.71                                                 66.01 30             216.17                                                 65.71 31             214.50                                                 15.43
0.00 0.00 3
                                                                    -                                                                      -              , - -  --          .,, +                   m                     -
0.00 0.00 4
e-
0.00 0.00 5
14.92 1.05 6
68.42 19.79 7
74.67 21.78 8
149.46 46.25 9
209.67 63.95 10 219.21 66.77 11 217.92 66.45 12 217.79 66.28 13 216.54 66.04 14 217.88 66.29 15 221.29 67.10 16 221.92 67.38 17 220.79 67.43 18 222.67 67.52 19 222.54 67.55 20 221.83 67.44 21 221.75 67.27 22 219.96 66.86 23 218.83 66.71 24 219.13 66.33 25 218.92 66.71 26 217.88 66.63 27 218.92 66.43 28 217.58 66.39 29 216.71 66.01 30 216.17 65.71 31 214.50 15.43
.,, +
m e-


                  ^
Refuelina information Reauest
;  ,                ,e                                                 Refuelina information Reauest
^
: 1.         Facility Name:
,e 1.
i Big Rock Point Plant                                                                                 j f                           2.         Scheduled date for next refueling shutdown:
Facility Name:
;                                                August 31,1997.
Big Rock Point Plant j
: 3.         Scheduled date for restart following shutdown:
f 2.
Scheduled date for next refueling shutdown:
August 31,1997.
3.
Scheduled date for restart following shutdown:
60 Day Duration.
60 Day Duration.
l
4.
;                            4.         Will refueling or resumption of operation thereafter require a technical specification change or               )
Will refueling or resumption of operation thereafter require a technical specification change or
)
other license amendment?
other license amendment?
.                                                No.
No.
i                                       If yes, explain:                                                                                               !
i If yes, explain:
;                                        if no, has the reload fuel design and core configuration been reviewed by Plant Safety Review Committee to determine whether any unreviewed safety questions as associated with the core reload (Reference 10 CFR, Section 50.59) ?
if no, has the reload fuel design and core configuration been reviewed by Plant Safety Review Committee to determine whether any unreviewed safety questions as associated with the core reload (Reference 10 CFR, Section 50.59) ?
To be perfom ed once core loading determined for cycle 30.
To be perfom ed once core loading determined for cycle 30.
e if no review has taken place, when is it scheduled?                                                           l
e if no review has taken place, when is it scheduled?
: 5.         Scheduled date(s) for submittal of proposed licensing action and supporting information:                       1 N/A.
5.
i                                                                                                                                                       ,
Scheduled date(s) for submittal of proposed licensing action and supporting information:
: 6.         Important licensing considerations associated with refueling, eg. new or different fuel dasign                 l
1 N/A.
}                                         or supplier, unreviewed design or performance analysis methods, significant changes in fuel j                                         design new operating procedures:
i 6.
l                                                 None.
Important licensing considerations associated with refueling, eg. new or different fuel dasign
i
}
: 7.         Number of fuel assemblies in:
or supplier, unreviewed design or performance analysis methods, significant changes in fuel j
design new operating procedures:
l None.
i 7.
Number of fuel assemblies in:
Core = 84.
Core = 84.
Spent Fuel Pool Storage = 358.
Spent Fuel Pool Storage = 358.
New Fuel Storage = 22.
New Fuel Storage = 22.
: 8.         Present licensed spent fuel pool storage capacity:
8.
Present licensed spent fuel pool storage capacity:
441 Size of any increase in licensed storage capacity that has been requested or planned (in number of fuel assemblies):
441 Size of any increase in licensed storage capacity that has been requested or planned (in number of fuel assemblies):
0                                                                                                     .
0 i
i
9.
: 9.         Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:
Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:
Last total core off load 1996.
Last total core off load 1996.
Last refueling 1999.
Last refueling 1999.
May 1,1997}}
May 1,1997}}

Latest revision as of 17:04, 11 December 2024

Monthly Operating Rept for May 1997 for Big Rock Nuclear Power Plant
ML20140C898
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 05/31/1997
From: Jeanne Johnston, Shields K
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9706100120
Download: ML20140C898 (6)


Text

- -

5

..e

@rowEmNa Consumers Power MKNWnAN'S Pit lNNtE55 June 3,1997 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sin Enclosed please find the statist; cal data for the Big Rock Point Nuclear Plant covering the period i

of May 1,1997 through May 31,1997.

j Sincerely, K J Shields Reactor Engineer Enclosures cc: Administrator Region Ill, Nuclear Regulatory Commission DR Hahn, Depariment of Enviromental Quality JR Padgett, Michigan Public Service Commission R Aben, Michigan Department of Labor MP Cass, American NuclearInsures B Lewis, McGraw-Hill,Inc.

SM McIntyre, P26-201 fg KP Powers, Big Rock Point

/ D l

GC Withrow, Big Rock Point NRC Resident inspector, Big Rock Point Document Control, Big Rock Point,740*22*15*10 File 9706100120 970531 PDR ADOCK 05000155 R

PDR

,,j A CAG ENE72GYCOMPANY

_ _ _. _ _. _ _ _. - - _. ~. _ _ -.. _. _ _ _ _..

FORM 16.3.H Operating Status Report - Nuclear Regulatory Commission 7ade k /9k2 Prepared by:

Date:

b D

R: viewed b Date:

(Reactor Er%lneer or Altemate)

Copy to be sent to the following by the seventh day of each month:

Nuclear Regulatory Commission Robert Aben, Assistant Chief Document Control Desk Bureau of Construction Codes Washington,DC 20555 Michigan Department of Labor 7150 Harris Drive, Box 30015 Lansing,MI 48909 4

Administrator American NuclearInsurers Region lli-USNRC Att: MP Cass 801 Warrenville Road Town Center, Suite 300S I

Lisle,IL 60532 4351 29 South Main Street i

West Hartford, CT 06107-2445 4

DR Hahn Barbara Lewis j

Department of Enviromental Gua!ity McGraw-Hill,Inc.

3500 North Logan 1200 G Street, N.W.

Lansing, MI 48906 Suite 1100 4

Washington,DC 20005 I

JR Padgett i

Michigan Public Service Commission PO Box 30221

{

Lansing, MI 48909 Routing Copy:

SM McIntyre, P26-201 4

KP Powers, Big Rock Point Plant CC Withrow, Big Rock Point Plant NRC Resident inspector, Big Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04) Cross Reference 16.3.3-17

.~.

causssssmarsgesygy NUCLEAR OPERATIONS DEPARTMENT Unit Shutdown and Power Reductions Report Month Docket Number Unit Date Completed by Telephone May,1997 56-160 Big Rock Point Plant June 3.1997 JR Johnston (614) 547 4 223 Method of Shuttmg Duration Down Licensee Event Systery Cy l

2 Number Date Type (Hours)

Reason p,,,,,,3 Report Number Code Code Cause and Corrective Action To Pnivent Recurrence 97 01 03/02/97 F

113.5 Hrs A

1, 2 On 034248 at 22:32; The unit was removed from service to Thru

, " _ and repair leakage from MO-7071 and/or VPl403 on

^

0646/97 the poet incedent system. ARer the unit was removed from service, the reactor was manually scrammed to fbily insert the remaining withdrawn control rod drives. Alter repairs were complete, the reactor was taken critical on 04/20/97 and ready to place the unit on line when the lir2 Reactor recirc pump inner seat failed. The turbine was placed on tuming gear and the reactor was manually cerammed (planned) to fully insert the remainmg withdrawn control rod drives. On 04/28/97 at 05:26; the 116 OCB tripped while trying to place the unit on line.

During "... _ "c"

c. the unit was keep at 3000 RPMs until 04/29/97 at 10:59 when the turbine was placed on tummg gear and at 17:14 the reactor was manually scrammed (planned) to fully insert the remaining withdrawn control rod drives. On 06/05/97 at 18:32; The unit retumed to norrnal servicu after aR repairs wre completed. On 05/27/97 at 17:40; The unit reached the "All Rods - AN Out" mode and started cost down towards the 1997 refuelmg outage.

(Total outage hours: 1,530.9)

L I

E i

1 2

Method:

kxhiNt G = Instructions for F o Forced Reason:

l S = Scheduled A = Equipment Failure (Explain) i = Manual Pieparation of Data Entry Sheets f

B = Maintenance of Test 2 = Manual Scram For t.icensee Event Report (LER)

C = Refueling 3 = Automatic Scram File (NUREG -0161)

D = Regulatory Restriction 4 = Other (Explain)

E = Regu: story Restnctiori 5Exhibit 1 = Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain)

Form 3156 247

1 STATS VER* ION 97.001: EA-8-STATS-97-01 02/06/97 RE]TIMEo06/03/97 07:52:26 Page 4 of 9 b

GREY 800K OPERATING DATA REPORT DOCKET NO. 50-155 DATE:

6/ 3 / 97

~

BY: JR JOHNSTON OPERATING STATUS PHONE: 616-547-8223

1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT NOTES:
2. REPORTING PERIOD:

5/97

3. LICENSED THERMAL POWER (MWT):

240

~

4. NAMEPLATE RATING (GROSS MWE):

75

5. DESIGN ELECTRICAL RATING (NET MWE):

72

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

71.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

67.0

8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT. GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS IF ANY:

THIS MONTH YEAR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.0 3623.0 299586.0
12. NUMBER OF HOURS REACTDR WAS CRITICAL 644.5 1398.5 217102.1
13. REACTDR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATDR ON-LINE 630.5 1311.5 213688.7
15. UNIT RESERVE SHUTDOVN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MVH) 128084.0 262004.0 41436265.0
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 41016.0 83734.0 13169403.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 38881.4 79280.9 12460542.2
19. UNIT SERVICE FACTOR 84.7%

36.2%

71.3%

20. UNIT AVAILABILITY FACTOR 84.7%

36.2%

71.3%

21. UNIT CAPACITY FACTOR (USING MDC NET) 78.0%

32.7%

61.8%

22. UNIT CAPACITY FACTOR (USING DER NET) 72.6%

30.4%

57.8%

23. UNIT FORCED OUTAGE RATE 15.3%

63.8%

12.1%

24. SHUTD0VNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. & DURATION OF EACH): Refueling, August 31, 1997 60 days.
25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

. ~..

~

1 STATS VERSIC 97.001: EA-8-STATS-97-01 02/06/97 RUNTIME=06/03/97 07:52:26 Ptge 2 of 9 DAY AVERAGE DAILY POWER (MWT)

(MWEN)

( 5/97) - CYCLE 29 1

0.00 0.00 2

0.00 0.00 3

0.00 0.00 4

0.00 0.00 5

14.92 1.05 6

68.42 19.79 7

74.67 21.78 8

149.46 46.25 9

209.67 63.95 10 219.21 66.77 11 217.92 66.45 12 217.79 66.28 13 216.54 66.04 14 217.88 66.29 15 221.29 67.10 16 221.92 67.38 17 220.79 67.43 18 222.67 67.52 19 222.54 67.55 20 221.83 67.44 21 221.75 67.27 22 219.96 66.86 23 218.83 66.71 24 219.13 66.33 25 218.92 66.71 26 217.88 66.63 27 218.92 66.43 28 217.58 66.39 29 216.71 66.01 30 216.17 65.71 31 214.50 15.43

.,, +

m e-

Refuelina information Reauest

^

,e 1.

Facility Name:

Big Rock Point Plant j

f 2.

Scheduled date for next refueling shutdown:

August 31,1997.

3.

Scheduled date for restart following shutdown:

60 Day Duration.

4.

Will refueling or resumption of operation thereafter require a technical specification change or

)

other license amendment?

No.

i If yes, explain:

if no, has the reload fuel design and core configuration been reviewed by Plant Safety Review Committee to determine whether any unreviewed safety questions as associated with the core reload (Reference 10 CFR, Section 50.59) ?

To be perfom ed once core loading determined for cycle 30.

e if no review has taken place, when is it scheduled?

5.

Scheduled date(s) for submittal of proposed licensing action and supporting information:

1 N/A.

i 6.

Important licensing considerations associated with refueling, eg. new or different fuel dasign

}

or supplier, unreviewed design or performance analysis methods, significant changes in fuel j

design new operating procedures:

l None.

i 7.

Number of fuel assemblies in:

Core = 84.

Spent Fuel Pool Storage = 358.

New Fuel Storage = 22.

8.

Present licensed spent fuel pool storage capacity:

441 Size of any increase in licensed storage capacity that has been requested or planned (in number of fuel assemblies):

0 i

9.

Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:

Last total core off load 1996.

Last refueling 1999.

May 1,1997