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                                                                        Enclosure 1
c.
Enclosure 1
,
,
  ..
,
                                                                                                        .
..
                                            APPENDIX                         SALP 7
.
                                        SALP BOARD REPORT
APPENDIX
                                  NUCLEAR REGULATORY COMMISSION                                         .
SALP 7
                                          REGION III
SALP BOARD REPORT
                          SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE'
NUCLEAR REGULATORY COMMISSION
                                          50-155/87001
.
                                      Inspection Report No.
REGION III
                                    Consumers Power Company
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE'
                                        Name of 1.icensee
50-155/87001
Inspection Report No.
Consumers Power Company
Name of 1.icensee
!
!
!                                     Big Rock Point Plant
!
                                        Name of Facility
Big Rock Point Plant
Name of Facility
i
i
l                             April 1, 1986 through August 31, 1987
l
!                                       Assessment Period
April 1, 1986 through August 31, 1987
!
Assessment Period
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      @              renc.co
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Enclosure 1
.
.
                                                                              Enclosure 1
.
.
            A. Summary of Meeting with Consumers Power Company on December 21, 1987
A.
              The findings and conclusions of the SALP board documented in Inspection
Summary of Meeting with Consumers Power Company on December 21, 1987
              Report No. 50-155/87001 were discussed with the licensee on December 21,
The findings and conclusions of the SALP board documented in Inspection
              1987, in Charlevoix, Michigan. The 11censee's regulatory performance
Report No. 50-155/87001 were discussed with the licensee on December 21,
              was presented and found acceptable in each fJnctional area.
1987, in Charlevoix, Michigan.
              The following licensee and NRC personnel attended the meeting.
The 11censee's regulatory performance
              Consumers Power Company
was presented and found acceptable in each fJnctional area.
              F. Buckman, Vice President Nuclear Operations
The following licensee and NRC personnel attended the meeting.
              G. Slade, Executive Director for Nuclear Assurance
Consumers Power Company
              R. Abel, Production and Plant Performance Superintendent
F. Buckman, Vice President Nuclear Operations
              R. Alexander, Technical Engineer
G. Slade, Executive Director for Nuclear Assurance
              J. Beer, Chemistry / Health Physics Superintendent
R. Abel, Production and Plant Performance Superintendent
              M. Sralinski, Senior Engineer
R. Alexander, Technical Engineer
              W. Blosh, Maintenance Engineer
J. Beer, Chemistry / Health Physics Superintendent
              G. Boss, A0
M. Sralinski, Senior Engineer
              T. Hagan, Human Resources Director
W. Blosh, Maintenance Engineer
              C. Macinski, Plant Public Affairs Director
G. Boss, A0
              0. Moeggenberg, Engineering Supervisor
T. Hagan, Human Resources Director
              G. Petitjean, Planning / Administrative Services Superintendent
C. Macinski, Plant Public Affairs Director
              E. Reciborski, Scheduling Administrator
0. Moeggenberg, Engineering Supervisor
              R. Schrader, Electrical I&C Engineering Supervisor
G. Petitjean, Planning / Administrative Services Superintendent
              W. Trubilowicz, Operations Superintendent
E. Reciborski, Scheduling Administrator
              M. Vankist, Property Protection Supervisor
R. Schrader, Electrical I&C Engineering Supervisor
              G. Withrow, Engineering Maintenance Superintendent
W. Trubilowicz, Operations Superintendent
              R. Suchmar, Nuclear Plant Training Administrator
M. Vankist, Property Protection Supervisor
              A. 'lrickenberger, Quality Control Supervisor
G. Withrow, Engineering Maintenance Superintendent
              P. Donnelly, Nuclear Assurance Administrator
R. Suchmar, Nuclear Plant Training Administrator
              L. Monshor, Quality Assurance Superintendent
A. 'lrickenberger, Quality Control Supervisor
              Ny: lear Regulatory Commission
P. Donnelly, Nuclear Assurance Administrator
              W. Guldemond, Chief, Reactor Projects Branch 2
L. Monshor, Quality Assurance Superintendent
              I. d. Jackiw, Chief, Reactor Projects Branch 28
Ny: lear Regulatory Commission
              S. Guthrie, Senior Resident Inspector
W. Guldemond, Chief, Reactor Projects Branch 2
              C. Papriello, Deputy Regional Administrator
I. d. Jackiw, Chief, Reactor Projects Branch 28
            B. Comments Rece*ved from Licensee
S. Guthrie, Senior Resident Inspector
              By let'.er dated January 20, 1988, the licensee provided written comments
C. Papriello, Deputy Regional Administrator
              on the SALP report in accordance with the forwarding letter.
B.
              In regards to the comments relative to Section IV.B., "Radiological
Comments Rece*ved from Licensee
              Controls," the staff reviewed the issue of failed fuel and cancelled
By let'.er dated January 20, 1988, the licensee provided written comments
              inspection on fuel bundles scheduled for return to the reactor core.
on the SALP report in accordance with the forwarding letter.
              Resolution of this concern involved several conference cells to address
In regards to the comments relative to Section IV.B., "Radiological
                                                      2
Controls," the staff reviewed the issue of failed fuel and cancelled
inspection on fuel bundles scheduled for return to the reactor core.
Resolution of this concern involved several conference cells to address
2


      - '   '
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          .
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                                                                            Enclosure 1
.
  .
,
Enclosure 1
.
v
v
              the testing necessary to determine that no leaking fuel bundles were
the testing necessary to determine that no leaking fuel bundles were
              returned to service. Your eventual ultrasonic testing of fuel bundles
returned to service.
              being returned to the core satisfied our concerns in this area. Based
Your eventual ultrasonic testing of fuel bundles
              on cur review of the information on gaseous releases, the report will
being returned to the core satisfied our concerns in this area. Based
              be corrected to reflect the following:
on cur review of the information on gaseous releases, the report will
                    As a result of continuing fuel cladding problems, radioactive
be corrected to reflect the following:
                    gaseous releases until March 1987, when the fuel problem was
As a result of continuing fuel cladding problems, radioactive
                    corrected, continued to be about a factor of 6 higher .   ...
gaseous releases until March 1987, when the fuel problem was
              In regards to the comments relative to Section IV.C., "Maintenance,"
corrected, continued to be about a factor of 6 higher .
              we accept your comments as they relate to EEQ and Appendix R.       Concerning
...
              the effectiveness of mainte,ance programs at Big Rock Point, the staff
In regards to the comments relative to Section IV.C., "Maintenance,"
              remains concerned that the current level of preventive, predictive, and
we accept your comments as they relate to EEQ and Appendix R.
              corrective maintenance at the facility may be only marginally adequate to
Concerning
              counter the effects of equipment aging and normal plant wear. The staff
the effectiveness of mainte,ance programs at Big Rock Point, the staff
              encourages you to continue to emphasize your preventive and predictive
remains concerned that the current level of preventive, predictive, and
              maintenance effort toward the goal of enhanced plant safety through such
corrective maintenance at the facility may be only marginally adequate to
              activities as pump overhauls.
counter the effects of equipment aging and normal plant wear. The staff
              In regards to the comments relative to Section IV.D., "Surveillance,"
encourages you to continue to emphasize your preventive and predictive
              the staff scknowledges your clarification of the status of the battery
maintenance effort toward the goal of enhanced plant safety through such
              service test. The inaccuracy in Paragraph 3 has been deleted from the
activities as pump overhauls.
              SALP report. The following statement has been deleted:
In regards to the comments relative to Section IV.D., "Surveillance,"
                    One surveillance on the station battery was not performed while
the staff scknowledges your clarification of the status of the battery
                    the requirement for its performance was under review by NRR.
service test. The inaccuracy in Paragraph 3 has been deleted from the
              In regards to the comments relative to Section IV.K., "Training and
SALP report. The following statement has been deleted:
              Qualificatior. Effectiveness," the staff appreciates the additional data
One surveillance on the station battery was not performed while
              you provided to describe the improvements made in upgrading the skills of
the requirement for its performance was under review by NRR.
              the mechanical / electrical maintenance staff. Based on our review of that
In regards to the comments relative to Section IV.K., "Training and
              information the report will be amended to reflect the following:
Qualificatior. Effectiveness," the staff appreciates the additional data
                    Skills training was generally conducted on schedule with only minimal
you provided to describe the improvements made in upgrading the skills of
                    impact from plant operations.
the mechanical / electrical maintenance staff.
                    Significant increase in training man-days were in evidence when
Based on our review of that
                    compared to the training effort during the previous assessment period.
information the report will be amended to reflect the following:
              The staff continues to regard skill training and worker protection training
Skills training was generally conducted on schedule with only minimal
              to be of a general nature and not sufficiently nuclear plant specific to
impact from plant operations.
              be of immediate benefit in upgrading the effectiveness of the newest
Significant increase in training man-days were in evidence when
              members of the mechanical / electrical maintenance staff. A review of the
compared to the training effort during the previous assessment period.
              CPC0 Training Records System Employee Training Report updated through
The staff continues to regard skill training and worker protection training
              January 4, 1988, for the five mcst recent additions to the maintenance
to be of a general nature and not sufficiently nuclear plant specific to
              staff indicate that the training provided these individuals during the
be of immediate benefit in upgrading the effectiveness of the newest
              assessment period heavily emphasized worker safety.     Examples include the
members of the mechanical / electrical maintenance staff. A review of the
                                                      3
CPC0 Training Records System Employee Training Report updated through
January 4, 1988, for the five mcst recent additions to the maintenance
staff indicate that the training provided these individuals during the
assessment period heavily emphasized worker safety.
Examples include the
3


                                                                                      _ _ _ _ _ _ _ _______________________ _ _ _
_ _ _ _ _
                                                                                                                                                          - _ _ -
_
      * *     '
_ _______________________ _ _ _
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- _ _ -
    .
* *
              -
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                                                                                                                                              Enclosure 1
Enclosure 1
                                    .
-
  .
.
l                   confined spaces and fire brigade training, protective tagging procedures,
,
                    asbestos control, and respirator use.                         During the last month of the
.
                    assessment period, the individual's course work began to emphasize general
.
                    skills through training courses emphasizing introduction to valves,
l
                    introduction to blue prints, hand tools, power tools, electrical math, and
confined spaces and fire brigade training, protective tagging procedures,
                    basic DC electricity. Big Rock Point System training for these and other
asbestos control, and respirator use.
                    individuals commenced August 17, 1987, two weeks prior to the close of
During the last month of the
                    the assessment period.
assessment period, the individual's course work began to emphasize general
                    In regards to the comments relative to Section IV.E., "Fire Protection,"
skills through training courses emphasizing introduction to valves,
                    Section IV.G., Security, Section IV.K., Licensing Activities, we
introduction to blue prints, hand tools, power tools, electrical math, and
                    acknowledge your comments and these facts will be factored into the
basic DC electricity.
                    SALP 8 assessment period.
Big Rock Point System training for these and other
                  C. Regional Administrator's Conclusions Based on Consideration of
individuals commenced August 17, 1987, two weeks prior to the close of
                    Licensee Comments
the assessment period.
                    Based on my review of the comments provided by the licensee, I have
In regards to the comments relative to Section IV.E., "Fire Protection,"
                    concluded that the overall ratings in the affected areas have not
Section IV.G., Security, Section IV.K., Licensing Activities, we
                    changed. Actions identified in the letter of response to SALP 7 dated
acknowledge your comments and these facts will be factored into the
                    January 20, 1988 will be factored into future Region III inspections.
SALP 8 assessment period.
C.
Regional Administrator's Conclusions Based on Consideration of
Licensee Comments
Based on my review of the comments provided by the licensee, I have
concluded that the overall ratings in the affected areas have not
changed. Actions identified in the letter of response to SALP 7 dated
January 20, 1988 will be factored into future Region III inspections.
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                                  Consum8Is
Consum8Is
                                  POW 8r                                                       Fr.a. rick w sockm.n
POW 8r
                                                                                              Srmor Vue Pressdent
Fr.a. rick w sockm.n
                                POWERING                                                     Ewty Supply
Srmor Vue Pressdent
                MICNIGAN'S PROGRE55
POWERING
                Generst Omces 1945 West Parnell Road. Jackson. MI 49201 e (517) 7881217
Ewty Supply
                January 20, 1988
MICNIGAN'S PROGRE55
                Nuclear Regulatory Commission
Generst Omces 1945 West Parnell Road. Jackson. MI 49201 e (517) 7881217
                Document Control Desk
January 20, 1988
                Washington, DC 20555
Nuclear Regulatory Commission
                DOCKET 50-155 - LICENSE DPR-6 - BIG ROCK POINT PLANT -
Document Control Desk
                SALP 7 REPORT C0KKENTS
Washington, DC 20555
                Consumers Power Company appreciates NRC effort in assessing the nerformance of
DOCKET 50-155 - LICENSE DPR-6 - BIG ROCK POINT PLANT -
                Big Rock Point during the SALP 7 period. Of special note was Mr. Paperiello
SALP 7 REPORT C0KKENTS
                and the SALP Board holding the presentation in Charlevoix, Michigan, which
Consumers Power Company appreciates NRC effort in assessing the nerformance of
                permitted an increased attendance of Consumers Power Company personnel responsi-
Big Rock Point during the SALP 7 period. Of special note was Mr. Paperiello
                                                                                                                    *
and the SALP Board holding the presentation in Charlevoix, Michigan, which
                ble for the operation of Big Rock Point. The direct communication was a
permitted an increased attendance of Consumers Power Company personnel responsi-
                valuable part of the overall SALP process, and it will assist us in planning
ble for the operation of Big Rock Point. The direct communication was a
                future strategies and activities to achieve excellence in performance.
*
                Following the presentation and review of the SALP 7 Report, Consumers Power
valuable part of the overall SALP process, and it will assist us in planning
                Company provides the following com=cr.ts.
future strategies and activities to achieve excellence in performance.
                A. Plant Operations
Following the presentation and review of the SALP 7 Report, Consumers Power
                    No Co= cents.
Company provides the following com=cr.ts.
4              B. Radiological Controls
A. Plant Operations
                    Unresponsiveness to NRC initiatives and concerns for fuel inspections was
No Co= cents.
                    never our intent. Only after carefully examining previous cycles' fuel
B. Radiological Controls
                    failures, current indicators, and personnel doses was the decision made not
4
                    to inspect fuel. We were confident that the fuel causing the failures was
Unresponsiveness to NRC initiatives and concerns for fuel inspections was
                    being discharged and not used in Cycle 22. In the spirit of ALARA, the
never our intent. Only after carefully examining previous cycles' fuel
                    possibility was great for receiving more dose from fuel inspections than
failures, current indicators, and personnel doses was the decision made not
                    the fuel failures we had been experiencing. Results of ultrasonic inspections
to inspect fuel. We were confident that the fuel causing the failures was
                    and next cycle performance substantiated our original evaluation that all
being discharged and not used in Cycle 22.
4                  leaker bundles were discharged. Paragraph six (6) of this section incorrectly
In the spirit of ALARA, the
                    refers to "... gaseous releases... continued to be about a factor of 6 higher
possibility was great for receiving more dose from fuel inspections than
                    than normal." After the Cycle 22 Refueling Outage (March, 1987) gaseous
the fuel failures we had been experiencing. Results of ultrasonic inspections
                    release rate was restored to normal and currently no leaking fuel is
and next cycle performance substantiated our original evaluation that all
                    evident.
leaker bundles were discharged. Paragraph six (6) of this section incorrectly
                    It is true that a water chemistry control program based on BWR Ovners Group
4
                    Guidelines was not formalized, however, virtually every chemistry parameter
refers to "... gaseous releases... continued to be about a factor of 6 higher
                    is within these guidelines and we feel confident that plant management
than normal." After the Cycle 22 Refueling Outage (March, 1987) gaseous
                    would take the appropriate measures if these parameters were above the
release rate was restored to normal and currently no leaking fuel is
                OC0188-0016-NLO2
evident.
                                                                    [
It is true that a water chemistry control program based on BWR Ovners Group
                          / +' '         "
Guidelines was not formalized, however, virtually every chemistry parameter
                                                1(                       p/                    UAN22 088
is within these guidelines and we feel confident that plant management
            9@t v
would take the appropriate measures if these parameters were above the
              - --
OC0188-0016-NLO2
                                  <'                        mglhenarwuwn
[ p/
UAN22 088
9@t v
/ +' '
1(
"
mglhenarwuwn
<'
- --


                                                                  _ _ _ _ _ _ _ _ .
_ _ _ _ _ _ _ _ .
          *
*
  -
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,.
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*
                Nuclear Regulatory Commission                                               2
.
                Big Rock Point Plant
Nuclear Regulatory Commission
  ,
2
                ? ALP 7 Report Comments
Big Rock Point Plant
                January 20, 1988
? ALP 7 Report Comments
                  "action levels" of the guidelines even though they were not procedura11 zed.
,
                  The applicable guidelines will be incorporated into plant procedures over
January 20, 1988
                  the next procedure review cycle.
"action levels" of the guidelines even though they were not procedura11 zed.
                  We note NRC concerns and have implemented improvements in the ALARA and
The applicable guidelines will be incorporated into plant procedures over
                  Radiation Work Permit programs and frisking equipment / practices since the
the next procedure review cycle.
                  assessment, and will continue efforts to further reduce dose and contamin-
We note NRC concerns and have implemented improvements in the ALARA and
                  ation incidents.
Radiation Work Permit programs and frisking equipment / practices since the
                C. Maintenance
assessment, and will continue efforts to further reduce dose and contamin-
                  Consumers Power Company utilized extensive resources in establishing a
ation incidents.
                  "good f aith" ef fort in complying with the EEQ and Appendix R regulations.
C. Maintenance
                  However, both the EEQ and Appendix R efforts evolved over a very long time
Consumers Power Company utilized extensive resources in establishing a
                  period allowing program managers, both Consumers Power Company and NRC, to
"good f aith" ef fort in complying with the EEQ and Appendix R regulations.
                  change during program development and compliance rTriew. Decisions or
However, both the EEQ and Appendix R efforts evolved over a very long time
                  compliance interpretations agreed upon at one stage have been changed or
period allowing program managers, both Consumers Power Company and NRC, to
                  modified by individuals involved at later time periods. Consumers Povet
change during program development and compliance rTriew. Decisions or
                  Company originally was involved in EEQ since 1975, with a LOCA task force,
compliance interpretations agreed upon at one stage have been changed or
                  followed with the RDS Modifications, and with the Systematic Evaluation     ,
modified by individuals involved at later time periods. Consumers Povet
                  Program in the late seventies. Implementation Inspections did not commence
Company originally was involved in EEQ since 1975, with a LOCA task force,
                  until 1986. We believe this contributed to the EEQ issues dealing with
followed with the RDS Modifications, and with the Systematic Evaluation
                  MO-7068 and Polyethylene and Butyl rubber cables. Consumers Power Company
,
                  still believes that M0-7068 and the cables were capable of performing their
Program in the late seventies. Implementation Inspections did not commence
                  safety function, however, we agreed to replace the components rather than
until 1986. We believe this contributed to the EEQ issues dealing with
                  continuing to debate the issues.
MO-7068 and Polyethylene and Butyl rubber cables. Consumers Power Company
                  Big Rock Point continues to have an effective maintenance performance
still believes that M0-7068 and the cables were capable of performing their
                  history as evidenced by historical plant availability and number of forced
safety function, however, we agreed to replace the components rather than
                  outages. Reactor trips from power have been minimal and the plant material
continuing to debate the issues.
                  condition has been noted as very good by the NRC, INPO, and Insurance
Big Rock Point continues to have an effective maintenance performance
                  Inspectors. During this SALP period Big Rock Point initiated and recently
history as evidenced by historical plant availability and number of forced
                  completed a Maintenance Self-Assessment utilizing INPO guidelines.
outages. Reactor trips from power have been minimal and the plant material
                  Throughout the next SALP period we will be implementing changes in our
condition has been noted as very good by the NRC, INPO, and Insurance
                  Maintenance Programs to improve the high priority areas identified in the
Inspectors. During this SALP period Big Rock Point initiated and recently
                    self-assessment. These will further strengthen our maintenance performance.
completed a Maintenance Self-Assessment utilizing INPO guidelines.
                    In addition, several major pump and motor overhauls are planned for the
Throughout the next SALP period we will be implementing changes in our
                  upcoming refueling outage. The main feedvater pumps, turbine / generator,
Maintenance Programs to improve the high priority areas identified in the
                    and a service water pump have been completed in the recent past. Over the
self-assessment. These will further strengthen our maintenance performance.
                    next few years, two to three major pump overhauls per year are planned.
In addition, several major pump and motor overhauls are planned for the
                    Big Rock Point will continue to monitor equipment performance and industry
upcoming refueling outage. The main feedvater pumps, turbine / generator,
                  maintenance practices toward enhancing existing Maintenance programs.
and a service water pump have been completed in the recent past. Over the
                D. Surveillance
next few years, two to three major pump overhauls per year are planned.
                    One inaccuracy existed in paragraph 3 of this section with regard to not
Big Rock Point will continue to monitor equipment performance and industry
                    performing a surveillance test (Service Test) on the station battery. A
maintenance practices toward enhancing existing Maintenance programs.
                    Technical Specification Change Request submittal dated December 22, 1986,
D. Surveillance
                    which is still under NRR review, modified the Service Test design time
One inaccuracy existed in paragraph 3 of this section with regard to not
                    interval to resolve errors as described in LER 86-004. Consumers Power
performing a surveillance test (Service Test) on the station battery. A
                OC0188-0016-NLO2
Technical Specification Change Request submittal dated December 22, 1986,
which is still under NRR review, modified the Service Test design time
interval to resolve errors as described in LER 86-004. Consumers Power
OC0188-0016-NLO2
__
__


    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
                                *
*
  .
.
              .
.
                                                              ,.
,.
                                                                                  Nucicar Rsgulatory Ccmmission                                                 3
Nucicar Rsgulatory Ccmmission
                                                                                  Big Rock Point Plant
3
                                                                                  SALP 7 Report Comments
Big Rock Point Plant
                                                                                  January 20, 1988
SALP 7 Report Comments
  '
'
                                                                                      Company agreed to impleaent this proposal into testing scheduled for the
January 20, 1988
                                                                                      1987 Refueling Outage. The modified surveillance test was completed
Company agreed to impleaent this proposal into testing scheduled for the
                                                                                      satisfactorily during the outage.
1987 Refueling Outage. The modified surveillance test was completed
                                                                                  E. Fire Protection
satisfactorily during the outage.
                                                                                      The NRC concern on lack of plant staff Appendix R understanding is related
E. Fire Protection
                                                                                      to the duration of the review and implementation. As discussed above in
The NRC concern on lack of plant staff Appendix R understanding is related
                                                                                      Section C, the effort extended over a long time period (approximately
to the duration of the review and implementation. As discussed above in
                                                                                      1978-1986). Because of the long time interval the need existed for several
Section C, the effort extended over a long time period (approximately
                                                                                      technical-level meetings with staff and consultant personnel to revice
1978-1986).
                                                                                      extensive submittals to understand the safe shutdown paths for Big Rock
Because of the long time interval the need existed for several
                                                                                      Point in complying with the Appendix R requirements. Although further NRR
technical-level meetings with staff and consultant personnel to revice
                                                                                      review was needed and one additional exemption was required, overall the
extensive submittals to understand the safe shutdown paths for Big Rock
                                                                                      post-fire safe shutdown methods met the requirements for Appendix R. Since
Point in complying with the Appendix R requirements. Although further NRR
                                                                                      the inspection, documentation has been improved and fire plans strengthened
review was needed and one additional exemption was required, overall the
                                                                                      to enhance the capability of Big Rock Point to mitigate the effects of a
post-fire safe shutdown methods met the requirements for Appendix R.
                                                                                      plant fire.
Since
                                                                                  F. Emergency Preparedness                                                       ,
the inspection, documentation has been improved and fire plans strengthened
                                                                                      No coc=ents.
to enhance the capability of Big Rock Point to mitigate the effects of a
                                                                                  G. Security
plant fire.
                                                                                      In response to NRC concerns regarding equipment aging, the 1987 CCTV
F. Emergency Preparedness
                                                                                      Upgrade Project was completed by year-end. Existing equipment was repaired,
                                                                                      cleaned or replaced. Two additional CCTV cameras and new lights were
                                                                                      installed and some existing lights were repositioned. A new metal detector
                                                                                      and X-ray machine were purchased for installation in the Lobby of the
                                                                                      Security Building.
                                                                                      In response to NRC concerns regarding an increase in personnel errors,
                                                                                      several methods of monitoring personnel performance have been initiated in
                                                                                      an effort to identify exceptional as well as weak performance. These
                                                                                      methods allow trending errors and pinpointing the causes. Each First
                                                                                      Lieutenant on shift is now committed to evaluating his shift personnel on a
                                                                                      weekly basis and documenting the results on a "Personnel Evaluation Form."
                                                                                      They are committed to one planned and one unplanned evaluation each week.
                                                                                      Drills are conducted twice per month on each shift using adopted scenarios
                                                                                      for contingencies.    Individuals with recurring performance problems are
                                                                                      retrained when needed and counseled or disciplined when applicable.
                                                                                      A new method of reviewing Logs has been established to track documentation
                                                                                      errors. This will ensure that proper logging is being accomplished.
                                                                                      A full review of all site security manuals and routine job information
                                                                                      sheets is being implemented to improve performance in the Security area.
,
,
                                                                                  OC0188-0016-NLO2
No coc=ents.
G. Security
In response to NRC concerns regarding equipment aging, the 1987 CCTV
Upgrade Project was completed by year-end. Existing equipment was repaired,
cleaned or replaced. Two additional CCTV cameras and new lights were
installed and some existing lights were repositioned. A new metal detector
and X-ray machine were purchased for installation in the Lobby of the
Security Building.
In response to NRC concerns regarding an increase in personnel errors,
several methods of monitoring personnel performance have been initiated in
an effort to identify exceptional as well as weak performance. These
methods allow trending errors and pinpointing the causes. Each First
Lieutenant on shift is now committed to evaluating his shift personnel on a
weekly basis and documenting the results on a "Personnel Evaluation Form."
They are committed to one planned and one unplanned evaluation each week.
Drills are conducted twice per month on each shift using adopted scenarios
for contingencies.
Individuals with recurring performance problems are
retrained when needed and counseled or disciplined when applicable.
A new method of reviewing Logs has been established to track documentation
errors. This will ensure that proper logging is being accomplished.
A full review of all site security manuals and routine job information
sheets is being implemented to improve performance in the Security area.
,
OC0188-0016-NLO2


  .
.
    .-
.-
'
'
      Nuc1 Gar Regulatcry Commission                                               4
Nuc1 Gar Regulatcry Commission
      Big Rock Point Plant
4
      SALP 7 Report Comments
Big Rock Point Plant
SALP 7 Report Comments
January 20, 1988
.
.
      January 20, 1988
H. Outages
      H. Outages
No comments.
          No comments.
I, Quality Programs and Administrative Controls Affecting Quality
      I, Quality Programs and Administrative Controls Affecting Quality
No comments.
          No comments.
J. Training and Qualification Effectiveness
      J. Training and Qualification Effectiveness
Training and Qualification Effectiveness was evaluated as a category 2 - a
          Training and Qualification Effectiveness was evaluated as a category 2 - a
rating judged equivalent in performance to the previous assessment period
          rating judged equivalent in performance to the previous assessment period
which at that time had received a category 1 rating. While we do not take
          which at that time had received a category 1 rating. While we do not take
issue with the lowering of a previously assessed category, a review of the
          issue with the lowering of a previously assessed category, a review of the
training results completed during this SALP period leads us to conclude
          training results completed during this SALP period leads us to conclude
training warrants a category 1 assessment.
          training warrants a category 1 assessment.
In response to the statement "While employees received some general worker
          In response to the statement "While employees received some general worker
training and on-the-job instruction, management made little progress in
          training and on-the-job instruction, management made little progress in
upgrading the mechanical / electrical staff's skill levels, a condition noted
          upgrading the mechanical / electrical staff's skill levels, a condition noted ,
,
          in the previous assessment period" on page 10 under maintenance summary; we
in the previous assessment period" on page 10 under maintenance summary; we
          believe that maintenance training has been aggressively pursued. We have
believe that maintenance training has been aggressively pursued. We have
          doubled the training time per repairworker from SALP 6 to SALP 7. During
doubled the training time per repairworker from SALP 6 to SALP 7.
          the SALP 7 period, we provided 443 student days of Mechanical / Electrical
During
          skills training and 108 student days of Safety training. This is a signif-
the SALP 7 period, we provided 443 student days of Mechanical / Electrical
          icant investment of time dedicated for upgrading the skills of a maintenance
skills training and 108 student days of Safety training. This is a signif-
          staff of 14 repairmen. All of this instruction time was dedicated to
icant investment of time dedicated for upgrading the skills of a maintenance
          strengthening the skills of our maintenance staff. This represents an
staff of 14 repairmen. All of this instruction time was dedicated to
          investment of 13% of the repairmen's time for training.
strengthening the skills of our maintenance staff. This represents an
          We do not concur with the statement "Skill training that was scheduled
investment of 13% of the repairmen's time for training.
          during the assessment period was frequently cancelled because of plant
We do not concur with the statement "Skill training that was scheduled
          activities..." on page 22 under the training summary. Our records indicate
during the assessment period was frequently cancelled because of plant
          that there were no cancellations. There vae some rescheduling of courses,
activities..." on page 22 under the training summary. Our records indicate
          but all courses originally scheduled were eventually completed.     The
that there were no cancellations. There vae some rescheduling of courses,
          percentage of courses required to be rescheduled was relatively low at 7.6%
but all courses originally scheduled were eventually completed.
          for the entire SALP 7 period, and was due to unforeseen plant outages.
The
          Also, on page 22 of the training suc=ary, further clarification is in order
percentage of courses required to be rescheduled was relatively low at 7.6%
          in response to the statement "Skill training and worker protection training
for the entire SALP 7 period, and was due to unforeseen plant outages.
          was too general, not nuclear plant specific, and did little to enhance the
Also, on page 22 of the training suc=ary, further clarification is in order
          effectiveness of the maintenance stafi". Skills training is not always
in response to the statement "Skill training and worker protection training
          required to be nuclear plant specific, however during the period, 121
was too general, not nuclear plant specific, and did little to enhance the
          student days of Big Rock Point specific training was provided to the
effectiveness of the maintenance stafi".
          maintenance staff. It should also be noted that all of the tasks required
Skills training is not always
          of the Maintenance repairmen were addressed via classroom training,
required to be nuclear plant specific, however during the period, 121
          on-the-job training, and shop practices during the SALP 7 period. During
student days of Big Rock Point specific training was provided to the
          the SALP 7 peried, a major effort was made to modify training materials to
maintenance staff.
          assure that all tasks were addressed as identified on the Big Rock Point
It should also be noted that all of the tasks required
          Plant Specific Task List. It is recognized that additional systems training
of the Maintenance repairmen were addressed via classroom training,
          is necessary for improved worker understanding and performance. At the end
on-the-job training, and shop practices during the SALP 7 period. During
      OC0188-0016-NLO2
the SALP 7 peried, a major effort was made to modify training materials to
assure that all tasks were addressed as identified on the Big Rock Point
Plant Specific Task List.
It is recognized that additional systems training
is necessary for improved worker understanding and performance. At the end
OC0188-0016-NLO2


                                                            .                                   __
.
        .- ,.
__
      ,
.-
    .
,.
              Nuclear Regulatory Commission                                             5
,
              Big Rock Point Plant
.
    .
Nuclear Regulatory Commission
              SALP 7 Report Comments
5
              January 20, 1988
Big Rock Point Plant
SALP 7 Report Comments
.
January 20, 1988
2
2
                of the SALP period the second round of systems training was started for the
of the SALP period the second round of systems training was started for the
                least senior repairworkers at the plant.
least senior repairworkers at the plant.
                Finally, on page 22, the statement "The Procedural requirements for both
Finally, on page 22, the statement "The Procedural requirements for both
                required and on-the-job training were not met and the Maintenance Depart-
required and on-the-job training were not met and the Maintenance Depart-
                ment Training Program has not been evaluated and accredited by INP0" is
ment Training Program has not been evaluated and accredited by INP0" is
                somewhat misleading.   INP0 evaluation and accreditation was not planned to
somewhat misleading.
                occur during this SALP period. The INPO evaluation was conducted in
INP0 evaluation and accreditation was not planned to
                October 1987 and after the fourteen man team completed their evaluation
occur during this SALP period. The INPO evaluation was conducted in
                they. proposed zero recom=endations in maintenance training. INFO considered
October 1987 and after the fourteen man team completed their evaluation
                the program to be very good and stated our program demonstrated a strong
they. proposed zero recom=endations in maintenance training.
                commitment by the plant. Essentially all of the procedural requirements
INFO considered
                for classroom and OJT were complete and in place prior to the end of the
the program to be very good and stated our program demonstrated a strong
                SALP 7 period. Formal INPO Board approval is tentatively scheduled to
commitment by the plant. Essentially all of the procedural requirements
                occur in the first quarter 1988.
for classroom and OJT were complete and in place prior to the end of the
                We also reiterate the fact that initial or replacement license candidate     ,
SALP 7 period. Formal INPO Board approval is tentatively scheduled to
                and requalification license candidate classes both achieved a 100% pass
occur in the first quarter 1988.
                rate during the SALP period. This is the sixth license class to achieve a
We also reiterate the fact that initial or replacement license candidate
                100% pass rate.   It is a ree-r' we are very proud of and speaks for itself
,
                  s to the caliber of Big Roo 'oint training.
and requalification license candidate classes both achieved a 100% pass
                We believe the above results demonstrate that management commitment to
rate during the SALP period. This is the sixth license class to achieve a
                training is evident to assure that our training provides the skills and
100% pass rate.
                knowledge necessary to continue to operate Big Rock Point as a safe and
It is a ree-r' we are very proud of and speaks for itself
                reliable plant. We also believe : hat the training results completed during
s to the caliber of Big Roo 'oint training.
                the SALP 7 period supports a Category 1 assessment.
We believe the above results demonstrate that management commitment to
              K. Licensing Activities
training is evident to assure that our training provides the skills and
                Consumers Power Company Management and staff will continue to support and
knowledge necessary to continue to operate Big Rock Point as a safe and
                utilize the Integrated Living Schedule (ILS) in accordance with License
reliable plant. We also believe : hat the training results completed during
                requirements to evaluate and prioritize workload. We also plan on working
the SALP 7 period supports a Category 1 assessment.
                with Region III personnel in the near term, on exploring ways to use the
K. Licensing Activities
                ILS process in prioritizing inspection based plant betterments.
Consumers Power Company Management and staff will continue to support and
                Consumers Power Company understands that high quality and timely licensing
utilize the Integrated Living Schedule (ILS) in accordance with License
                documents are essential in maintaining a sound licensing basis for Big Rock
requirements to evaluate and prioritize workload. We also plan on working
                Point and continue to support this objective. Corporate and plant licensing       ,
with Region III personnel in the near term, on exploring ways to use the
                personnel will continue to advocate frequent meetings with NRR and Region
ILS process in prioritizing inspection based plant betterments.
                personnel to understand and prioritize issues from both a NRC and Consumers
Consumers Power Company understands that high quality and timely licensing
                Power Company perspective. Our goal will be to recognize unique or complex
documents are essential in maintaining a sound licensing basis for Big Rock
                  technical issues and ensure that related submittals are timely with suf-
Point and continue to support this objective. Corporate and plant licensing
                  ficient detail to minimize interaction.
,
              OC0188-0016-NLO2
personnel will continue to advocate frequent meetings with NRR and Region
__
personnel to understand and prioritize issues from both a NRC and Consumers
Power Company perspective. Our goal will be to recognize unique or complex
technical issues and ensure that related submittals are timely with suf-
ficient detail to minimize interaction.
OC0188-0016-NLO2
__


                  -- .           .
-- .
  .       .
.
  -
.
      .
.
            ,.
-
    .
.
                Nuclear Regulctory Commissien                                               6
,.
                  Big Rock Point Plant
.
  '
Nuclear Regulctory Commissien
                  SALP 7 Report Comments
6
                January 20, 1988
Big Rock Point Plant
                Consumers Power Company believes the overs 11 SALP evaluation presented a
SALP 7 Report Comments
                balanced assessment of plant performance during the appraisal period. The
'
                issue concerning resource allocation that was raised in the SALP report is one
January 20, 1988
                to which we vill remain sensitive, but Consumers Power Company strongly
Consumers Power Company believes the overs 11 SALP evaluation presented a
                believes that management commitment to excellence cannot be measured by the
balanced assessment of plant performance during the appraisal period. The
                amount of money spent on a plant. We will continue to work closely with the
issue concerning resource allocation that was raised in the SALP report is one
                NRC staff in communicating the establishment of priorities and schedults for
to which we vill remain sensitive, but Consumers Power Company strongly
                action to improve plant safety and performance.
believes that management commitment to excellence cannot be measured by the
                Frederick W Buckman (Signed)
amount of money spent on a plant. We will continue to work closely with the
                Frede' tick W Buckman
NRC staff in communicating the establishment of priorities and schedults for
                Senior Vice President
action to improve plant safety and performance.
                Energy Supply
Frederick W Buckman (Signed)
                CC At-inistrator, Region III, NRC                               ,
Frede' tick W Buckman
                                                                                                ,
Senior Vice President
                      NRC Resident Inspector - Big Rock Point
Energy Supply
CC At-inistrator, Region III, NRC
,
,
NRC Resident Inspector - Big Rock Point
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Latest revision as of 07:23, 11 December 2024

App to SALP 7 Board Rept 50-155/87-01 for Apr 1986 - Aug 1987
ML20150F858
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/30/1988
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20150F844 List:
References
50-155-87-01, 50-155-87-1, NUDOCS 8804060028
Download: ML20150F858 (4)


See also: IR 05000155/1987001

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Enclosure 1

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APPENDIX

SALP 7

SALP BOARD REPORT

NUCLEAR REGULATORY COMMISSION

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REGION III

SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE'

50-155/87001

Inspection Report No.

Consumers Power Company

Name of 1.icensee

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Big Rock Point Plant

Name of Facility

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April 1, 1986 through August 31, 1987

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Assessment Period

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Enclosure 1

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A.

Summary of Meeting with Consumers Power Company on December 21, 1987

The findings and conclusions of the SALP board documented in Inspection

Report No. 50-155/87001 were discussed with the licensee on December 21,

1987, in Charlevoix, Michigan.

The 11censee's regulatory performance

was presented and found acceptable in each fJnctional area.

The following licensee and NRC personnel attended the meeting.

Consumers Power Company

F. Buckman, Vice President Nuclear Operations

G. Slade, Executive Director for Nuclear Assurance

R. Abel, Production and Plant Performance Superintendent

R. Alexander, Technical Engineer

J. Beer, Chemistry / Health Physics Superintendent

M. Sralinski, Senior Engineer

W. Blosh, Maintenance Engineer

G. Boss, A0

T. Hagan, Human Resources Director

C. Macinski, Plant Public Affairs Director

0. Moeggenberg, Engineering Supervisor

G. Petitjean, Planning / Administrative Services Superintendent

E. Reciborski, Scheduling Administrator

R. Schrader, Electrical I&C Engineering Supervisor

W. Trubilowicz, Operations Superintendent

M. Vankist, Property Protection Supervisor

G. Withrow, Engineering Maintenance Superintendent

R. Suchmar, Nuclear Plant Training Administrator

A. 'lrickenberger, Quality Control Supervisor

P. Donnelly, Nuclear Assurance Administrator

L. Monshor, Quality Assurance Superintendent

Ny: lear Regulatory Commission

W. Guldemond, Chief, Reactor Projects Branch 2

I. d. Jackiw, Chief, Reactor Projects Branch 28

S. Guthrie, Senior Resident Inspector

C. Papriello, Deputy Regional Administrator

B.

Comments Rece*ved from Licensee

By let'.er dated January 20, 1988, the licensee provided written comments

on the SALP report in accordance with the forwarding letter.

In regards to the comments relative to Section IV.B., "Radiological

Controls," the staff reviewed the issue of failed fuel and cancelled

inspection on fuel bundles scheduled for return to the reactor core.

Resolution of this concern involved several conference cells to address

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Enclosure 1

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the testing necessary to determine that no leaking fuel bundles were

returned to service.

Your eventual ultrasonic testing of fuel bundles

being returned to the core satisfied our concerns in this area. Based

on cur review of the information on gaseous releases, the report will

be corrected to reflect the following:

As a result of continuing fuel cladding problems, radioactive

gaseous releases until March 1987, when the fuel problem was

corrected, continued to be about a factor of 6 higher .

...

In regards to the comments relative to Section IV.C., "Maintenance,"

we accept your comments as they relate to EEQ and Appendix R.

Concerning

the effectiveness of mainte,ance programs at Big Rock Point, the staff

remains concerned that the current level of preventive, predictive, and

corrective maintenance at the facility may be only marginally adequate to

counter the effects of equipment aging and normal plant wear. The staff

encourages you to continue to emphasize your preventive and predictive

maintenance effort toward the goal of enhanced plant safety through such

activities as pump overhauls.

In regards to the comments relative to Section IV.D., "Surveillance,"

the staff scknowledges your clarification of the status of the battery

service test. The inaccuracy in Paragraph 3 has been deleted from the

SALP report. The following statement has been deleted:

One surveillance on the station battery was not performed while

the requirement for its performance was under review by NRR.

In regards to the comments relative to Section IV.K., "Training and

Qualificatior. Effectiveness," the staff appreciates the additional data

you provided to describe the improvements made in upgrading the skills of

the mechanical / electrical maintenance staff.

Based on our review of that

information the report will be amended to reflect the following:

Skills training was generally conducted on schedule with only minimal

impact from plant operations.

Significant increase in training man-days were in evidence when

compared to the training effort during the previous assessment period.

The staff continues to regard skill training and worker protection training

to be of a general nature and not sufficiently nuclear plant specific to

be of immediate benefit in upgrading the effectiveness of the newest

members of the mechanical / electrical maintenance staff. A review of the

CPC0 Training Records System Employee Training Report updated through

January 4, 1988, for the five mcst recent additions to the maintenance

staff indicate that the training provided these individuals during the

assessment period heavily emphasized worker safety.

Examples include the

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confined spaces and fire brigade training, protective tagging procedures,

asbestos control, and respirator use.

During the last month of the

assessment period, the individual's course work began to emphasize general

skills through training courses emphasizing introduction to valves,

introduction to blue prints, hand tools, power tools, electrical math, and

basic DC electricity.

Big Rock Point System training for these and other

individuals commenced August 17, 1987, two weeks prior to the close of

the assessment period.

In regards to the comments relative to Section IV.E., "Fire Protection,"

Section IV.G., Security,Section IV.K., Licensing Activities, we

acknowledge your comments and these facts will be factored into the

SALP 8 assessment period.

C.

Regional Administrator's Conclusions Based on Consideration of

Licensee Comments

Based on my review of the comments provided by the licensee, I have

concluded that the overall ratings in the affected areas have not

changed. Actions identified in the letter of response to SALP 7 dated

January 20, 1988 will be factored into future Region III inspections.

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Fr.a. rick w sockm.n

Srmor Vue Pressdent

POWERING

Ewty Supply

MICNIGAN'S PROGRE55

Generst Omces 1945 West Parnell Road. Jackson. MI 49201 e (517) 7881217

January 20, 1988

Nuclear Regulatory Commission

Document Control Desk

Washington, DC 20555

DOCKET 50-155 - LICENSE DPR-6 - BIG ROCK POINT PLANT -

SALP 7 REPORT C0KKENTS

Consumers Power Company appreciates NRC effort in assessing the nerformance of

Big Rock Point during the SALP 7 period. Of special note was Mr. Paperiello

and the SALP Board holding the presentation in Charlevoix, Michigan, which

permitted an increased attendance of Consumers Power Company personnel responsi-

ble for the operation of Big Rock Point. The direct communication was a

valuable part of the overall SALP process, and it will assist us in planning

future strategies and activities to achieve excellence in performance.

Following the presentation and review of the SALP 7 Report, Consumers Power

Company provides the following com=cr.ts.

A. Plant Operations

No Co= cents.

B. Radiological Controls

4

Unresponsiveness to NRC initiatives and concerns for fuel inspections was

never our intent. Only after carefully examining previous cycles' fuel

failures, current indicators, and personnel doses was the decision made not

to inspect fuel. We were confident that the fuel causing the failures was

being discharged and not used in Cycle 22.

In the spirit of ALARA, the

possibility was great for receiving more dose from fuel inspections than

the fuel failures we had been experiencing. Results of ultrasonic inspections

and next cycle performance substantiated our original evaluation that all

leaker bundles were discharged. Paragraph six (6) of this section incorrectly

4

refers to "... gaseous releases... continued to be about a factor of 6 higher

than normal." After the Cycle 22 Refueling Outage (March, 1987) gaseous

release rate was restored to normal and currently no leaking fuel is

evident.

It is true that a water chemistry control program based on BWR Ovners Group

Guidelines was not formalized, however, virtually every chemistry parameter

is within these guidelines and we feel confident that plant management

would take the appropriate measures if these parameters were above the

OC0188-0016-NLO2

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Nuclear Regulatory Commission

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Big Rock Point Plant

? ALP 7 Report Comments

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January 20, 1988

"action levels" of the guidelines even though they were not procedura11 zed.

The applicable guidelines will be incorporated into plant procedures over

the next procedure review cycle.

We note NRC concerns and have implemented improvements in the ALARA and

Radiation Work Permit programs and frisking equipment / practices since the

assessment, and will continue efforts to further reduce dose and contamin-

ation incidents.

C. Maintenance

Consumers Power Company utilized extensive resources in establishing a

"good f aith" ef fort in complying with the EEQ and Appendix R regulations.

However, both the EEQ and Appendix R efforts evolved over a very long time

period allowing program managers, both Consumers Power Company and NRC, to

change during program development and compliance rTriew. Decisions or

compliance interpretations agreed upon at one stage have been changed or

modified by individuals involved at later time periods. Consumers Povet

Company originally was involved in EEQ since 1975, with a LOCA task force,

followed with the RDS Modifications, and with the Systematic Evaluation

,

Program in the late seventies. Implementation Inspections did not commence

until 1986. We believe this contributed to the EEQ issues dealing with

MO-7068 and Polyethylene and Butyl rubber cables. Consumers Power Company

still believes that M0-7068 and the cables were capable of performing their

safety function, however, we agreed to replace the components rather than

continuing to debate the issues.

Big Rock Point continues to have an effective maintenance performance

history as evidenced by historical plant availability and number of forced

outages. Reactor trips from power have been minimal and the plant material

condition has been noted as very good by the NRC, INPO, and Insurance

Inspectors. During this SALP period Big Rock Point initiated and recently

completed a Maintenance Self-Assessment utilizing INPO guidelines.

Throughout the next SALP period we will be implementing changes in our

Maintenance Programs to improve the high priority areas identified in the

self-assessment. These will further strengthen our maintenance performance.

In addition, several major pump and motor overhauls are planned for the

upcoming refueling outage. The main feedvater pumps, turbine / generator,

and a service water pump have been completed in the recent past. Over the

next few years, two to three major pump overhauls per year are planned.

Big Rock Point will continue to monitor equipment performance and industry

maintenance practices toward enhancing existing Maintenance programs.

D. Surveillance

One inaccuracy existed in paragraph 3 of this section with regard to not

performing a surveillance test (Service Test) on the station battery. A

Technical Specification Change Request submittal dated December 22, 1986,

which is still under NRR review, modified the Service Test design time

interval to resolve errors as described in LER 86-004. Consumers Power

OC0188-0016-NLO2

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Big Rock Point Plant

SALP 7 Report Comments

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January 20, 1988

Company agreed to impleaent this proposal into testing scheduled for the

1987 Refueling Outage. The modified surveillance test was completed

satisfactorily during the outage.

E. Fire Protection

The NRC concern on lack of plant staff Appendix R understanding is related

to the duration of the review and implementation. As discussed above in

Section C, the effort extended over a long time period (approximately

1978-1986).

Because of the long time interval the need existed for several

technical-level meetings with staff and consultant personnel to revice

extensive submittals to understand the safe shutdown paths for Big Rock

Point in complying with the Appendix R requirements. Although further NRR

review was needed and one additional exemption was required, overall the

post-fire safe shutdown methods met the requirements for Appendix R.

Since

the inspection, documentation has been improved and fire plans strengthened

to enhance the capability of Big Rock Point to mitigate the effects of a

plant fire.

F. Emergency Preparedness

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No coc=ents.

G. Security

In response to NRC concerns regarding equipment aging, the 1987 CCTV

Upgrade Project was completed by year-end. Existing equipment was repaired,

cleaned or replaced. Two additional CCTV cameras and new lights were

installed and some existing lights were repositioned. A new metal detector

and X-ray machine were purchased for installation in the Lobby of the

Security Building.

In response to NRC concerns regarding an increase in personnel errors,

several methods of monitoring personnel performance have been initiated in

an effort to identify exceptional as well as weak performance. These

methods allow trending errors and pinpointing the causes. Each First

Lieutenant on shift is now committed to evaluating his shift personnel on a

weekly basis and documenting the results on a "Personnel Evaluation Form."

They are committed to one planned and one unplanned evaluation each week.

Drills are conducted twice per month on each shift using adopted scenarios

for contingencies.

Individuals with recurring performance problems are

retrained when needed and counseled or disciplined when applicable.

A new method of reviewing Logs has been established to track documentation

errors. This will ensure that proper logging is being accomplished.

A full review of all site security manuals and routine job information

sheets is being implemented to improve performance in the Security area.

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OC0188-0016-NLO2

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Big Rock Point Plant

SALP 7 Report Comments

January 20, 1988

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H. Outages

No comments.

I, Quality Programs and Administrative Controls Affecting Quality

No comments.

J. Training and Qualification Effectiveness

Training and Qualification Effectiveness was evaluated as a category 2 - a

rating judged equivalent in performance to the previous assessment period

which at that time had received a category 1 rating. While we do not take

issue with the lowering of a previously assessed category, a review of the

training results completed during this SALP period leads us to conclude

training warrants a category 1 assessment.

In response to the statement "While employees received some general worker

training and on-the-job instruction, management made little progress in

upgrading the mechanical / electrical staff's skill levels, a condition noted

,

in the previous assessment period" on page 10 under maintenance summary; we

believe that maintenance training has been aggressively pursued. We have

doubled the training time per repairworker from SALP 6 to SALP 7.

During

the SALP 7 period, we provided 443 student days of Mechanical / Electrical

skills training and 108 student days of Safety training. This is a signif-

icant investment of time dedicated for upgrading the skills of a maintenance

staff of 14 repairmen. All of this instruction time was dedicated to

strengthening the skills of our maintenance staff. This represents an

investment of 13% of the repairmen's time for training.

We do not concur with the statement "Skill training that was scheduled

during the assessment period was frequently cancelled because of plant

activities..." on page 22 under the training summary. Our records indicate

that there were no cancellations. There vae some rescheduling of courses,

but all courses originally scheduled were eventually completed.

The

percentage of courses required to be rescheduled was relatively low at 7.6%

for the entire SALP 7 period, and was due to unforeseen plant outages.

Also, on page 22 of the training suc=ary, further clarification is in order

in response to the statement "Skill training and worker protection training

was too general, not nuclear plant specific, and did little to enhance the

effectiveness of the maintenance stafi".

Skills training is not always

required to be nuclear plant specific, however during the period, 121

student days of Big Rock Point specific training was provided to the

maintenance staff.

It should also be noted that all of the tasks required

of the Maintenance repairmen were addressed via classroom training,

on-the-job training, and shop practices during the SALP 7 period. During

the SALP 7 peried, a major effort was made to modify training materials to

assure that all tasks were addressed as identified on the Big Rock Point

Plant Specific Task List.

It is recognized that additional systems training

is necessary for improved worker understanding and performance. At the end

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Nuclear Regulatory Commission

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Big Rock Point Plant

SALP 7 Report Comments

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January 20, 1988

2

of the SALP period the second round of systems training was started for the

least senior repairworkers at the plant.

Finally, on page 22, the statement "The Procedural requirements for both

required and on-the-job training were not met and the Maintenance Depart-

ment Training Program has not been evaluated and accredited by INP0" is

somewhat misleading.

INP0 evaluation and accreditation was not planned to

occur during this SALP period. The INPO evaluation was conducted in

October 1987 and after the fourteen man team completed their evaluation

they. proposed zero recom=endations in maintenance training.

INFO considered

the program to be very good and stated our program demonstrated a strong

commitment by the plant. Essentially all of the procedural requirements

for classroom and OJT were complete and in place prior to the end of the

SALP 7 period. Formal INPO Board approval is tentatively scheduled to

occur in the first quarter 1988.

We also reiterate the fact that initial or replacement license candidate

,

and requalification license candidate classes both achieved a 100% pass

rate during the SALP period. This is the sixth license class to achieve a

100% pass rate.

It is a ree-r' we are very proud of and speaks for itself

s to the caliber of Big Roo 'oint training.

We believe the above results demonstrate that management commitment to

training is evident to assure that our training provides the skills and

knowledge necessary to continue to operate Big Rock Point as a safe and

reliable plant. We also believe : hat the training results completed during

the SALP 7 period supports a Category 1 assessment.

K. Licensing Activities

Consumers Power Company Management and staff will continue to support and

utilize the Integrated Living Schedule (ILS) in accordance with License

requirements to evaluate and prioritize workload. We also plan on working

with Region III personnel in the near term, on exploring ways to use the

ILS process in prioritizing inspection based plant betterments.

Consumers Power Company understands that high quality and timely licensing

documents are essential in maintaining a sound licensing basis for Big Rock

Point and continue to support this objective. Corporate and plant licensing

,

personnel will continue to advocate frequent meetings with NRR and Region

personnel to understand and prioritize issues from both a NRC and Consumers

Power Company perspective. Our goal will be to recognize unique or complex

technical issues and ensure that related submittals are timely with suf-

ficient detail to minimize interaction.

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Big Rock Point Plant

SALP 7 Report Comments

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Consumers Power Company believes the overs 11 SALP evaluation presented a

balanced assessment of plant performance during the appraisal period. The

issue concerning resource allocation that was raised in the SALP report is one

to which we vill remain sensitive, but Consumers Power Company strongly

believes that management commitment to excellence cannot be measured by the

amount of money spent on a plant. We will continue to work closely with the

NRC staff in communicating the establishment of priorities and schedults for

action to improve plant safety and performance.

Frederick W Buckman (Signed)

Frede' tick W Buckman

Senior Vice President

Energy Supply

CC At-inistrator, Region III, NRC

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NRC Resident Inspector - Big Rock Point

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