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                                                                                                    l
APPENDIX B
                                                        APPENDIX B
U. 5. NUCLEAR REGULATORY COMISSION
                                          U. 5. NUCLEAR REGULATORY COMISSION
REGION IV
                                                                                    - '
- '
                                                        REGION IV
NRC Inspection Report:
            NRC Inspection Report:           50-267/85-33               License: DPR-34
50-267/85-33
            Docket:       50-267
License: DPR-34
            Licensee:       Public Service Company of Colorado (PSC)
Docket:
                            P. O. Box 840
50-267
                            Denver, Colorado 80201
Licensee:
;           Facility Name:         Fort St. Vrain Nuclear Generating Station
Public Service Company of Colorado (PSC)
  *
P. O. Box 840
            Inspection At:         Fort St. Vrain Nuclear Generating Station, Platteville,
Denver, Colorado 80201
                                  Colorado
;
            Inspection Conducted: December 9-13, 1985
Facility Name:
!         Inspector:                                                                   /2/z7/97
Fort St. Vrain Nuclear Generating Station
                              M. E. Skow, Project Engineer, Project Section A,           Date
Inspection At:
                                Reactor Projects Branch
Fort St. Vrain Nuclear Generating Station, Platteville,
          Approved:                    -          -    #
*
                              J. T Jauffon, Ch .f,ProjectSgfdhh,
Colorado
                                                                      /                  / 2M
Inspection Conducted: December 9-13, 1985
                                                                                        Dat[ /
!
                                R ctorl Projec s Branch
Inspector:
                                          V
/2/z7/97
          Inspection Summary
M. E. Skow, Project Engineer, Project Section A,
          Inspection Conducted December 9-13, 1985 (Report 50-267/83-33)
Date
          Areas Inspected:           Routine, unannounced inspection of nonlicensed operator
Reactor Projects Branch
I         training and follow-up to NRC Inspection Report 50-267/85-26. The inspection
J. T Jauffon, Ch .
l         involved 23 inspector-hours onsite by one NRC inspector.
#
/
/ 2M
Approved:
-
-
f,ProjectSgfdhh,
Dat[
/
R ctorl Projec s Branch
V
Inspection Summary
Inspection Conducted December 9-13, 1985 (Report 50-267/83-33)
Areas Inspected:
Routine, unannounced inspection of nonlicensed operator
I
training and follow-up to NRC Inspection Report 50-267/85-26.
The inspection
l
involved 23 inspector-hours onsite by one NRC inspector.
l
l
          Results: Within the areas inspected, two violations were identified
Results: Within the areas inspected, two violations were identified
      .(paragraph 2 ).
.(paragraph 2 ).
l
l
hh
D
,
'
'
          ,
G
                            hh
                            G
                                      D
i
i
                                                                                                  r
r
        -     n- . .-- -       -- -           ,   --
-
n-
. .-- -
-- -
,
--
, - , - - . - -
-,n--
-
~~- --


                - - - .       .   .-       .           .     .       -     _       .   _ - . _ _ - .. _-.
- - - .
  .
.
            .
.-
.
.
.
-
_
.
_ - . _ _ - ..
_-.
.
.
l...
l...
-2-
,
,
                                                                -2-
!
                                                                                      ' ~
                                                            DETAILS
                1.        Persons Contacted
!
!
' ~
DETAILS
1.
Persons Contacted
!
*J. W. Gahm, knager, Nuclear Power Operations
'
'
                        *J. W. Gahm, knager, Nuclear Power Operations
*C. L. Fuller, Station Manager
                        *C. L. Fuller, Station Manager
L. W. Singleton, Manager. Quality Assurance
,
,
                          L. W. Singleton, Manager. Quality Assurance
I
I
                          R. L. Craun, Site Engineering Manager
R. L. Craun, Site Engineering Manager
                        *F. J. Borst, Support Services Manager
*F. J. Borst, Support Services Manager
,
*M. J. Ferris, QA Operations Manager
                        *M. J. Ferris, QA Operations Manager
,
.                       *F. J. Novachek, Technical / Administrative Services Manager
.
*F. J. Novachek, Technical / Administrative Services Manager
j
j
~
*W. L. Craine, Superintendent Maintenance
                        *W. L. Craine, Superintendent Maintenance
~
                        *R. Burchfield, Superintendent Nuclear Bettement Engineering
*R. Burchfield, Superintendent Nuclear Bettement Engineering
    .                  *T. D. McIntirw Nuclear Site Engineering Supervisor
*T. D. McIntirw Nuclear Site Engineering Supervisor
                        *S. Hofstetter, Nuclear Licensing and Fuel
.
                          S. W111 ford, Superintendent of Training
*S. Hofstetter, Nuclear Licensing and Fuel
                          R. Rivera, Operator Training Supervisor
S. W111 ford, Superintendent of Training
R. Rivera, Operator Training Supervisor
G. Weiderspoon, Auxiliary Tender
;
;
                          G. Weiderspoon, Auxiliary Tender
.
                        * Denotes those present at the exit interview
                2.        Followup to NRC Inspection Report 50-267/85-26
                          The NRC inspector perfonned a followup inspection to verify the findings of
.
.
* Denotes those present at the exit interview
2.
Followup to NRC Inspection Report 50-267/85-26
The NRC inspector perfonned a followup inspection to verify the findings of
.
NRC Inspection Report 50-267/85-26, hereafter referred to as the PAT
i
i
                          NRC Inspection Report 50-267/85-26, hereafter referred to as the PAT
report. The NRC inspector also detemined what, if any, corrective
                          report. The NRC inspector also detemined what, if any, corrective
j
j                         actions had been taken by the licensee. The paragraph numbers of the PAT
actions had been taken by the licensee. The paragraph numbers of the PAT
:                         report are used below to discuss the specific concerns of that report.
:
;                         Specific item numbers are also identified, but some item numbers are made
report are used below to discuss the specific concerns of that report.
j.
;
                          up of several parts in various paragraphs,
Specific item numbers are also identified, but some item numbers are made
j
up of several parts in various paragraphs,
.
'
'
                          PAT Report Paragraph 2.a.(2), Open Item 8526-01
PAT Report Paragraph 2.a.(2), Open Item 8526-01
;                        Procedure P-1, " Plant Operations," did not provide adequate control of
Procedure P-1, " Plant Operations," did not provide adequate control of
,                        temporary plant modifications. Specifically, Section 4.9, " Control of
;
i                        Temporary Configuration," contained no provisions for ensuring the
temporary plant modifications. Specifically, Section 4.9, " Control of
,
i
i
                          temporary nature of modifications made under that procedure. At the time
Temporary Configuration," contained no provisions for ensuring the
:                        of the inspection, 37 Temporary Configuration Requests (TCRs) were open
j                        from 2 to 9 years. The licensee had initiated pennanent Design Change
i                        Notices (DCNs) for several of these TCRs however, at least 11 of these
i                        DCNs had been in preparation for over 2 years. This lack of control of
l                        temporary changes resulted in permanent changes being made to the station
'
                          without the necessary reviews being conducted.
i                        Inspection Followup
i
i
;                         NRC Inspection Report 50-267/85-31 discussed the licensee's programmatic
temporary nature of modifications made under that procedure. At the time
j                         corrective action. During this followup, the NRC inspector reviewed the
:
i                         licensee's TCRs that were maintained in the control room. The more recent
of the inspection, 37 Temporary Configuration Requests (TCRs) were open
j
from 2 to 9 years. The licensee had initiated pennanent Design Change
i
Notices (DCNs) for several of these TCRs however, at least 11 of these
i
DCNs had been in preparation for over 2 years. This lack of control of
l
temporary changes resulted in permanent changes being made to the station
without the necessary reviews being conducted.
'
i
Inspection Followup
i
;
NRC Inspection Report 50-267/85-31 discussed the licensee's programmatic
j
corrective action. During this followup, the NRC inspector reviewed the
i
licensee's TCRs that were maintained in the control room. The more recent
.
.
      - - - _ -                                           - __
- - -
-
-
- __
-
-
- -
-


                                . _ . _ _ _             __ __. _ ____                                                     - _-                               _ _ _               _ _ ._               - __
. _ . _ _ _
                              '
__ __. _ ____
        ...
- _-
                                                                                                                      - 3-
_ _
,
_
_ _ ._
- __
'
...
3-
-
,
TCRs all appeared to have had safety evaluations perfomed.- This was in
,
,
                                                    TCRs all appeared to have had safety evaluations perfomed.- This was in
;
;
keeping with the licensee's corrective action. The older TCRs appeared to
have had safety evaluations perfonned only if the TCRs had been marked as
;
;
                                                    keeping with the licensee's corrective action. The older TCRs appeared to
!
!
                                                    have had safety evaluations perfonned only if the TCRs had been marked as
" Safety Related." The NRC inspector found two older TCRs that installed
                                                    " Safety Related." The NRC inspector found two older TCRs that installed
l
l                                                   temporary gages. These gages were used by the operators to verify
temporary gages. These gages were used by the operators to verify
j
j
                                                    compliance with Technical Specification Limiting Conditon of Operation
compliance with Technical Specification Limiting Conditon of Operation
                                                    (TS LCO) 4.2.7, but the TCRs, 820427, dated April 13, 1982, and 820503,
(TS LCO) 4.2.7, but the TCRs, 820427, dated April 13, 1982, and 820503,
,
,
'
'
                                                    dated May 1,1982, were neither marked as " Safety Related" nor as Technical
dated May 1,1982, were neither marked as " Safety Related" nor as Technical
                                                    Specification involved. Thus, they were equipnient required to support
Specification involved. Thus, they were equipnient required to support
Technical Specifications. Changes to these equipments required a safety
4
4
i
i
                                                  Technical Specifications. Changes to these equipments required a safety
evaluation as described in 10 CFR 50.59. No safety evaluation had been
                                                  evaluation as described in 10 CFR 50.59. No safety evaluation had been
i
performed at the time of the PAT inspection.
In addition, the licensee
i
could not show that the gages had been calibrated. The licensee stated
that there was not a program in place to routinely calibrate temporary
;
.
i
i
i
gages. The failure to perfonn a safety evaluation of TCRs used to verify
                                                    performed at the time of the PAT inspection. In addition, the licensee
-
                                                  could not show that the gages had been calibrated. The licensee stated
,
;        .
:
          -                                        that there was not a program in place to routinely calibrate temporary
compliance with LCOs is an apparent violation (8533-01). This portion of
i          ,
j
                                                  gages. The failure to perfonn a safety evaluation of TCRs used to verify
Unresolved Item 8526-02 is closed because it has been incorporated into
:
the apparent violation.
                                                  compliance with LCOs is an apparent violation (8533-01). This portion of
;
j                                               Unresolved Item 8526-02 is closed because it has been incorporated into
l
                                                the apparent violation.
The licensee committed to calibrate the gages installed by TCRs 820427 and
  ;
l
l                                               The licensee committed to calibrate the gages installed by TCRs 820427 and
820503 prior to plant startup.
  l                                           820503 prior to plant startup.                                                   .
.
I
I
                                                PAT Report Paragraph 4.a.(4), Part 1. Unresolved Item 8526-05
PAT Report Paragraph 4.a.(4), Part 1. Unresolved Item 8526-05
t
t
i
Gearcase oil used for Motor Operated Valve (MOV) applications differed
t
t
i                                            Gearcase oil used for Motor Operated Valve (MOV) applications differed
from that reconsnended by the vendor manual and may not have been suitable
I
I
                                              from that reconsnended by the vendor manual and may not have been suitable
for the environment of all plant MOVs. Proced ae MP 39-3 and the vendor
                                              for the environment of all plant MOVs. Proced ae MP 39-3 and the vendor
manual specify the use of SAE 80 EP oil in the gearcase of motor operated
                                              manual specify the use of SAE 80 EP oil in the gearcase of motor operated
valves. Discussions with maintenance personnel revealed that Mobil 629
  ;
;
                                              valves. Discussions with maintenance personnel revealed that Mobil 629
cil was being used for all MOV applications. The licensee had not
                                            cil was being used for all MOV applications. The licensee had not
perfomed an engineering evaluation to determine that the Mobil 629 oil
                                              perfomed an engineering evaluation to determine that the Mobil 629 oil
was suitable for all MOV applications or compatible with residual oil that
                                            was suitable for all MOV applications or compatible with residual oil that
may have been in the gearcase.
                                            may have been in the gearcase.
Inspection Followup
                                              Inspection Followup                                                                                                         '
'
                                                                                                                                                                                                                ,
,
j                                           Mobil 629 is an SAE 40 oil. The vendor maintenance manual specifies SAE 80
j
Mobil 629 is an SAE 40 oil. The vendor maintenance manual specifies SAE 80
;
;
EP oil.
In response to the PAT report, the licensee initiated Action
'
'
                                            EP oil. In response to the PAT report, the licensee initiated Action
Request GSAR-979 to resolve the issue of oil suitability. The use of the
                                            Request GSAR-979 to resolve the issue of oil suitability. The use of the
Mobil 629 oil is considered a design change, and the failure to perform an
                                            Mobil 629 oil is considered a design change, and the failure to perform an
appropriate evaluation of the oil suitability is an apparent violation of
                                            appropriate evaluation of the oil suitability is an apparent violation of                                                                                       I
I
i
i
                                            10CFR50.55(8533-02). This portion of Unresolved Item 8526-05 is closed
10CFR50.55(8533-02). This portion of Unresolved Item 8526-05 is closed
l                                           because it is incorporated into the apparent violation.
l
'
because it is incorporated into the apparent violation.
                                                                                                                                                                                                              e
'
!
!
                                            The licensee committed to complete evaluation of the oil suitability prior to
e
j                                           plant startup.
The licensee committed to complete evaluation of the oil suitability prior to
j
plant startup.
1
1
i
i
                                                                                                                                                                                                              o
o
l
l
l
l
                                                                                                                                                                                                                h
h
    .. - - - - - - _ - - - - -               -_,,,n               ,-e_ .,m n.-,- - - , , --,,n_,_.w.,,.,---,,,.-_,m,,             ,n,---n,,-.,,m,.,.,-.,--r,.       -.y_-   .. we   ,v . - em, m mm--
.. - - - - - -
- - - - -
-_,,,n
,-e_
.,m
n.-,- - - , ,
--,,n_,_.w.,,.,---,,,.-_,m,,
,n,---n,,-.,,m,.,.,-.,--r,.
-.y_-
.. we
,v
.
- em, m mm--


                                              _ _ .           __                       .         _ _   _ . _ _ _
_ _ .
            : .
__
                  *
.
    ;..         ,
_
                                                                  -4-
_
!                   3.   Nonlicensed Staff Training                                         -
_ . _ _ _
:
.
;..
*
,
-4-
!
3.
Nonlicensed Staff Training
-
i
i
                          This inspection was to evaluate the effectiveness of the training programs
This inspection was to evaluate the effectiveness of the training programs
for the nonlicensed staff. As a starting point, the NRC inspector selected
'
'
                          for the nonlicensed staff. As a starting point, the NRC inspector selected
an event that the licensee reported to the NRC duty officer on December 4,
                          an event that the licensee reported to the NRC duty officer on December 4,
1985. During this event, an Auxiliary Tender inadvertently tripped a
                          1985. During this event, an Auxiliary Tender inadvertently tripped a
breaker for a bearing water pump which resulted in a loop shutdown. The
                          breaker for a bearing water pump which resulted in a loop shutdown. The
;
;                         NRC inspector found that the Auxiliary Tender had received documented
NRC inspector found that the Auxiliary Tender had received documented
!                         on-the-job training in breaker operation. He had not received formal
!
                          classroom training in breaker operation. However, he participated in the
on-the-job training in breaker operation.
                          development of the training elements for formal classroom training which,
He had not received formal
                          in effect, demonstrated his knowledge of breaker operation. In the event
classroom training in breaker operation.
                          selected, the tender stated that he had identified the proper breaker he
However, he participated in the
                          was to rack out. He went to the end of the panel to get the crank returned
development of the training elements for formal classroom training which,
    a                    to and tripped the wrong breaker. The licensee is evaluating the training
in effect, demonstrated his knowledge of breaker operation.
                          task elements to determine if the classroom training can be modified to
In the event
                          preclude this kind of lapse of concentration by an operator.
selected, the tender stated that he had identified the proper breaker he
                          The development of the task elements above was part of the licensee's
was to rack out. He went to the end of the panel to get the crank returned
                          program to upgrade training to support INPO accreditation. The licensee
to and tripped the wrong breaker. The licensee is evaluating the training
a
task elements to determine if the classroom training can be modified to
preclude this kind of lapse of concentration by an operator.
The development of the task elements above was part of the licensee's
program to upgrade training to support INPO accreditation. The licensee
stated that they expect to be ready for Auxiliary Tender training INPO
,
,
  '
accreditation by December 31, 1985. Documentation reviewed by the NRC
                          stated that they expect to be ready for Auxiliary Tender training INPO
'
                          accreditation by December 31, 1985. Documentation reviewed by the NRC
inspector appears to support that date.
                          inspector appears to support that date.
l
l                         In addition, classroom training was observed and an individual training
In addition, classroom training was observed and an individual training
                          record was reviewed.       No violations or deviations were ncted.
record was reviewed.
No violations or deviations were ncted.
I
I
                    4.   Exit Interview
4.
,
Exit Interview
                          An exit interview was held on December 13, 1985, with those personnel
An exit interview was held on December 13, 1985, with those personnel
i                         denoted in paragraph 1 of this report. The NRC senior resident inspector
,
                          also attended this meeting. At the meeting, the scope of the inspection
i
;                         and findings were summarized. The licensee also confirmed those
denoted in paragraph 1 of this report. The NRC senior resident inspector
j                         commitments identified in paragraph 2.
also attended this meeting. At the meeting, the scope of the inspection
;
and findings were summarized. The licensee also confirmed those
j
commitments identified in paragraph 2.
I
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Latest revision as of 17:32, 11 December 2024

Insp Rept 50-267/85-33 on 851209-13.Violation Noted: Failure to Perform Safety Evaluation for Installed Temporary Gauges & Failure to Review Design Change for Suitability
ML20140A576
Person / Time
Site: Fort Saint Vrain 
Issue date: 01/02/1986
From: Jaudon J, Skow M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20140A554 List:
References
50-267-85-33, NUDOCS 8601230228
Download: ML20140A576 (4)


See also: IR 05000267/1985033

Text

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1

APPENDIX B

U. 5. NUCLEAR REGULATORY COMISSION

REGION IV

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NRC Inspection Report:

50-267/85-33

License: DPR-34

Docket:

50-267

Licensee:

Public Service Company of Colorado (PSC)

P. O. Box 840

Denver, Colorado 80201

Facility Name:

Fort St. Vrain Nuclear Generating Station

Inspection At:

Fort St. Vrain Nuclear Generating Station, Platteville,

Colorado

Inspection Conducted: December 9-13, 1985

!

Inspector:

/2/z7/97

M. E. Skow, Project Engineer, Project Section A,

Date

Reactor Projects Branch

J. T Jauffon, Ch .

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Approved:

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Dat[

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R ctorl Projec s Branch

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Inspection Summary

Inspection Conducted December 9-13, 1985 (Report 50-267/83-33)

Areas Inspected:

Routine, unannounced inspection of nonlicensed operator

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training and follow-up to NRC Inspection Report 50-267/85-26.

The inspection

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involved 23 inspector-hours onsite by one NRC inspector.

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Results: Within the areas inspected, two violations were identified

.(paragraph 2 ).

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DETAILS

1.

Persons Contacted

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  • J. W. Gahm, knager, Nuclear Power Operations

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  • C. L. Fuller, Station Manager

L. W. Singleton, Manager. Quality Assurance

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R. L. Craun, Site Engineering Manager

  • F. J. Borst, Support Services Manager
  • M. J. Ferris, QA Operations Manager

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  • F. J. Novachek, Technical / Administrative Services Manager

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  • W. L. Craine, Superintendent Maintenance

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  • R. Burchfield, Superintendent Nuclear Bettement Engineering
  • T. D. McIntirw Nuclear Site Engineering Supervisor

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  • S. Hofstetter, Nuclear Licensing and Fuel

S. W111 ford, Superintendent of Training

R. Rivera, Operator Training Supervisor

G. Weiderspoon, Auxiliary Tender

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  • Denotes those present at the exit interview

2.

Followup to NRC Inspection Report 50-267/85-26

The NRC inspector perfonned a followup inspection to verify the findings of

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NRC Inspection Report 50-267/85-26, hereafter referred to as the PAT

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report. The NRC inspector also detemined what, if any, corrective

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actions had been taken by the licensee. The paragraph numbers of the PAT

report are used below to discuss the specific concerns of that report.

Specific item numbers are also identified, but some item numbers are made

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up of several parts in various paragraphs,

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PAT Report Paragraph 2.a.(2), Open Item 8526-01

Procedure P-1, " Plant Operations," did not provide adequate control of

temporary plant modifications. Specifically, Section 4.9, " Control of

,

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Temporary Configuration," contained no provisions for ensuring the

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temporary nature of modifications made under that procedure. At the time

of the inspection, 37 Temporary Configuration Requests (TCRs) were open

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from 2 to 9 years. The licensee had initiated pennanent Design Change

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Notices (DCNs) for several of these TCRs however, at least 11 of these

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DCNs had been in preparation for over 2 years. This lack of control of

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temporary changes resulted in permanent changes being made to the station

without the necessary reviews being conducted.

'

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Inspection Followup

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NRC Inspection Report 50-267/85-31 discussed the licensee's programmatic

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corrective action. During this followup, the NRC inspector reviewed the

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licensee's TCRs that were maintained in the control room. The more recent

.

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TCRs all appeared to have had safety evaluations perfomed.- This was in

,

keeping with the licensee's corrective action. The older TCRs appeared to

have had safety evaluations perfonned only if the TCRs had been marked as

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" Safety Related." The NRC inspector found two older TCRs that installed

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temporary gages. These gages were used by the operators to verify

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compliance with Technical Specification Limiting Conditon of Operation

(TS LCO) 4.2.7, but the TCRs, 820427, dated April 13, 1982, and 820503,

,

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dated May 1,1982, were neither marked as " Safety Related" nor as Technical

Specification involved. Thus, they were equipnient required to support

Technical Specifications. Changes to these equipments required a safety

4

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evaluation as described in 10 CFR 50.59. No safety evaluation had been

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performed at the time of the PAT inspection.

In addition, the licensee

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could not show that the gages had been calibrated. The licensee stated

that there was not a program in place to routinely calibrate temporary

.

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gages. The failure to perfonn a safety evaluation of TCRs used to verify

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compliance with LCOs is an apparent violation (8533-01). This portion of

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Unresolved Item 8526-02 is closed because it has been incorporated into

the apparent violation.

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The licensee committed to calibrate the gages installed by TCRs 820427 and

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820503 prior to plant startup.

.

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PAT Report Paragraph 4.a.(4), Part 1. Unresolved Item 8526-05

t

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Gearcase oil used for Motor Operated Valve (MOV) applications differed

t

from that reconsnended by the vendor manual and may not have been suitable

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for the environment of all plant MOVs. Proced ae MP 39-3 and the vendor

manual specify the use of SAE 80 EP oil in the gearcase of motor operated

valves. Discussions with maintenance personnel revealed that Mobil 629

cil was being used for all MOV applications. The licensee had not

perfomed an engineering evaluation to determine that the Mobil 629 oil

was suitable for all MOV applications or compatible with residual oil that

may have been in the gearcase.

Inspection Followup

'

,

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Mobil 629 is an SAE 40 oil. The vendor maintenance manual specifies SAE 80

EP oil.

In response to the PAT report, the licensee initiated Action

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Request GSAR-979 to resolve the issue of oil suitability. The use of the

Mobil 629 oil is considered a design change, and the failure to perform an

appropriate evaluation of the oil suitability is an apparent violation of

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10CFR50.55(8533-02). This portion of Unresolved Item 8526-05 is closed

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because it is incorporated into the apparent violation.

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!

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The licensee committed to complete evaluation of the oil suitability prior to

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plant startup.

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3.

Nonlicensed Staff Training

-

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This inspection was to evaluate the effectiveness of the training programs

for the nonlicensed staff. As a starting point, the NRC inspector selected

'

an event that the licensee reported to the NRC duty officer on December 4,

1985. During this event, an Auxiliary Tender inadvertently tripped a

breaker for a bearing water pump which resulted in a loop shutdown. The

NRC inspector found that the Auxiliary Tender had received documented

!

on-the-job training in breaker operation.

He had not received formal

classroom training in breaker operation.

However, he participated in the

development of the training elements for formal classroom training which,

in effect, demonstrated his knowledge of breaker operation.

In the event

selected, the tender stated that he had identified the proper breaker he

was to rack out. He went to the end of the panel to get the crank returned

to and tripped the wrong breaker. The licensee is evaluating the training

a

task elements to determine if the classroom training can be modified to

preclude this kind of lapse of concentration by an operator.

The development of the task elements above was part of the licensee's

program to upgrade training to support INPO accreditation. The licensee

stated that they expect to be ready for Auxiliary Tender training INPO

,

accreditation by December 31, 1985. Documentation reviewed by the NRC

'

inspector appears to support that date.

l

In addition, classroom training was observed and an individual training

record was reviewed.

No violations or deviations were ncted.

I

4.

Exit Interview

An exit interview was held on December 13, 1985, with those personnel

,

i

denoted in paragraph 1 of this report. The NRC senior resident inspector

also attended this meeting. At the meeting, the scope of the inspection

and findings were summarized. The licensee also confirmed those

j

commitments identified in paragraph 2.

I

i

)

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