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                                                                                                                              MAR 2 51987
y
          Docket No.                           50-219
MAR 2 51987
          License No. DPR-16
Docket No.
          GPU Nuclear Corporation
50-219
          ATTN: Mr. P. B. Fiedler
License No. DPR-16
                        -Vice President and Director
GPU Nuclear Corporation
          Oyster Creek Nuclear Generating Station
ATTN: Mr. P. B. Fiedler
          P. O. Box 388
-Vice President and Director
          Forked River, New Jersey 08731
Oyster Creek Nuclear Generating Station
          Gentlemen:
P. O. Box 388
          Subject:                     Inspection Report No. 50-219/86-38
Forked River, New Jersey 08731
          This refers to the routine safety inspection by Messrs. W. Bateman,
Gentlemen:
          J. Wechselberger, W. Baunack, R. Borchardt, L. Doerflein, R. Fuhrmeister,
Subject:
          R. Freudenberger and D. Florek from November 17, 1986 - January 16, 1987 at the
Inspection Report No. 50-219/86-38
          Oyster Creek Nuclear Generating Station. The inspections were augmented to
This
          provide 16 hour a day coverage during plant startup activities and consisted of
refers
          document reviews, interviews, and observations of activities as documented in
to the
          the enclosed inspection report. The findings were discussed with you and other
routine
          members of your staff at the conclusion of the inspection.
safety
          We acknowledge receipt of your November 7, 1986 response to the Violation cited
inspection by Messrs.
          in Inspection Report 86-21. The corrective action in your response did not
W.
          specify commitments made by the Radiological Controls Director to the resident
Bateman,
          inspector. The commitments concerned revisions to the ALARA review procedure
J. Wechselberger,
          to ensure the radiological engineer and the assigned job supervisor thoroughly
W.
          understand the radiological job aspects just prior to commencement of work
Baunack,
          activities, and to the radiological control survey procedure to ensure radio-
R.
          logical control technicians properly evaluate radiological survey data in addi-
Borchardt,
          tion to performing the survey to obtain the radiological information for a work
L.
          area. In addition, the direction you provided to the Group Radiological Con-
Doerflein,
          trol Shift Supervisor on proper supervisory inspection of the radiological and
R.
          safety conditions in the drywell was to be delineated in a memorandum and later
Fuhrmeister,
          proceduralized. If your understanding of these additional commitments differs
R. Freudenberger and D. Florek from November 17, 1986 - January 16, 1987 at the
          from the above description, please notify this office promptly.                                                                 In addition,
Oyster Creek Nuclear Generating Station.
          we acknowledge receipt of your December 3, 1986 response to the violation cited
The inspections were augmented to
          in Inspection Report 86-24 and your comments in addressing the improvements in
provide 16 hour a day coverage during plant startup activities and consisted of
          timeliness of processing Preliminary Safety Concerns. Your corrective actions
document reviews, interviews, and observations of activities as documented in
          will be verified in a future NRC inspection.
the enclosed inspection report. The findings were discussed with you and other
                                                                                                                                                                                        I
members of your staff at the conclusion of the inspection.
            B703310601 870325
We acknowledge receipt of your November 7, 1986 response to the Violation cited
            PDR           ADOCK 05000219
in Inspection Report 86-21.
            G                                         PDR
The corrective action in your response did not
                                                          OFFICIAL RECORD COPY                                           IR OYC 86-38 - 0001.0.0
specify commitments made by the Radiological Controls Director to the resident
                                                                                                                          03/19/87
inspector. The commitments concerned revisions to the ALARA review procedure
                                                                                                                                                                                    \ \
to ensure the radiological engineer and the assigned job supervisor thoroughly
understand the radiological job aspects just prior to commencement of work
activities, and to the radiological control survey procedure to ensure radio-
logical control technicians properly evaluate radiological survey data in addi-
tion to performing the survey to obtain the radiological information for a work
area.
In addition, the direction you provided to the Group Radiological Con-
trol Shift Supervisor on proper supervisory inspection of the radiological and
safety conditions in the drywell was to be delineated in a memorandum and later
proceduralized.
If your understanding of these additional commitments differs
from the above description, please notify this office promptly.
In addition,
we acknowledge receipt of your December 3, 1986 response to the violation cited
in Inspection Report 86-24 and your comments in addressing the improvements in
timeliness of processing Preliminary Safety Concerns. Your corrective actions
will be verified in a future NRC inspection.
I
B703310601 870325
PDR
ADOCK 05000219
G
PDR
OFFICIAL RECORD COPY
IR OYC 86-38 - 0001.0.0
03/19/87
\\
\\
!
!
    _   _
_
              . . _ _ _ _ ____ . _ , . _ . _ .               __,_ _ ___. _ . _ __, _ .. _ _,_ _. , _ _ _ _ _ _ . _ _ _ .                   , _ . _ _ _ _ , _ _ _ _ . _ _ _ _ . _ _
_
. . _ _ _ _ ____ . _ , . _ . _ .
__,_ _ ___. _ . _ __, _ .. _ _,_ _. , _ _ _ _ _ _ . _ _ _ .
, _ . _ _ _ _ , _ _ _ _ . _ _ _ _ . _ _


        _                         .                                     _           .
_
      i   i
.
            GPU Nuclear Corporation                                               2
_
                                                                                                            :5 E
.
            Your action to establish twenty-four hour management coverage during the con-
i
            clusion of the outage and later during plant startup, is considered a positive
i
            step toward improving performance during plant startup from an extended outage.
GPU Nuclear Corporation
            However, an apparent violation of NRC requirements was identified and is cited
2
:5 E
Your action to establish twenty-four hour management coverage during the con-
clusion of the outage and later during plant startup, is considered a positive
step toward improving performance during plant startup from an extended outage.
However, an apparent violation of NRC requirements was identified and is cited
in Appendix A and categorized under the General Statement of Policy and Proced-
-
-
            in Appendix A and categorized under the General Statement of Policy and Proced-
ure for NRC Enforcement Actions,10 CFR Part 2, Appendix C (Enforcement Policy
.
.
            ure for NRC Enforcement Actions,10 CFR Part 2, Appendix C (Enforcement Policy
1986).
            1986).                 In particular, a startup was conducted with nuclear instrumentation
In particular, a startup was conducted with nuclear instrumentation
            problems in which your operations management elected to manipulate equipment in
problems in which your operations management elected to manipulate equipment in
            an attempt to stay in literal compliance with the Technical Specifications to
an attempt to stay in literal compliance with the Technical Specifications to
            avoid a plant shutdown despite the instrument problems. These actions were
avoid a plant shutdown despite the instrument problems.
            inconsistent with your procedures and with good, conservative operating prac-
These actions were
inconsistent with your procedures and with good, conservative operating prac-
tices.
Your response to this violation should follow the instructions of
4
4
            tices.                  Your response to this violation should follow the instructions of
Appendix A, with particular emphasis on measures to prevent such occurrences in
,          Appendix A, with particular emphasis on measures to prevent such occurrences in
,
            the future.
the future.
'
'
            The response directed by this letter and the accompanying Notice are not sub-
The response directed by this letter and the accompanying Notice are not sub-
            ject to the clearance procedures of the Office of Management and Budget as
ject to the clearance procedures of the Office of Management and Budget as
            required by the Paperwork Reduction Act of 1980, PL 96-511.
required by the Paperwork Reduction Act of 1980, PL 96-511.
            Your cooperation with us in these matters is appreciated.
Your cooperation with us in these matters is appreciated.
                                                                                        Sincerely,
Sincerely,
                                                                                          SSk .                 e -_
SSk .
                                                                                        Frederick J. He6 don, Acting Chief
e -_
                                                                                        Reactor Projects Branch No.1
Frederick J. He6 don, Acting Chief
                                                                                        Division of Reactor Projects
Reactor Projects Branch No.1
            Enclosures:
Division of Reactor Projects
            1.           Appendix A, Notice of Violation
Enclosures:
            2.           NRC Region I Report No. 50-219/86-38
1.
i           cc w/encls:
Appendix A, Notice of Violation
2.
NRC Region I Report No. 50-219/86-38
i
cc w/encls:
BWR Licensing Manager
4
4
            BWR Licensing Manager
Licensing Manager, Oyster Creek
Public Document Room (PDR)
'
'
            Licensing Manager, Oyster Creek
Local Public Document Room (LPDR)
            Public Document Room (PDR)
Nuclear Safety Information Center (NSIC)
            Local Public Document Room (LPDR)
NRC Resident Inspector
            Nuclear Safety Information Center (NSIC)
State of New Jersey
            NRC Resident Inspector
bec w/encls:
            State of New Jersey
Region I Docket Room (with concurrences)
            bec w/encls:
,
            Region I Docket Room (with concurrences)                                                                               ,
Management Assistant, DRMA (w/o encis)
            Management Assistant, DRMA (w/o encis)
DRP Section Chief
            DRP Section Chief
DRS Director
            DRS Director
DRSS Director
            DRSS Director
0FFICIAL RECORD COPY
                                                                        0FFICIAL RECORD COPY       IR OYC 86-38 - 0002.0.0
IR OYC 86-38 - 0002.0.0
                                                                                                  03/23/87
03/23/87
1
1
  -_     -   . _ _ _ . _ _ _ , . -       .._ - _-_ . - _ - .. - - - - .- -_                          - . -     _- . . . _ _ -
-_
-
. _ _ _ . _ _ _ , . -
..
-
-
. -
- .. - - - - .- -
- .
-
_- . .
. _ _ -


I
I
  ,     i
,
            GPU Nuclear Corporation             3
i
                                                                NAR 2 51987
GPU Nuclear Corporation
        O
3
          s
NAR 2 51987
            RI:DRP                       RI:DRP
O
                                                                d.
d.
                                                              RI:0RP
s
    Mo 'f   Bateman/mjd                   Blough             Hebdon
RI:DRP
            3/M/87                       3/?f/87             3/14/87
RI:DRP
                                    0FFICIAL RECORD COPY IR OYC 86-38 - 0003.0.0
RI:0RP
                                                        03/23/87
M 'f
                                        ,
Bateman/mjd
Blough
Hebdon
o
3/M/87
3/?f/87
3/14/87
0FFICIAL RECORD COPY
IR OYC 86-38 - 0003.0.0
03/23/87
,
}}
}}

Latest revision as of 16:06, 7 December 2024

Forwards Safety Insp Rept 50-219/86-38 on 861117-870116 & Notice of Violation
ML20205H010
Person / Time
Site: Oyster Creek
Issue date: 03/25/1987
From: Hebdon F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20205H013 List:
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8703310601
Download: ML20205H010 (3)


See also: IR 05000219/1986038

Text

u

y

MAR 2 51987

Docket No.

50-219

License No. DPR-16

GPU Nuclear Corporation

ATTN: Mr. P. B. Fiedler

-Vice President and Director

Oyster Creek Nuclear Generating Station

P. O. Box 388

Forked River, New Jersey 08731

Gentlemen:

Subject:

Inspection Report No. 50-219/86-38

This

refers

to the

routine

safety

inspection by Messrs.

W.

Bateman,

J. Wechselberger,

W.

Baunack,

R.

Borchardt,

L.

Doerflein,

R.

Fuhrmeister,

R. Freudenberger and D. Florek from November 17, 1986 - January 16, 1987 at the

Oyster Creek Nuclear Generating Station.

The inspections were augmented to

provide 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> a day coverage during plant startup activities and consisted of

document reviews, interviews, and observations of activities as documented in

the enclosed inspection report. The findings were discussed with you and other

members of your staff at the conclusion of the inspection.

We acknowledge receipt of your November 7, 1986 response to the Violation cited

in Inspection Report 86-21.

The corrective action in your response did not

specify commitments made by the Radiological Controls Director to the resident

inspector. The commitments concerned revisions to the ALARA review procedure

to ensure the radiological engineer and the assigned job supervisor thoroughly

understand the radiological job aspects just prior to commencement of work

activities, and to the radiological control survey procedure to ensure radio-

logical control technicians properly evaluate radiological survey data in addi-

tion to performing the survey to obtain the radiological information for a work

area.

In addition, the direction you provided to the Group Radiological Con-

trol Shift Supervisor on proper supervisory inspection of the radiological and

safety conditions in the drywell was to be delineated in a memorandum and later

proceduralized.

If your understanding of these additional commitments differs

from the above description, please notify this office promptly.

In addition,

we acknowledge receipt of your December 3, 1986 response to the violation cited

in Inspection Report 86-24 and your comments in addressing the improvements in

timeliness of processing Preliminary Safety Concerns. Your corrective actions

will be verified in a future NRC inspection.

I

B703310601 870325

PDR

ADOCK 05000219

G

PDR

OFFICIAL RECORD COPY

IR OYC 86-38 - 0001.0.0

03/19/87

\\

\\

!

_

_

. . _ _ _ _ ____ . _ , . _ . _ .

__,_ _ ___. _ . _ __, _ .. _ _,_ _. , _ _ _ _ _ _ . _ _ _ .

, _ . _ _ _ _ , _ _ _ _ . _ _ _ _ . _ _

_

.

_

.

i

i

GPU Nuclear Corporation

2

5 E

Your action to establish twenty-four hour management coverage during the con-

clusion of the outage and later during plant startup, is considered a positive

step toward improving performance during plant startup from an extended outage.

However, an apparent violation of NRC requirements was identified and is cited

in Appendix A and categorized under the General Statement of Policy and Proced-

-

ure for NRC Enforcement Actions,10 CFR Part 2, Appendix C (Enforcement Policy

.

1986).

In particular, a startup was conducted with nuclear instrumentation

problems in which your operations management elected to manipulate equipment in

an attempt to stay in literal compliance with the Technical Specifications to

avoid a plant shutdown despite the instrument problems.

These actions were

inconsistent with your procedures and with good, conservative operating prac-

tices.

Your response to this violation should follow the instructions of

4

Appendix A, with particular emphasis on measures to prevent such occurrences in

,

the future.

'

The response directed by this letter and the accompanying Notice are not sub-

ject to the clearance procedures of the Office of Management and Budget as

required by the Paperwork Reduction Act of 1980, PL 96-511.

Your cooperation with us in these matters is appreciated.

Sincerely,

SSk .

e -_

Frederick J. He6 don, Acting Chief

Reactor Projects Branch No.1

Division of Reactor Projects

Enclosures:

1.

Appendix A, Notice of Violation

2.

NRC Region I Report No. 50-219/86-38

i

cc w/encls:

BWR Licensing Manager

4

Licensing Manager, Oyster Creek

Public Document Room (PDR)

'

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

State of New Jersey

bec w/encls:

Region I Docket Room (with concurrences)

,

Management Assistant, DRMA (w/o encis)

DRP Section Chief

DRS Director

DRSS Director

0FFICIAL RECORD COPY

IR OYC 86-38 - 0002.0.0

03/23/87

1

-_

-

. _ _ _ . _ _ _ , . -

..

-

-

. -

- .. - - - - .- -

- .

-

_- . .

. _ _ -

I

,

i

GPU Nuclear Corporation

3

NAR 2 51987

O

d.

s

RI:DRP

RI:DRP

RI:0RP

M 'f

Bateman/mjd

Blough

Hebdon

o

3/M/87

3/?f/87

3/14/87

0FFICIAL RECORD COPY

IR OYC 86-38 - 0003.0.0

03/23/87

,