ML20207K866
| ML20207K866 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/31/1986 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20207K870 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8701090548 | |
| Download: ML20207K866 (4) | |
See also: IR 05000289/1986017
Text
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DEC 311986
Docket / License No. 50-289/DPR-50
GPU Nuclear Corporation
ATTN:
Mr. H. D. Hukill
Director TMI-1
P. O. Box 480
Middletown, Pennsylvania 17057
Gentlemen:
Subject:
Inspection 50-289/86-17
During the period September 8, 1986, to October 3, 1986, members of the NRC
Region I staff conducted routine safety inspection activities at your facility.
The results of these inspections are documented in the enclosed report. At the
conclusion of the inspections, Mr. R. Conte of my staff summarized the inspection
findings for you and other members of your staff. A number of concerns were
raised in this report that warrant your specific attention.'
First, the recent Performance Appraisal Team (PAT) and our inspectors identified
concerns with your implementation of the required technical and safety review of
procedures and procedure changes. These concerns include failure to properly
implement the process in the past, and inadequacies in your September 1, 1986,
revision to the process.
From discussions with our inspectors, it appears that
you may not totally agree on the above points and that you desire a meeting with
Region I management.
I also believe a meeting is warranted, as discussed later
in this letter.
This inspection report also documents that procedure implementation problems
have continued to occur at your facility.
The engineered safeguard actuation
testing is an example where personnel error occurred resulting in the unneces-
sary entry into a TS action statement unbeknownst to your staff at the time.
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A contributing factor, apparently not recognized in your staff's review of the
event, was the failure of management to insist that the surveillance procedure
be used for coordination and control from the start of the test. We would like
to discuss this matter with you at the meeting.
You should also follow the
instructions of Appendix A to this letter for the cited violation on this
matter.
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OFFICIAL RECORD COPY
IR TMIl 8 g I - 0001.0.0
12/31/86
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Also related to the procedure adherence issue is the adequacy of your responses
to a Notice of Violation, issued July 11, 1986, dealing with several examples
of failure to follow procedures. We believe that one of your responses, dealing
with a failure to follow the alarm response procedure, reflects a potentially
nonconservative approach to correcting symptoms of problems reflected by various
-alarms in the plant.
You will be requested to respond further after we discuss
the matter at the upcoming meeting.
We will contact you shortly to schedule a management meeting. The major topics
for that conference should be (1) the adequacy of your past and current technical /
safety review process, including your views on how the new review system enhances
your safety review methodology and complies with current Technical Specifications;
(2) procedure adherence problems, including your current perspective of the pro-
blem with respect to the Corporate Task Force findings and your related corrective
actions; and (3) any potential interrelation between the procedure adherence /
adequacy problems and the past or current technical / safety review systems. At
the meeting you and your staff should be prepared to discuss the circumstances
surrounding these matters, your findings relative to the underlying reasons for
these occurrences, your views on the significance, and your immediate and long-
term corrective actions.
Other apparent violations were identified. You should follow the instructions
of Appendix A in preparing the required response.
With respect to the independent verification of equipment control measures, your
letter of April 29, 1986, was incomplete in that you did not address in detail
how you meet the elements of TMI Task Action Plan (TAP) I.C.6.
Paragraph 10.5
of the enclosed inspection report details our concerns. Please provide, within
60 days, a written description which fully describes your independent verifica-
tion program relative to TAP Item I.C.6.
Finally, this inspection identified a problem with your post-accident sampling
procedures. Currently-approved procedures do not provide analytical capabi-
lities down to the low end of the range specified in correspondence related
to the TMI TAP Items. We understand that you plan to correct this.
Please prc-
vide us within 30 days with information regarding your analytical procedures
to be used and a schedule for their implementation.
Your cooperation with us in these matters is appreciated.
Sincerely,
Binal Signeq
William F. Kane, Director
Division of Reactor Projects
Enclosures:
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1. Appendix A, Notice of Violation
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2. NRC Region I Inspection Report Number 50-289/86-17
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0FFICIAL RECORD COPY
IR TMI1 86-17 - 0002.0.0
12/31/86
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GPU Nuclear Corporation
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cc w/encls:
R. J. Toole, Operations and Maintenance Director, TMI-1
C. W. Smyth, TMI-1 Licensing Manager
R. J. McGoey, Manager, PWR Licensing
E. L. Blake, Jr.
TMI-1 OTSG Hearing Service List
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
Commonwealth of Pennsylvania
bec w/ enc 1:
Region I Docket Room (concurrence copy)
J. Goldberg, OELD: HQ
Management Assistant, DRMA (w/o enc 1)
A. Blough, DRP Section Chief
W. Travers, NRR
K. Abraham, RI
R. Conte, RI
W. Baunack, RI
J. Callan, IE
M. Dev, RI
R. Freudenberger, RI
D. Johnson, RI
M. Miller, RI
G. Napuda, RI
J. Rogers, RI
A. Varela,.RI
H. Zibulsky, RI
DRS File
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R. Conte, RI
W. Baunack, RI
J. Callan, IE
M. Dev, RI
R. Freudenberger, RI
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M. Miller, RI
G. Napuda, RI
J. Rogers, RI
A. Varela, RI
H. Zibulsky, RI
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