ML17055C340
| ML17055C340 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 09/02/1986 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mangan C NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17055C341 | List: |
| References | |
| NUDOCS 8609080174 | |
| Download: ML17055C340 (6) | |
See also: IR 05000220/1986007
Text
Docket No. 50-220
jEp
OS 1986
Niagara
Mohawk Power Corporation
ATTN:
Mr. C.
V. Mangan
Senior Vice President
300 Erie Boulevard West
Syracuse,
13202
Gentlemen:
Subject:
Inspection
Report
Number 50-220/86-07
This refers to the modification outage
inspection
conducted
by Mr. C. Anderson
of this office on June 2-13,
1986 of activities authorized
by
NRC License
Number DPR-63 at the Nine Mile Point Nuclear Station Unit Number 1, Scriba,
New York and at the corporate offices, Syracuse,
New York and to the
discussions
of our findings held by Mr. Anderson with members of your staff on
June
6 and June
13,
1986.
The primary purpose of this inspection
was to review Niagara
Mohawk control of
modification activities during the
1986 refueling outage.
Areas
examined during
this inspection
are described
in the
NRC Region I Inspection
Report which is
enclosed with this letter.
The major functional areas
reviewed included:
Design
Control, Installation,
Post Modification Testing
and System Restoration.
Generally,
the inspection consisted of selective
examinations of procedures
and represen-
tative records',
interviews with personnel,
and observations
by the inspectors.
The team observed that
a number of changes
related to the control of modifications
were implemented during the
1986 refueling outage.
These
included the development
of new procedures
and
an increase
in the size of groups responsible
for overseeing
the modifications.
The team concluded that these initiatives provided
a good
mechanism to control modification activities.
However, this inspection identified
several deficiencies.
Four violations were identified and are discussed
in
Appendix A.
In addition, the team inspection findings have
been characterized
as program strengths
or weaknesses,
as appropriate,
and are documented
in
Appendices
B and
C, respectively,
to this letter.
You are required to respond to Appendix A within thirty days of the receipt of
this letter, stating actions
taken or planned to correct the violations.
We
also request that you describe
any proposed
changes
to improve the areas
iden-
tified as weaknesses
in Appendix
C.
We are particularly concerned
about the apparent
inadequacies
in your contractor
quality control activities as evidenced
by the violations found during our
review of the Emergency
Condenser modifications.
In view of this,
and recent
problems with the fai lure of a contractor to properly perform post welding
hydrostatic testing of a primary containment penetration
(Inspection 86-10), it
appears
that the violations identified during this team inspection
may not be
an isolated problem.
OFFICIAL RECORD
COPY
860'7080174
860902
ADOCK OS000220
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IR NMP1 86
07
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Niagara
Mohawk Power Corporation
2.l
Therefore,
as
we discussed
in a July 2,
1986 telephone call with Mr. W. Hanson
of your staff,
we request that you include in your response
the steps
you plan
to take to evaluate
the
scope of contractor
gC deficiencies;
your plans fo'r any
re-inspection of suspect
systems;
and your evaluation of the safety implica-
tions resulting
from inadequate
inspections
by your contractors.
Based
on discussions
with members of your staff at the exit meeting
on June
13,
1986, it is our understanding
that the upgrading of the engineering
assurance
procedures
for Nine Mile Point Nuclear Station will be completed
by October
1986
and will be used for modification design related activities planned for the
next refueling outage.
We also understand
that you plan to complete your
evaluation of the total loads
on the
AC and
DC emergency
busses
by June
1987
and that in the future you will maintain
an
up to date compilation of all
safety related electrical
loads.
In addition,
we understand
that you will
review these
loads to ensure
the assumptions
made in the safety analyses
are
not violated.
If our understanding
of your activities and schedules
related to
the upgrading of the engineering
assurance
procedures
or your evaluation of the
loads
on the
AC and
DC emergency
bus loads is incorrect,
then
we request that you
notify us as
soon
as practical.
The responses
directed
by this letter and the accompanying
Notice are not subject
to the clearance
procedures
of the Office of Management
and Budget
as requi red
by the Paperwork Reduction Act of 1980,
PL 96-511.
Sincerely,
1 ggg~e4 BV
Stewart
D, Ebneter,
Director
Division of Reactor'afety
Enclosure:
NRC Region I Inspection
Report
Number 50-220/86-07
cc w/encl:
T.
E.
Lempges,
Vice President,
Nuclear Generation
J.
A. Perry, Vice President,
guality Assurance
T. Perkins,
General
Superintendent,
Nuclear Generation
W. Hansen,
Manager of guality Assurance
T.
Roman, Station Superintendent
J. Aldrich, Supervisor,
Operations
W. Drews, Technical
Superintendent
Troy B. Conner, Jr.
Esquire
John
W. Keib, Esquire
Director,
Power Division
Public Document
Room (PDR)
Local Public Document
Room (LPDR)
Nuclear Safety Information Center
(NSIC)
NRC Resident
Inspector
State of New York
OFFICIAL RECORD
COPY
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