ML17059B643
| ML17059B643 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/17/1997 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17059B644 | List: |
| References | |
| 50-220-97-05, 50-220-97-5, 50-410-97-05, 50-410-97-5, EA-97-228, NUDOCS 9707290163 | |
| Download: ML17059B643 (8) | |
See also: IR 05000220/1997005
Text
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9707290163
DOC.DATE: 97/07/17
NOTARIZED:
NO
> FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara
Powe
50-410 Nine Mile Point Nuclear Station,
Unit 2, Niagara
Moha
JTH. NAME
AUTHOR AFFILIATION
GINS,J.T.
Region
1 (Post
820201)
CIP.NAME
RECIPIENT AFFILIATION
SYLVIA,BER.
Niagara
Mohawk Power Corp.
SUBJECT:
Forwards
insp repts
50-220/97-05
6 50-410/97-05
on 970310-
0418.No violations noted.
DOCKET
05000220
05000410
DISTRIBUTION CODE: IEOIF
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SIZE:
+2.
IZITLE: General
(50 Dkt)-Insp Rept/Notice of Violation Response
NOTES:
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NOTE TO ALL "RIDS" RECIPIENTS:
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ENCL
20
July 17,
1997
Mr. B.'Ralph Sylvia
Executive Vice President Generation Business
Group and Chief Nuclear Officer
Niagara Mohawk Power Corporation
Nuclear Learning Center
450 Lake Road
Oswego, NY 13126
SUBJECT:
NRC INSPECTION REPORT NOS. 50-220/97-05 AND 50-410/97-05
Dear Mr. Sylvia:
This letter refers to the NRC inspection conducted
by Mr. Leonard Cheung and
Mr. Richard Skokowski from March 10-14; 1997, and from April 14-18, 1997, at the Nine
Mile Point Nuclear Station, Units
1 and 2. The purpose of this inspection was to determine
whether activities authorized by the licensee were conducted
safely, and in accordance
with the NRC requirements.
At the April 18, 1997, exit meeting, the findings were
discussed with Messrs.
R. Abbott and M. McCormick and other members of your staff.
Additional findings were also discussed
with Mr. D. Baker of your staff in a telephone call
on June 4, 1997.
The inspection was directed toward areas important to public health and safety.
The areas
examined during this inspection included:
1) your corrective actions in response
to your
identification of multiple motor-operated
valves (MOVs) at both Units
1 and 2 being
vulnerable to mechanical damages
caused
by fire induced hot shorts during a postulated
control room fire; 2) your corrective actions following your identification, on two separate
occasions, that isolation switches were not provided to the control circuitry for the Unit 2
Division I and II emergency service water outlet valves; 3) your corrective actions in
resolving the issue associated
with the service life of Unit 2 Agastat GP relays; and 4) your
corrective actions taken to resolve several previously identified inspection items.
nal analyses that were
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8
Based on the information developed during the inspections,
as well as information
described
in License Event Report LER No. 96-10 for Unit 1, issued on December 2, 1996,
and LER 96-15 for Unit 2, issued on January
16, 1997, and supplemented
on March 27,
1997, a number of apparent violations were identified.
These apparent violations include
the failure to appropriately consider the possibility of electrical "hot shorts" in your fire
protection analysis, to determine whether such hot shorts could affect safe shutdown of
the reactor in the event of a fire in the control room.
Reanalysis indicated the fire-induced
hot shorts could render certain MOVs from performing the intended safe shutdown
function.
The NRC is concerned that your engineering
and design organization did not fully
evaluate the MOVs'ulnerability to hot shorts in their origi
conducted
in 1992.
Mr. B. Ralph Sylvia
The above apparent violations are being reviewed by NRC management.
We will inform
you of the review result at a later date.
In addition to the above, based
on this inspection, the inspectors determined that your
program for calculating the service life of Unit 2 normally-energized Agastat relays was not
based
on sound engineering judgement.
Although not a violation of NRC requirements,
we
understand that you were in a process of revising your program to develop
a better
calculation method.
In accordance
with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter
and its enclosures,
and your response
will be placed in the NRC Public Document Room.
Your cooperation with us is appreciated.
Sincerely,
James T. Wiggins, Director
Division of Reactor Safety
Docket Nos.
50-220, 50-410
Enclosure:
Inspection Report
cc w/enclosures:
R. Abbott, Vice President 5 General Manager - Nuclear
C. Terry, Vice President- Safety Assessment
and Support
J. Conway, Vice President - Nuclear Engineering
K. Dahlberg, Vice President - Nuclear Operations
D. Wolniak, Manager, Licensing
J. Warden, New York Consumer Protection Branch
G. Wilson, Senior Attorney
M. Wetterhahn, Winston and Strawn
J. Rettberg, New York State Electric and Gas Corporation
Director, Electric Division, Department of Public Service, State of New York
C. Donaldson,
Esquire, Assistant Attorney General, New York Department of Law
J. Vinquist, MATS, Inc.
P. Eddy, Power Division, Department of Public Service, State of New York
F. Valentino, President,
New York State Energy Research
and Development Authority
J. Spath, Program Director, New York State Energy Research
and Development Authority
0
Mr. B. Ralph Sylvia
Distribution w/encl:
W. Axelson, DRA (1)
Region
I Docket Room (with concurrences)
Nuclear Safety Information Center (NSIC)
PUBLIC
NRC Resident Inspector
J. Wiggins, DRS
L. Doerflein, DRP
T. Moslak, DRP
R. Junod,
DRS Files (2)
Distribution w/encl:
(VIAE-MAIL)
W. Dean OEDO
B. Norris - Nine Mile Point
A. Dromerick, NRR
D. Hood, NRR
M. Campion,
Rl
Inspection Program Branch (IPAS)
R. Correia, NRR
F. Talbot, NRR
DOCDESK
DOCUMENT NAME: A:iNM970505.INS
To receive a copy of this document, Indicate in the box:
C
~ Copy without attachment/enclosure
E
Copy with attachment/enclosure
ff" ~ No copy
, OFFICE
NAME
DATE
RI/DRS
LCheung
07/16/97
Rl/DRP
LDoerflein
07/
/97
RI/DRS
WRuland
07
/97
OFFICIAL RECORD COPY
+~ Rl/ RA
DH
dy
07/
/97
0