ML17284A475
| ML17284A475 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/25/1988 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| Shared Package | |
| ML17284A476 | List: |
| References | |
| EA-86-070, EA-86-70, TAC-63528, NUDOCS 8808180131 | |
| Download: ML17284A475 (6) | |
See also: IR 05000397/1988016
Text
ACCELZRATKULA
LRW DXKRIPN
QRXDP ~~+
ACCESSION NBR:8808180131
DOC;DATE: 88/07/25
NOTARIZED:
NO
~
~
~
FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public
Powe
AUTH.NAME
AUTHOR AFFILIATION
KIRSCH,D.F.
Region
5, Ofc of the Director
RECIP.NAME
RECIPIENT AFFILIATION
SORENSEN,G.C.
Washington Public Power Supply System
SUBJECT:
Forwards Safety Insp Rept 50-397/88-16
on 880606-10.
Violations noted.
DXSTRXBUTXON CODE:
XEOXD
COPXES
RECEXVED:LTR I ENCL 2
SXSE:
TITLE: General
(50 Dkt)-Insp Rept/Notice of Violation Response
NOTES:
DOCKET
05000397
RECIPIENT
ID CODE/NAME
PD5
INTERNAL: ACRS
DEDRO
NRR/DLPQ/PEB
11
NRR/DOEA DIR 11
NRR/DREP/RPB
10
NRR/PMAS/ILRB12
OE LIEBERMANxJ
ES/DSR
DEPY
EXTERNAL: LPDR
COPIES
LTTR ENCL
1
1
2
2
1
1
1
1
~ 1
1
2
2
1
1
1
1
1
1
1
1
1
1
1
1
RECIPIENT
ID CODE/NAME
SAMWORTHiR
NRR MORISSEAUxD
NRR/DLPQ/QAB 10
NRR/DREP/EPB
10
NRR/DRIS DIR 9A
NUDOCS-ABSTRACT
OGC/HDS2
RES/DSIR
DEPY
RGN5
FILE
01
NRC PDR
COPIES
LTTR ENCL
2
2
1
1
1
1
1
1l,l
1
1
1
1
1
1
1
1
1
1
1
1
TOTAL NUMBER OF COPIES
REQUIRED:
LTTR
26
ENCL
26
Docket No.
50-397
EA 86-070
Washington Public Power Supply System
P.
0.
Box 968
3000 George Washington
Way
Richland,
99352
Attention:
Mr.
G.
C. Sorensen,
Manager
Regulatory
Programs
Gentlemen:
Subject:
NRC Inspection at WNP-2
This refers to the special
announced
safety inspection
by Messrs.
C.
Ramsey,
A. Johnson,
and
K.
Rod, of this office; Messrs.
J. Bradfute, I. Ahmed, T.
Chandrasekaran
and
Ms.
S.
Juergens
of NRR; Mr.
M. Murphy of Region IV; Mr.
D.
Ward of Region II; and Mr.
K. Sullivan of Brookhaven National Laboratory,
on
June 6-10,
1988, of activities authorized
by NRC License
No.
NPF-21 and to the
discussion of findings by the inspection
team with members of your staff at
the conclusion of the inspection.
Areas
examined during this inspection
are described in the enclosed inspection
report.
Within these
areas,
the inspection consisted of selective
examinations of procedures
and representative
records,
interviews with
personnel,
and observations
by the inspectors.
The inspection
was performed
as
a follow-up to previous inspections that
determined that
some of your activities were apparently 'not conducted in full
compliance with the
NRC approved Fire Protection
Program.
While the
inspection
team recognized
the significant resources
and effort you expended
over the past two years performing
a comprehensive
reevaluation of your
compliance with your fire protection program
and implementing modifications
required to bring your facility into full compliance,
the team identified
additional deficiencies
in your program implementation,
as well as
inadequacies
in your fire hazard analysis.
These conditions appear to be
violations of Facility Operating
License
The specific apparent
violations are:
Failure to provide adequate fire barrier protection for safe
shutdown trains located in the cable spreading
room and reactor building;
failure to perform an adequate
high-low pressure
interface analysis
and
failure to establish plant operating procedures
to support safe
shutdown in
the event of a loss of DC power supplies.
Enforcement action concerning these
conditions will be the subject of a separate
correspondence.
In light of the fact that the violation concerning failure to provide adequate
fire barrier protection for safe
shutdown trains is similar to,
and involve
some of the
same safe
shutdown circuits (2DG2-106 and 2DG2-107 in the cable
8808i 80 2 3 1 880725
ADOCK 0500039'7
6
spreading
room) that
LER 84-31 and previous violations 86-05-02
and 87-02-01
identified,
we are particularly 'disturbed
by your failure to achieve
adequate
corrective action in this regard.
In addition, it is our view that the
position you took regarding
NRC requirements
on the need to protect high-low
pressure
interface motor operated
valves
from spuriously opening
due to fire
damage
was inappropriate
and complete action should
have
been initiated to
assure
compliance with these fire protection program requirements
following
the Appendix
R inspection in 1986 (Inspection
Report 397/86-05).
We wish to reemphasize
to you the importance the
NRC places
on providing the
protection required to ensure reliable operation of safe
shutdown equipment.
In accordance
with 10 CFR 2.790(a),
a copy of this letter
and the enclosure
will be placed in the
NRC Public Document
Room.
Should you have
any questions
concerning this inspection
we will be glad to
discuss
them with you.
Sincerely,
Ufigin'ol sigrjgd Qy
+P,, F, Kiradj~
D. F;"'Kirsch, Director
Division of Reactor Safety
and Projects
Enclosure:
Inspection Report
No. 50-397/88-16
cc w/enclosure:
C.
M. Powers,
WNP-2 Plant Manager
G.
D. Bouchey, Director, Assurance
8 Licensing
Mr.
G.
E.
Doupe,
Esq.,
Mr. A.
Lee Oxsen, Assistant
Managing Director
for Operations,
MD/1023
State of Washington
Mr.
N.
S.
Reynolds,
Esq.
P. L. Powell,'WNP-2 Licensing Manager
-3-
bcc w/enclosure:
Docket File
Project Inspector
Resident Inspector
G.
Cook,
RV
B. Faulkenberry,
RV
J. Martin,
RV
T. Foley,
bcc w/o enclosure:
M. Smith
J. Zollicoffer
REGION V
CRamsey/Joan
AJ
nson
7/4//88
7/ Pf /88
ea
SRi hards
7/ '88
7/g5'/88
DFKir ch
7/
/88
REQUEST
COPY ]
R
COPY ]
COPY ]
COPY ]
RE
UEST
COPY ]
YES /
NO
ES /
NO
ES /
NO
YES /
NO
ES /
NO
S
ND TO
]
YES /
NO