ML17290A226
| ML17290A226 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/12/1993 |
| From: | Miller L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Sorenson G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 9304200118 | |
| Download: ML17290A226 (5) | |
See also: IR 05000397/1991027
Text
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UNITED STATES
NUCLEAR REGULATORYCOMMISSION
REGION V
1450 MARIALANE
WALNUTCREEK, CAUFORNIA94596-5368
April 12,
1993
Docket No.
50-397
Washington Public Power Supply System
P. 0.
Box 968
3000 George
Way
Richland,
99352
Attention:
Mr.
G.
C. Sorenson,
Manager
Regulatory
Programs
SUBJECT:
OUTSTANDING CONCERNS
Dear Mr. Sorenson:
We conducted
an inspection of your Emergency Operating
Procedures
(EOPs)
during July,
1991
and the results
were forwarded under Inspection
Report
Number 50-397/91-27.
You provided
a response
to this inspection via letter to
the Document Control
Desk dated
November 21,
1991.
After analysis of this
'esponse,
some Washington Public
Power Supply System
(the Supply System)
technical
positions for EOP deviations
were forwarded to the Office of Nuclear
Reactor Regulation for further review.
We received
the results of that
,
review,
and then reviewed your phase II EOPs.
As
a result of this review of
your phase
II. EOPs,
we still have
two outstanding
concerns.
These
are listed
below:
The Supply System deviated
from the Owners
Group guidance
in the Drywell
Spray Initiation curve.
This curve is shown
as figure "E" of PPM 5.2. 1,
"Primary Containment Control," in the phase II EOPs.
Please
indicate
whether this deviation
was submitted to the Boiling Water Reactors
Owners
Group
(BWROG) for review.
Changes
to the Drywell Spray Initiation limit
curve should
be addressed
to the
The Supply System should ensure
that changes
to this curve are consistent
with its purpose
developed
by
the
The
NRC staff does not intend to review changes
to the
generic curve
on
a plant specific basis.
Modification to this curve
should
be included in Appendix "C" of the
Emergency
Procedure
Guidelines
(EPG's),
however.
(This was previously designated
Design Deviation 17.)
The Supply System
does not monitor temperature
near the instrument lines
in the reactor building.
No instrumentation exists at
WNP-2 to
specifically monitor temperature
near individual instrument lines in the
reactor building.
However, temperature
in the general
area of the
instrument lines is measured.
The Supply System stated
in
a November ll,
1991 letter that events that could cause
a high temperature
in the
93O42M
CV 050OO397
ii8 930412
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April 12,
1993
reactor
building have
been reviewed,
and that two abnormal
procedures
were written to allow the Supply System to implement the intent of EPG
Caution
1.
We find this deviation acceptable
provided that (1) the
measured
temperature
in the general
area of the instrument lines is below
RPV saturation
temperature,
and (2) the level instrument
reads
above
a
minimum indicated level.
The Supply System should address
how their
Phase II EOPs or abnormal
procedures
provide for these conditions.
(This
was previously designated
Implementation Deviation 2.)
We request that you address
the outstanding
concerns listed above;
Your
response
should
be in a letter.
Thank you for your cooperation.
If you have
any questions,
please
contact
P.
Horrill of my staff at (510) 975-0293.
ewis
F. Hiller, Jr., Chief
Reactor Safety Branch
CC:
Hr. J.
W. Baker,
WNP-2 Plant Manager
Hr. A.
G. Hosier,
WNP-2 Licensing Manager
Hr. J.
C. Gearheart,
Director, guality Assurance
Mr.
G.
E.
Doupe,
Esq.
Hr. J.
V. Parrish,, Assistant
Managing Director for Operations
Hr. A. Lee Oxsen,
Acting Managing Director
State of WA
Hr. H. H. Philips,
Esq.,
Winston
and Strawn
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April 12,
1993
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J. Clifford, NRR
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