ML17291A863
| ML17291A863 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/16/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17291A861 | List: |
| References | |
| 50-397-95-03, 50-397-95-3, NUDOCS 9506210052 | |
| Download: ML17291A863 (4) | |
See also: IR 05000213/2003014
Text
ENCLOSURE
1
Washington Public Power Supply System
Washington Nuclear Project-2
Docket:
50-397
License:
During an
NRC inspection conducted
on February
13 through March 14.
1995.
three violations of NRC requi rements
were identified.
In accordance
with the
"General
Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2. Appendix C. the violations are listed below:
A.
10 CFR Part 50, Appendix B. Criterion V. states,
in part, "Activities
affecting quality shall
be prescribed
by documented instructions,
procedures,
or drawings of a type appropriate to the circumstances
and
shall
be accomplished
in accordance
with these instructions,
procedures.
or drawings."
1.
Procedure
EI 2.8,
"Generating Facility Design
Change Process."
Revision
11, Section 4. 1.8.a,
states
that "[drawing change
notices]
DCNs shall
be prepared
in accordance
with Attachment 5. 10
and shall
be listed on the document control system input sheet."
Contrary to the above.
as of March 3,
1995,
a drawing change
notice was not prepared,
or included on
a document control system
input sheet,
for the Final Safety Analysis Report
Drawing 02E12-04. 10. 1: Sheets
1 and 2,
and the drawing was not
updated.
2.
Procedure
PDS-5,
"Design Safety Analysis and
10 CFR 50.59 Review
Guidance,"
Revision
2, Attachment 7. 1, requi res
a safety
evaluation for modifications which affected the fire hazards
analysis.
Contrary to the above,
on February 20,
1991.
and January
23.
1992,
a safety evaluation addressing
potential fires and thei r effects,
was not performed for the addition of a filter/polisher unit in
the diesel
fuel oil system.
This modification affected the fire
hazards
analysis.
This is
a Severity Level
IV violation (Supplement I) (397/9503-01).
Criterion III of Appendix 8 to 10 CFR Part 50 states that measures
shall
be established
to assure that the design basis
are correctly translated
in procedures
and instructions.
9506210052 950bib
ADQCK 05000397
6
0
-2-
Contrary to the above,
as of March 3,
1995, established
measures
did not
assure that:
1.
The design basis of the standby service water system
was correctly
translated
into procedures
and instructions in that the acceptance
criteria of Procedures
7.4.7. 1. 1. 1 and 7.4.7. 1. 1.2 did not account
for variations in spray
pond level
or
pump degradation.
2.
The design basis of the diesel
fuel oil system
was correctly
translated into procedures
and instructions in that the acceptance
criteria of the surveillance test procedures
did not account for
variations in suction conditions
or
pump degradation.
The design basis of the spent fuel pool cooling system
was
correctly translated
into procedures
and instructions in that the
acceptance criteria of the surveillance test procedures
did not
account for variations in suction pressure
or pump degradation.
This is
a Severity Level
IV violation (Supplement I) (397/9503-02).
Criterion
V of Appendix
B to 10 CFR Part 50 states,
in part, that
"[alctivities affecting quality shall
be prescribed
by documented
instructions
.
.
. of a type appropriate to the circumstances
.
Contrary to the above,
as of Parch 3.
1995,
Procedure
10.2.8,
Testing
and Repair of Safety and Relief Valves. Revision 15,
was not appropriate
to the circumstances
in that:
1.
Section 4.0 did not contain any precaution related to the
determination of adjustment
ring position prior to disassembly;
2.
Section 6.2 did not requi re an authorized
nuclear inspector
review
for testing
and resetting of relief valves;
3.
Section
6. 1.3.j did not provide any instructions
on which
direction to turn the rings. nor did it identify a reference point
for counting turns
and notches;
Section
6. 1.8.d stated that the adjusting rings should
be
installed to the
same position as
when removed or to the
manufacturer's
specifications;
however, in the
same section, it
was stated that the ring positions
were for information only; and,
5.
Section 6.2.5.b stated that adjustment
rings for liquid service
valves
had little or no influence over the valve reseat
characteristics.
This is
a Severity Level
IV violation (Supplement I) (397/9503-06).
-3-
Pursuant to the provisions of 10 CFR 2.201,
Washington Public Power Supply
System is hereby requi red to submit
a written statement
or explanation to the
U.S. Nuclear Regulatory Commission.
ATTN:
Document Control Desk,
D.C.
20555 with a copy to the Regional Administrator,
Region IV, 611
Ryan
Plaza Drive, Suite 400. Arlington, Texas
76011,
and
a copy to the
NRC Resident
.
Inspector at the facility that is the subject of this Notice, within 30 days
of the date of the letter transmitting this Notice of 'Violation (Notice).
This reply should
be clearly marked
as
a "Reply to a Notice of Violation" and
should include for each violation:
(1) the reason for the violation, or, if
contested'he
basis for disputing the violation, (2) the corrective steps
that have been taken
and the results
achieved,
(3) the corrective steps that
will be taken to avoid further violations,
and (4) the date when full
compliance will be achieved.
Your response
may reference or include previous
docketed
correspondence, if the correspondence
adequately
addresses
the
o
required
response.
If an adequate
reply is not received within the time
specified in this Notice.
an order or a Demand'or
Information may be issued
as to why the license should not be modified. suspended,
or revoked'r
why
such other action
as
may be proper should not be taken.
Where good cause is
shown,
consider ation will be given to extending the response
time.
Dated at Arlington, Texas
this 16th day of June
1995