ML18039A231
| ML18039A231 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 01/02/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18039A230 | List: |
| References | |
| 50-260-97-11, 50-296-97-11, NUDOCS 9801210267 | |
| Download: ML18039A231 (4) | |
See also: IR 07100026/2012006
Text
Valley Authority
Browns Ferry Nuclear Plant
Docket Nos.
50-260
and 50-296
License
Nos.
During an
NRC inspection
conducted
on October
26 through
December
6,
1997,
two
violations of NRC requirements
were identified.
In accordance
with the
"General
Statement of Policy and Procedure
for
NRC Enforcement Actions,"
NUREG-1600, the violations are listed below:
A.
Technical Specification 6.8. 1. 1 requi res that written procedures
shall
be established,
implemented
and maintained covering the applicable
procedures
recommended
in Appendix A of Regulatory Guide 1.33, Revision
2, February
1978.
Paragraph
4 of Appendix A of Regulatory Guide 1.33
recommends
procedures
for the operation of the Control
Room Heating
and
Ventilation Systems.
Operating Instruction 0-OI-31. Control
Bay and Off-Gas Treatment
Building Air Conditioning System,
Revision 49, provides procedural
guidance for operation of the Control
Bay and Off-Gas Treatment Building
air conditioning systems.
Contrary to the above, written procedures
were not adequately
maintained
in that Operating Instruction 0-OI-31 did not adequately
address
operation of the control
room emergency ventilation
(CREV) system
priority select switch (0-XSW-31-7214).
The procedure
was not properly
revised
when the
CREV system
was modified in 1993.
This condition
existed from that time unti 1 December
5,
1997.
This is
a Severity Level
IV Violation (Supplement I)
10 CFR 50, Appendix B, Criterion V, Instructions,
Procedures,
and
Drawings,
requi res that activities affecting quality be performed in
accordance
with documented instructions,
procedures
or drawings
appropriate to the circumstances.
Procedure
NNDP-5,
"HOV Program," Revision 1,
and its predecessor,
Site
Standard
Practice
SSP-6.51.
"Program Plan for Generic Letter 89-10,"
Revision 3, specified trending requirements for Generic Letter 89-10
motor-operated
valves.
MHDP-5 required
issuance of a motor-operated
valve trending report at the completion of every testing cycle (18
months or end of each refueling outage).
SSP-.6.51
had required
a
similar report at the same periodicity.
980i2i0267 980i02
ADQCK 05000259
6
'nclosure
1
0
0
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Contrary to the above,
on November
19,
1997. the trend report required
by Procedure
HHDP-5 and Site Standard
Practice
SSP-6.51
had not been
prepared.
This is
a Severity Level
IV Violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201,
Valley Authority is
hereby required 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 II, and
a copy to the
NRC Resident
Inspector
at Browns Ferry, 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,
the 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 required
response.
If an adequate
reply is not received within the time specified in this Notice,
an order
or
a
Demand for Information may be issued
as to why the license should not be
modified, suspended,
or revoked,
or why such other action as
may be proper
should not be taken.
Where good cause is shown, consideration will be given
to extending the response
time.
Because
your response will be placed in the
NRC Public Document
Room (PDR), to
the extent possible, it should not include any personal
privacy, proprietary,
or safeguards
information so that it can be placed in the
PDR without
redaction.
If personal
privacy or proprietary information is necessary
to
provide an acceptable
response,
then please
provide
a bracketed
copy of your
response
that identifies the information that should
be protected
and
a
redacted
copy of your
response that deletes
such information.
If you request
withholding of such material,
you must specifically identify the portions of
your response that you seek to have withheld and provide in detail the bases
for your claim of withholding (e.g. explain why the disclosure of information
will create
an. unwarranted
invasion of personal
privacy or provide the
information required
by 10 -CFR 2.790(b) to support
a request for withholding
confidential
commercial or financial information). If safeguards
information
is necessary
to provide an acceptable
response,
please
provide the level of
protection described in 10 CFR 73.21.
Dated at Atlanta, Georgia
this 2nd day of January
1998
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