ML20198N621
| ML20198N621 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 12/29/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20198N614 | List: |
| References | |
| 50-302-97-17, NUDOCS 9801210147 | |
| Download: ML20198N621 (2) | |
See also: IR 07100026/2011029
Text
Florida Power Corporation
Docket No. 50-302
Crystal River Unit 3
License No. DPR-72
During NRC ins)ections conducted on October 26 through November 29. 1997,
violations of iRC 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.
10 CFR 50.59 states that a licensee may make changes in procedures as
described in the safety analysis report or may conduct tests not
described in the safety analysis report. without prior NRC approval.
unless the proposed change or test involves a change in the technical
specifications incorporated in the license or an unreviewed safety
question.
The licensee must maintain records of changes to procedures
or of tests conducted, including a written safety evaluation which
provides the bases for the determination that the change, test. or
experiment does not involve an unreviewed safety question.
Contrary to the above, on November 5. 1997, the licensee failed to
perform an adequate safety evaluation. per 10 CFR 50.59 for the
functional test procedure for the "B" emergency diesel generator power
Ungrade and radiator replacement modifications. MAR 97-05-15-01. in tnat
tIleevaluationfailedtorecognizethatallowableoperatingparameters
had been ciianged from those in the reviewed and approved surveillance
procedure incorporated in the test procedure.
This resulted in the lack
of evaluation for the changes in the procedure.
This is a Severity Level IV Vioistion (Supplement 1).
B.
10 CFR 50. Appendix B. Criterion III. Design Control. requires in part,
that measures be established to assure that appitcable regulatory
requirements and the design basis. as defined in 10 LFR 50.2.
Definitions, and as specified in the license application, are correctly
translated into specifications, procedures, and instructions.
Tiicse
measures shall include provisions to assure that appropriate quality
standards are specified and included in design documents and that
deviations from such standards are controlled.
In addition, the design
control masures shall provide for verifying or checking the adequacy of
design, such as by the performance of design reviews.
Contrary to the above. in December 19e4. the licensee incorrectly
translated design specifications and removed thermal relief valves from
several heat exchangers when they incorrectly assumed that these valves
were redundant. The valves were needed to protect components in the
Decay Heat Closed Cycle Cooling (DC) and Nuclear Services Closed Cycle
Cooling (SW) systems from thermal overpressurization.
In addition, as
of November 19, 1997, under Modification Approval Record 96-10-04-02.
Enclosure 1
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9801210147 971229
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which installed the missing relief valves-and replaced other
inadequately sized relief valves, an erigineer overlooked the replacement
of existing valve DCV-109 when preparing tM work requests to install
,
the valves.
Because of this oversight. DCV-109 was not included in the
_ design change package and therefore, not replaced in the system.
Closure of the design change package and closure of the associated
restart issue failed to detect the oversight.
This is a Severity Level IV Violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201. Florida Power Corporation is
hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission. ATTN: Document Control Desk. Washington, DC
20555 with a copy to the Regional Administrator. Region II, and a copy to the
NRC Resident Inspector, at Crystal River, 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 como11ance will be achieved.
Your response may reference or include previous docketed correspondence if
the correspondence adequately addresses the recuired response. If an adequate
reply is not received within the time specifiec
in this Notice, an order or
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
3 roper
should not be taken. Where good cause is shown, consideration will
3e given
to extending the response time.
Because your res)onse will be placed in the NRC Public Document Room (PDR)
to
the extent possi)le, it should not include any personal privacy. 3roprietary,
or safeguards information so that it can be placed in the PDR witlout
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 s)ecifically identify the portions of
.your response that you seek to have withleld 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 29th day of December 1997
Enclosure 1
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