ML20207E176
| ML20207E176 | |
| Person / Time | |
|---|---|
| Site: | River Bend |
| Issue date: | 12/29/1986 |
| From: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Cahill GULF STATES UTILITIES CO. |
| Shared Package | |
| ML20207E180 | List: |
| References | |
| EA-86-183, NUDOCS 8701020081 | |
| Download: ML20207E176 (3) | |
See also: IR 05000458/1986036
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION IV
81s RYAN PLAZA DRIVE, SUITE 1000
ARUNGTON, TEXAS 70011
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DEC 2 91996
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Docket No. 50-458
License No. NPF-47
EA 86-183
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Gulf States Utilities
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ATTN: William J. Cahill, Jr.
Senior Vice President
River Bend Nuclear Group
P. O. Box 220
St. Francisci11e, Louisiana 70775
SUBJECT: NOTICEOFVIOLATION(NRCINSPECTIONREPORTNO. 50-458/86-36)
This refers to the NRC inspection conducted of activities authorized by License
No. NPF-47 during the period October 16-23, 1986 at the River Bend Station. This
inspection consisted of a review and evaluation of the circumstances and corrective
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actions associated with the modification of the control building ventilation
system. During the inspection, a violation of NRC requirements was identified.
The inspection findings were documented in Inspection Report No; 50-458/86-36
sent to you be letter dated October 30, 1986, and an enforcement conference
was conducted November 10, 1986, at the Region IV office to discuss the violation
and your corrective actions.
As described in the enclosed Notice of Violation, plant personnel discovered
on October 16, 1986 that temporary alterations to the control building venti-
lation system had been implemented on October 29, 1985 and June 27, 1986 based
on an inadequate safety evaluation. The safety evaluation failed to recognize
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that the temporary alterations prevented the automatic start of one of tha
redundant trains of the control building ventilation system under certain single
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failure scenarios. Without this automatic start capability, manual actuation
would have been required to prevent control room, switchgear room, and chiller
room temperatures from exceeding their design basis limits during a loss of
coolant accident with offsite power available. While it appears that the
inadequate evaluation had no impact on plant safety, the NRC is concerned that
your engineering review process for these modifications was deficient in
the identification of the system design bases used in the 50.59 safety evaluation.
In accordance with the " General Statement of Policy and Procedure for NRC
Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violation described
in the enclosed Notice has been classified at a Severity Level III. Normally,
a civil penalty is considered for a Severity Level III violation. However,
after consultation with the Director, Office of Inspection and Enforcement, I
have decided that a civil penalty will not be proposed in this case because of
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the unusually prompt and extensive corrective actions taken to correct the
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problem and prevent recurrence, and the licensee's prior good performance in
the general area of concern.
CERTIFIED MAIL - RETURN RECEIPT REQUESTED
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8701020081 861229
ADOCK 05000450
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_ Gulf States Utilities
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DEC29I!El
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You are required to respond to this letter and should follow the instructions
specified in the enclosed Notice when preparing your response. In your
response, you should document the specific actions taken and any additional
actions you plan to prevent recurrence. After reviewing your response to
-this Notice, including your proposed corrective actions, the NRC will determine
' whether further NRC enforcement action is necessary to ensure compliance with
-NRC regulatory requirements.
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In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,
Title 10, Code of Federal Regulations, a copy of this letter and its enclosure
will_ be placed in the NRC Public Document Room.
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The responses directed by this letter and the enclosed Notice are not subject
to the clearance procedures of the Office of Management and Budget as required
by the Paperwork Reduction Act of 1980, PL 96-511.
Sincerely,
__
f!obert D. Martin
Regional Administrator
Enclosure:
cc w/ enclosure:
State of Louisiana Radiation Control Program Director