ML19309F942
| ML19309F942 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/04/1980 |
| From: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML19309F937 | List: |
| References | |
| IEB-79-27, NUDOCS 8005020042 | |
| Download: ML19309F942 (6) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Tennessee Valley Authority
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Docket No. 50-259 (Browns Ferry Unit No. 1)
)
CONFIRMATORY ORDER I
Tennessee Valley Authority (the " licensee") is the holder of Facility Operating License No. OPR-33 (the " license") with an expiration date of May 10, 2007, which authorizes operation of the Brosns Ferry Unit No.1 (the " facility").
II On November 10, 1979, an event occurred at the Oconee Power Station, Unit 3, that resulted in loss of power to a nonclass 1-E 120 Vac single phase power panel that supplied poaer to the Integrated Control System and the Nonnuclear Instrumentation System.
This loss of power resulted in control system malfunc-tions and significant loss of information to the control room operator.
This event was described in Information Notice 79-29, dated November 16, 1979, onich was sent to this licensee.
This licensee was requested by IE Bulletin 79-27, dated November 30, 1979, " Loss of Nonclass 1-E Instrumentation and Control Power 3us During Operation" to review, among other things, buses supplying power to certain instrument and control systers, emergency procedures related to loss of power to such buses and failure to certain power supplies.
In accordance with Bulletin 79-27 the licensee was requested to submit to the Commission the results of its review by February 28, 1980.
This licensee has not met this date.
O.
On February 26, 1980, an event occurred at Crystal River Unit No. 3 that also J
involved a loss of instrument and control power.
This event was described in Information Notice 80-10, " Partial Loss of Nonnuclear Instrument System Power i
Supply During Operation," dated March 7, 1980.
Because of the implications of j
the Crystal River Unit No. 3 event on February 26, 1950 and because of the potential adverse effects on public health and safety that could result from future events of this type, the information requested in IE Bulletin 79-27 must be submitted in order that NRC can determine whether this license should i
be modified to protect the health and safety of the public.
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t The Licensee has committed by letter dated March 28, 1980, supplemented by telephone conversations between Commission representatives and Mr. L. M. Mills and others of the Licensee organization on March 27, 1980, that it would i
provide the information required by Bulletin 79-27 as revised in Attachment A t
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to this Order, by July 1,1980.
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In view of the importance of this matter, I have determined that these I
commitments should be formalized by order and that the public healtn, safety and interest require that this action be made immediately.. effective.
Accord-i ingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Commission's regulations.in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED, EFFEC E /E IlltaDIATELY, THAT:
i (1) The licensee shall submit to the Director of Reactor Operations 1
Inspection, Washington, D.C. 20555 and to the Director of the 1
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. appropriate NRC Regional Office, written statements under oath containing the information required in Attachment A to this Order; and (2) The licensee shall submit the statements on or before July 1, 1980.
IV Any person who has an interest affected by this Order may request a hearing within twenty-five (25) days of the date of the Order.
Any request for a hearing will not stay the effectiveness of this Order.
Any request fa,r a hearing shall be submitted to the Director, Office of Inspection and Enforce-ment, U. S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a ccpy to the Executive Legal Director at the above address.
If a hearing is requested by a person who has an interest affected by this Order, the Cocmission will issue an Order designating the time and place of any such hearing.
V In the event a person who has an interest affected by this Order requests a hearing as provided above and a hearing is held, the issues to be considered at such a hearing shall be:
(1) Whether the facts set forth in Part II of this Order provide an adequate basis for the actions ordered; (2) 'nhether the Licensee should perform the actions required in Part III of this Order in accordance with the schedule stated therein.
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Operation of the facility on terms consistent with this Order is not stayed by the pendency of any proceedings on the Order.
FOR THE NUCLEAR REGULATORY COMMISSION
/
/
s Victor Stello, Jr/ '
Director Office of Inspection and Enforcement Dated at Bethesda, Maryland cn this & ^
day of April, 1980 l
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i Attachment A i
1.
Review the class 1-E and nonclass 1-E buses supplying power to safety i-and non-safety related instrumentation and control systems which could
- 1 affect the ability to achieve a cold shutdown condition using existing i
4 procedures or procedures developed under item 2 below.
For each bus:
a) identify and review the alarm and/or indication provided in the control _ room to alert the operator to the loss of power t'o the bus.-
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b) identify the instrument and control system loads connected to the bus and evaluate the effects of loss of power to these loads i
including the ability to achieve a cold shutdown condition.
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c) describe any proposed design modifications resulting from these reviews and evaluations, and your proposed schedule for implementing l
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those modifications.
I 2.
Review emergency procedures that will be used by control room operators, i
including procedures required to achieve a cold shutdown condition, upon loss of power to each class 1-E and nonclass 1-E bus. supplying power to safety and.non-safety related instrument and control systems.
At a j
minimum, the review shall assure that energency. procedures include:
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a) the diagnostics / alarms / indicators / symptoms resulting from th'e review and evaluation-conducted per item 1 above.
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b) the use of-alternate indication and/or control circuits which may be powered from other nonclass 1-E or class 1-E instrumentation and i
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control-buses.
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c) methods for restoring power to the bus.
i Provide a description of the changes to the emergency procedures and f
administrative controls that have been prepared to conform to items 2a, 2b and 2c above and provide a description of and schedule for implementa-i tion of any design changes resulting from the changes to emergency procedures and administrative controls.
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3.
Re-review IE Circular No. 79-02, " Failure of 120 Volt Vital AC Power Supplies," dated January 11, 1979, to include both class 1-E and nonclass l
1-E safety related p.ooer supply inverters.
Based on a review of operating experience and your re-review of IE Circular No. 79-02, describe any administrative controls that have been implemented as a result of the s
re-review and describe.any proposed design modifications and schedule for completion to be implemented as a result of the re-review.
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