ML19309F215
| ML19309F215 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/04/1980 |
| From: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| Shared Package | |
| ML19309F216 | List: |
| References | |
| IEB-79-27, NUDOCS 8004290006 | |
| Download: ML19309F215 (6) | |
Text
8004290 O Q (,j r
'sj UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Power Authority of the State of
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Docket No. 50-286 New York
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(Indian Point Unit No. 3)
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CONFIRMATORY ORDER I
The Power Authority of the State of New York (the " licensee") is the holder of Facility Operating License No. DPR-64 (the " license") with an expiration date of August 13, 2009, which authorizes operation of the Indian Point Unit No. 3 (the " facility' ).
II On November 10, 1979, an event occurred at the Oconee Power Station, Unit 3, that resulted il loss of power to a nonclass 1-E 120 Vac single phase power panel that supplied power 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, which 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 i
Control Power Bus During Operation" to review, among other things, buses L
supplying power to certain instrument and control' systems, 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.
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-g-On February' 26,1980, an event occurred at Crystal River Unit No. 3 that also involved a loss of instrument and control power.
This event was described in l
Information Notice 80-10, " Partial Loss of Nonnuclear Instrument System Power i
Supply During Operation," dated March 7, 1980.
Because of the implications of the Crystal River Unit No. 3 event on February 26, 1980 and because of the poten-tial 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 ordsr that NRC can determine whether this license should be modified to protect the health and safety of the pub'lic.
The Licensee has committed by letter dated February 28, 1980, supplemented by I
telephone conversations between Commission representatives and Mr. J. P. Bayne of the Licensee organization on March 26, 1980, that it would provide the information required by Bulletin 79-27 as revised in Attachment A to this Order, by May 30, 1980.
i III In view of the importance of this matter, I have determined that these commitments should be formalized by order and that the public health, safety and interest require that this action be made immediately effective.
Accord-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, EFFECTIVE IMMEDIATELY, THAT:
(1) The licensee shall submit to the Director of Reactor Operations Inspection, Washington, D.C. 20555 and to the Director of the l
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1 l 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 May 30, 1980.
I IV i
i Any person who has an interest affected by this Order may request a hearing within twenty-five (25) days of the date of tha Order.
Any request for a hearing will not stay the effectiveness of this Order.
Any request for a j
hearing shall be submitted to the Director, Office of Inspection and Enforce-ment, U. S. Nuclear Regulatcry Commission, Washington, D.C.
20555, with a
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copy 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 Commission will issue an Order designating the time and place of.any such hearing.
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i-In the event a person who has an interest affected by this Order requests a j
hearing as provided above and a hearing is held, the issues to be considered at such a hearing shall be:
i (1) Whether the facts set forth in Part II of this Order provide an adequate basis for the actions ordered; i
l (2) Whether the Licensee should perform the actions required in Part Ill 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 h
4 Vittor Stello, 'Jrr Director Office of Inspection and Enforcement Dated at Bethesda, Maryland on this Pd day of April, 1980 i
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Attachment A 1.
Review the class 1-E and nonclass 1-E buses supplying power to safety i
and non-safety related instrumentation and control systemt. which could affect the ability to achieve a cold shutdown condition using existing procedures or procedures developed under item 2 below.
For each bus:
I a) identify and review the alarm and/or indication provided in the control room to alert the operator to the loss of power to the bus.
b) identify the instrument and control system loads co.nnected to the l
bus and evaluate the effects of, loss of.p_cwer to these loads l
including the ability to achieve a cold shutdown condition.
c) describe any proposed design modifications resulting from these reviews and evaluations, and your proposed schedule for implementing those modifications.
2.
Review emergency procedures that will be used by control room operators, i
including procedures required to achieve a cold shutdown condition, upon j
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 emergency procedures include:
.i a) the diagnostics / alarms / indicators / symptoms resulting from the 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 control buses.
c) methods for restoring power to the bus.
Provide a description of the changes to the emergency procedures and administrative controls that have been prepared to conform to items 2a, 2b and 2c above and provide a description of and schedule for implementa-tion of any design changes resulting from the changes to emergency procedures and administrative controls.
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 nonc1tss 1-E safety related power 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 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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