U-600013, Forwards Supplemental Info in Response to IE Bulletin 84-03 Re Refueling Cavity Water Seal,In Response to Insp on 850305-11.Operator Actions for Refueling Bellows Failure Described
| ML20126C614 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/05/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-84-03, IEB-84-3, U-600013, NUDOCS 8506140479 | |
| Download: ML20126C614 (3) | |
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U-600013 LO8-85 (06-05)-L 1A.120 ILLINOIS POWER COMPANY CLINToN POWER STATION. P.o. box 678. CLiNToN. ILLINots 61727 June 5, 1985 Docket No. 50-461 Mr. James G. Keppler Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
IE Bulletin 84-03: Refueling Cavity Water Seal
Dear Mr. Keppler:
In response to the routine safety inspection conducted by Mr. T. P.
Gwynn, of the NRC Region III office on February 5, 1985 through March 11, 1985, the following supplemental information in response to IE Bulletin 84-03 is provided for your review.
The following Clinton Power Station Plant procedures were reviewed:
1000 Series - Administrative Procedures 1013.02 Fuel Handling 2000 Series - Technical Procedure No relevant procedures identified 3000 Series - System / Plant Operating Procedures 3317.01 Fuel Pool Cooling and Cleanup 3701.01 New Fuel Receiving and Inspection 3702.01 Inclined Fuel Transfer System 3702.01 Refueling Operations 3703.02 Fuel Handling Platform Operation 4000 Series - Off-normal Procedures 4001.01 Reactor Coolant Leakage 5000 Series - Annunciator Procedures 5040.37 Low Level Containment Transfer Pool 5040.38 Low Level Upper Containment Pool 5067.33 High High Level Drywell Sump Equipment / Floor Drain 5067.44 High Flow Containment /Drywell Equipment Floor Drain 5068.02 Drywell Floor Drain Sump Leakage High 5068.05 Drywell Equipment Drain Sump Leakage JUN 6198$
5068.19 eling Bellows Leakage 506140479 850605
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U-600013 LO8-85 (06-05)-L 1A.120 6000 Series - Chemical / Radiochemical Procedures No relevant procedures identified 7000 Series - Radiation Protection Procedures 7400.07 Operation of Fixed Analog Area Radiation Monitor 8000 Series - Maintenance Department Procedures No relevant procedures identified 9000-Series - Surveillance Procedures 9000.02 Unit. Attendant Surveillance Log 9000.03 Core Alteration Log 4
To ensure that-in the unlikely event of a refueling bellows failure operator actions are appropriate, the operators first must be aware that this leakage is occurring and secondly must take proper mitigating actions based upon this knowledge. The discussion that follows will consider each aspect separately.
A.
Operator Awareness of Situation The existing procedures appear adequate to inform the operator of a bellows leakage condition. The alarms associated with Annunciator. Procedures 5040.37, 5040.38, 5067.33, 5067.44, 5068.02, 5068.05 and 5068.19 are all capable of providing indications of refueling bellows leakage. Even though the instruments feeding these alarms are non-safety related, it is believed that sufficient redundancy exists to ensure that the
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plant operators will be aware of the refueling bellows leakage condition.
In addition, a low water condition in the upper containment pool would be easily observable to the operator in control of the fuel handling platform.
B.
Operator Mitigating Actions Annunciator Procedures 5040.37 Low Level Containment Transfer Pool, 5040.38 Low Level Upper Containment Pool, and 5068.19 Refueling Bellows Leakage plus Radiation Protection Procedure 7400.07 Operation of Fixed Analog Area Radiation Monitors provide the operators with instructions to handle a bellows leakage event. The Annunciator procedures refer the operator to procedure 3317.01 Fuel Pool Cooling and Cleanup to have the operator provide makeup flow to these pools. The Radiation Protection Procedure instructs the Fuel Handling Platform Operator to lower items into a safe location, when a high radiation alarm occurs in the area.
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- LO8-85 (06-05)-L 1A.120 Failure of the refueling bellows used at Clinton Power Station
- would require structural failure of welded components. This event is considered to be highly _unlikely and the need for plant modifications or an Off-Normal Procedure to address this specific event is not believed necessary.
This supplemental information resolves the concerns on IE Bulletin 84-03 identified by the referenced inspection.
I hereby affirm that the information in this letter is correct to the best of my knowledge.
Sincerely yours, d
a F. A.
pan nberg Dire or - Nuclea Licensing and Configuration Nuclear Station Engineering SMK/ lab cc:
B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Illinois Department of Nuclear Safety NRC Document Control Desk, Washington, D.C.
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