ML20113B128
| ML20113B128 | |
| Person / Time | |
|---|---|
| Site: | Clinton |
| Issue date: | 01/04/1985 |
| From: | Hall D ILLINOIS POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| REF-PT21-85, REF-PT21-85-045-000 55-84-23, PT21-85-045-000, PT21-85-45, U-10237, NUDOCS 8501210335 | |
| Download: ML20113B128 (3) | |
Text
D/7][b ILLINOIS POWER OOMPANY 1A 120 IP u-1o237 CLINTON POMR STATION P.O. box 678. CLINTON, ILLINOIS 61727 January 4, 1985 Docket No. 50-461 Mr. James G. Keppler Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Potentially 10CFR50.55(e) Deficiency 55-84-23:
Ruskin Interlocking Blade Fire Dampers
Dear Mr. Keppler:
On December 3, 1984, Illinois Power Company notified Mr. F.
Jablonski, NRC Region III, (Ref:
IP memorandum Y-25989, dated August 28, 1984) of a potentially reportable deficiency j
concerning the failure of certain models of Ruskin Fire Dampers to close under installed air flow conditione.
Our investigation of this issue is progressing and this letter is submitted as an interim report in accordance with the requirements of 10CFR50.55(e).
Attachment A provides the details of our investigation to date.
We trust that this interim report provides you sufficient background information to perform a general assessment of this potentially reportable deficiency and adequately describes our overall approach to resolve the issue.
Sincerely yours, D.
. Hall, Vice President RLC/lr (NRCl)
Attachment cc:
NRC Resident Office, V-690 Director - Office of I&E, US NRC, Washington, DC 20555 Illinois Department of Nuclear Safety INPO Records Center g12gocP0foogg JAN 101985 3
s 1g
~
l
2 ATTACHMENT A Illinois Power Company Clinton Power Station Docket No. 50-461 Potentially Reportable 10CFR50.55(e) Deficiency 55-84-23 Ruskin Interlocking Blade Fire Dampers Interim Report Statement of Potentially Reportable Deficiency / Background On November 6, 1984, Ruskin, Division of Philips Industries, Inc. notified the NRC of a reportable 10CFR21 condition involving Ruskin Interlocking Blade Fire Damper, Model numbers IBD-21, 23,
& NIBD-23 supplied with closure springs.
Ruskin has determined that their test methods utilized for closure under air flow may not accurately depict actual field installed conditions.
Ruskin recommends that fire dampers supplied to CPS, with closure springs, which require closure under air flow conditions, be tested to verify proper operation.
Investigation Results Illinois Power has prepared and is implementing an investigation plan to determine the extent of this problem at the Clinton Power Station (CPS).
A review will be performed to:
1.
Determine the applicable damper model numbers utilized in safety related systems, and to identify those units by equipment identification number and system.
2.
Identify the system configuration, air flow condition, rating of fire dampers, and performance characteristics.
3.
Identify required damper closure conditions and associated control logic of the HVAC systems.
4.
Determine field testing requirements for verification of proper damper operation.
5.
Evaluate the recommended design modification, when issued by Ruskin.
Similar Concerns An investigation will be performed to determine the 10 pact of similar problems, associated with non-safety applications, on safety-related areas.
Page 1 of 2 L
T
~
Attachment A (continued)
Root Cause The root cause of the identified deficiency will be determined and evaluated by the manufacturer, Ruskin.
Corrective Action Corrective actions required to remedy the problem and any necessary equipment modification will be determined after Ruskin's investigation is completed for the 10CFR21 report.
Ruskin expects to complete their tests by January 30, 1985 and provide recommendations for modification by February 15, 1985.
Safety Implications / Significance Illinois Power's investigation of this potentially reportable deficiency is continuing.
The safety implications and significance will be assessed after all background information is evaluated.
It is anticipated that approximately ninety (90) days will be necessary to complete our investigation, determine reportability and submit a final report on the issue.
Page 2 of 2 L'