ML20149N091
| ML20149N091 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/25/1988 |
| From: | Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20149N081 | List: |
| References | |
| 50-254-87-33, 50-265-87-33, IEB-85-003, IEB-85-3, NUDOCS 8803010185 | |
| Download: ML20149N091 (1) | |
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Notice of Deviation Commonwealth Edison Docket No. 50-254 Docket No. 50-265 As a result of the inspection conducted on Des ^er 6, 1987 through February 6, 1988, and in accordance with the "General Policy and Procedures for NRC Enforce-ment Actions," 10 CFR Part 2, Appendix C, the following deviations were identified:
1.
As stated in 10 CFR 50.55 a(g)(6)(ii), "the Comission may require the licensee to follow an augmented inservice inspection program for systems and components for which the comission deems that added assurance of structural reliability is necessary." IE Bulletin 85-03 (IEB) required that licensees develop and implement a program by November 15, 1987, to ensure that valve operator switches are selected, set and maintained properly for motor-operated valves in the HPCI/ core spray and RCIC systems that are required to be tested for operational readiness in accordance with 10 CFR 50.55 a(g).
In responses to IE Bulletin 85-03 dated May 15, 1986, and April 24, 1987, the licensee described a program and schedule to satisfy IEB 85-03 by November 15, 1987.
Contrary to the above, the licensee did not notify the NRC until November 24, 1987, that Quad Cities had not complied with the requirements of IE Bulletin 8E 03 and would not be in compliance until the April 1988 refueling outage.
The failure to comply with the requirements of IE Bulletin 85-03 within the specified time frame and the failure to inform the NRC of this fact prior to the required compliance date are together considered a Deviation from the licensee's comitment.
2.
In the FSAR the licensee comits to the ASME code which requires that supports for safety system components adhere to seismic criteria.
Contrary to the above, on December 19, 1987, Commonwealth Edison's BWR Engineering concluded that the ATWS (anticipated transient without scram) support hangers for the reactor vessel instrument racks on Unit 1 (racks 2201-5 and 6) and Unit 2 (racks 2202-5 and 6) did not meet ASME code requirements for seismic support, though they did meet operability requi rements.
This problem was discovered on December 1, 1987, by the Senior Resident Inspector.
This is considered a Deviation from the licensee's commitment.
Pursuant to the provisions of 10 CFR Part 2 Appendix C, Part H., Comonwealth Edison is required to submit to this Office within thirty days of the date of the letter transmitting this notice, a written statement or explanation in reply, including for each deviation:
(1) The reason for the deviations if admitted; (2) the corrective steps which have been taken and the results achieved; (3) the corrective steps which will be taken to avoid further deviations; and (4) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending your response time.
Ib Orb ( b O W -
Dated 9803010185 880225 W. L. Forney, Chief Q
{DR ADOCK 0500 4
Reactor Projects Branch 1
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