ML20196J307
| ML20196J307 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/28/1988 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20196J248 | List: |
| References | |
| 50-373-88-12, 50-374-88-11, NUDOCS 8807060357 | |
| Download: ML20196J307 (2) | |
Text
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s NOTICE OF VIOLATION Comonwealth Edison Company Docket No. 50-373 Docket No. 50-374 As a result of the inspection conducted on April 4-6 and May 3,1988, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1987),'the following violations were identified:
1.
10 CFR 50, Appendix B, Criterion XVI, as implemented by Commonwealth Edison Company Quality Assurance Manual. Nuclear Generating Station, Section 16, requires, in part, that measures be established to assure that conditions adverse to quality such as deficiencies, nonconformances, deviations...
which are adverse to quality and might affect the operation of a nuclear generating station are promptly identified and corrective action taken to preclude repetition for significant conditions adverse to quality.
Contrary to the above, the following instances were identified in which the licensee failed to promptly identify and correct deficiencies associated with the drywell temperature monitoring program:
a.
During the period of November 1987 to February 1988, the licensee failed to take action to repair an inoperable continuously monitoring, 14 point, drywell temperature recorder.
Consequently, drywell temperature data from 14 sensors located adjacent to safety-related components was not taken for approximately three months. This data is normally used in Environmental Qualification evaluations to ensure that sufficient remaining qualified life exists for safety-related components located inside the drywell, b.
During the period of November 1987 to March 1988, the licensee failed to obtain and transmit daily temperature readings from sensor 1TE-VP211 (located by MSIV "D") to Boiling Water Reactor Engineering Department (BWRED) for evaluation. Sensor 1TE-VP211 has indicated temperatures which were above the trigger set point for an extended period of time.
This is a Severity Level IV violation (Supplement I).
2.
Technical Specification 3.7.7 (Area Temperature Monitoring) states that "The temperature of each area of Unit 1 and Unit 2 shown in Tat,le 3.7.7-1 shall be maintained within the limits indicated in Table 3.7.7-1".
Technical Specification Action item for 3.7.7.a requires that with one or more areas exceeding the temperature limit (s) shown in Table 3.7.7-1 for more than eight hours, the licensee shall prepare and submit a Special Report to the Comission within the next 30 days and include an analysis to demonstrate the continued operability of the affected equipment.
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Notice of-Violation 2
Contrary to the above, on June 29, 1987, Unit 2 drywell temperature readings obtained by Sensor 2TE-VP204, located in the vicinity of Safety Relief Valves D and J, exceeded the limit specified by Technical Specification Table 3.7.7-1.
However, a Special Report was not submitted to the NRC within the time frame required by Technical Specification 3.7.7.a.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation:
(1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
JUN 2 81988 Dated H. J. Miller, Director Division of Reactor Safety
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