ML20137V925

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Notice of Violation from Insp on 850812-14,26-28 & 0903
ML20137V925
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/06/1985
From: Paperiello C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20137V922 List:
References
50-373-85-26, 50-374-85-27, NUDOCS 8512100124
Download: ML20137V925 (3)


Text

4 Appendix A NOTICE OF VIOLATION ,

Comonwealth Edison Company Docket No. 50-373 Docket No. 50-374 As a result of the inspection conducted on August 12-14, 26-28 and September 3, 1985, and in accordan,ce with the General Policy and Procedures for NRC Enforce-ment Actions, (10 CFR'Part 2, Appendix C), the following violations were identified:

1. states that Technical Specification "The temperature of each 3.7.7 (Area area Temperature of Unit 1 and Unit Monitoring) 2 shown in Table 3.7.7-1 shall be maintained within the limits indicated in Table 3.7.7-1". TS 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 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the licensee shall prepare and submit a Special Report to the Comission within the next 30 days and includir.g an analysis to demonstrate the continued operability of the affected equipment.

Contrary to the above, the temperature limits of Table 3.7.7-1 were exceeded in the Unit 1 drywell during numerous and extended periods during 1984 and 1985 and a Special Report for these events were not submitted in a timely manner to the Comission to demonstrate the continued operability of the affected equipment.

This is a Severity Level IV violation (Supplement I).

2. 10 CFR 50, Appendix B, Criterion XIV, as implemented by Comonwealth Edison Company Quality Assurance Manual, Nuclear Generating Stations, Section 14, requires that measures be established for indicating the operating status of structures, systems, and components, such as by tagging.

Contrary to the above, on August 12 and 28, 1985, operator yellow caution tags attached in September 1984 to the control room containment monitoring recorders 2TR-CM037 and 2TR-CM038 indicated that the recorder alarms were set at 150 F whereas calibration records indicated that these alarms had been set at 140 F and 141 F respectively since January 26, 1984.

This is a Severity Level IV violation (Supplement I).

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0512100124 851206 3 ADOCK 0500 gDR

J Appendix 2 i

3. 10 CFR 50, Appendix B, Criterion V, as implemented by Commonwealth Edison Company (CECO) Quality Assurance Manual, Nuclear Generating Station, l Section 5,-requires that activities affecting quality be performed in accordance with documented instructions and procedures of a type appropriate to the circumstances.

Contrary to the above, the following examples of failure to follow procedures or lack of documented procedures were identified:

a. CECO procedure LLP 84-21: (1) Did not contain a specific time table i

for monitoring drywell temperatures, (2) The " checking" and " reviewer" signatures were missing from the available drywell temperature monitor-  !

i ing data, (3) The drywell temperature monitoring data was submitted to S&L in a noncontrolled manner contrary to Ceco Quality Procedure Q.P.

No. 6-1 titled " Distribution of Design Documents," (4) Acceptance criteria for Equipment Qualification (EQ) threshold temperatures used to assure component qualified life was erroneous in that ambient rather than housing temperatures were used, and (5) Attachments A and D lacked documented evidence of site engineering review as required by the QA Program, Section 6.
b. Documented procedures were not available to address corrective actions to be taken by power plant operational personnel when temperatures exceed the'TS 3.7.7 limits. '

i

c. A documented surveillance procedure requiring inspections and surveillance of piping or equipment insulation and other potential sources of increased sensible heat load, prior to closure of the drywell and return to power was not available.

This is a Severity Level IV violation (Supplement I).

u 10 CFR 50, Appendix B, Criterion XVI, as implemented by Commonwealth Edison 4.

Company Quality Assurance Manual, Nuclear Generating Stations, Section 16, requires that measures be established to assure that conditions adverse to quality such as deviations, nonconformances . . . are promptly identified j and corrected.

Contrary to the above, the licensee's Station Nuclear Engineering Department (SNED) failed to respond in a prompt and responsible manner regarding their evaluation and recommendations for containment monitoring (temperature) alarm set points as recalculated and supplied by S&L. S&L submitted this  !

data through the LaSalle plant management for SNED review and evaluation in December 1984 for Unit I and January 1985 for Unit 2. Requested response 1 dates were designated as January and February 1985; however, as of I

August 14, 1985, no effective action had been taken by SNED engineers to

! disposition this issue.

! This is a Severity Level IV violation (Supplement I). .

W

Appendix 3 Pursuant of 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 violation and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

l% b l } -

Dated' / /

C. J.//Paperit/Ilo, Director Division of feactor Safety

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