ML20207P650

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Rev 1 to NRC Notification Inadequate
ML20207P650
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/05/1987
From: Birchell R, Knightly J, Stewart D
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207P454 List:
References
SWEC-SQN-23, SWEC-SQN-23-R01, SWEC-SQN-23-R1, NUDOCS 8701160366
Download: ML20207P650 (5)
v • d • e


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TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-23 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 1 TITLE: NRC Notification Inadequate REASON FOR REVISION: To incorporate TAS and SRP comments SWEC

SUMMARY

STATEMENT: The item in this report was identified by the Nuclear Regulatory Commission (NRC) and was included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. The item evaluated within this report was verified to be adequately addressed and is ready for NRC closure.

PREPARATION PREPARED BY:

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  • SRP Secretary's signature denotes SRP concurrences are in files.

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TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTHER SITES CEG Element

Title:

NRC NOTIFICATION INADEQUATE 4

SWEC Concerns: A02850305005-001 Source Document: NRC Report 50-328/85-06 Report Number: SWEC-SQN-23 f

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Report SWEC-SQN-23 NRC Notification Inadequate I. Introduction During an inspection covering the period of January 6 through February 5, 1985 (Reference 1), the Nuclear Regulatory Commission (NRC) residents identified one violation (328/85-06-01) which was included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis, as follows:

A02850305005-001 (Violation 328/85-06-01), NRC Notification Inadequate Ir. formation on the background, corrective actions taken, verification methodology, verification analysis, completion status, and pertinent references for this issue is included in this report.

II. Verification of SWEC Issue A. Background 10 CFR 50.'2 to(2)(1-1) requires the licensee to notify the NRC operations center as soon as practicable and in all cases, within four hours of any event or condition that reruits in manual or

! automatic actuation of the Reactor Protection System (RPS). 10 CFR 50.72 (c) " Followup Notification" requires that the results of ensuing evaluations or assessments of plant conditions and information related to plant behavior that is not caderstood be immediately reported.

Contrary to the above, on January 12, 1985, notification of the NRC operations center of an RPS actuation within the four hour requirement was made, however the licensee failed to report that the RPS train A trip breaker had failed to automatically open and was manually tripped. No follow-up notification to the operations center was made when licensee personnel determined that the initial report was incomplete.

B. Corrective Ia. tion Taken The corrective action for violation 328/85-06-01 (Reference 2), is applicable to this SWEC concern. Several discussions were held between Sequoyah Management and NRC personnel concerning this event, including the reporting aspect. It was agreed that events of this nature which were not included as part of the initial phone call would be included in a followup call as the information is known.

This clarification of policy was verbally transmitted to onshift personnel who would be responsible for 10 CFR 50.72 notifications, including the Shift Technical Adviser (STA). Further, a memorandum from the Operations Section manager to all licensed personnel and STAS was sent to provide written clarification on NRC phone calls.

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The clarification was added to the control room administrative l instruction. AI-18 " Plant Reporting Requirements - Notification and l Licensee Event Report," as follows: l l

In addition to making the required initial notification with I respect to the applicable events above: l ,

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Immediately report any further degradation in the level of lR1 safety of the plant or other worsening plant conditions l )

including those that require the declaration of the Emergency l l Classes, if such a declaration has not been previously made; or l l any change from one Emergency Class to another; or a termination l of the Emergency Class. 1 l

I Immediately report the results of ensuing evaluations or l l assessments of plant conditions, the effectiveness of response 1 or protective measures taken, and information related to plant I behavior that is not understood. l l

Maintain an open, continuous communication channel with the NRC l Operations Center upon request by the NRC. l C. Verification Methodology The SWEC concern identified for Employee Concerns Task Group (ECTG) verification was stated as follows:

RIMS # ISSUE RIMS ITEM A02850305005-001 Incomplete notification to RIMS-001 NRC on RPS actuation.

ECTC reviewed the Sequoyah Compliance Licensing files for internal and external correspondence related to this issue, the applicable control room instruction, and the NRC status and tracking system for the issue. This review of the pertinent documentation formed the basis for this verification activity.

D. Verification Analysis The ECTG review of the pertinent documents indicated that the corrective actions for this concern and the violation have been completed and are adequate to resolve the concern and violation. At the time of this ECTG verification, the NRC violation remains open; however, the SQN plant response has been found acceptable to the NRC (Reference 3), corrective actions have been completed, and the issue is considered by SQN to be ready for NRC closure.

E. Completion Status Based on SQN corrective action and compliance with requirements, this issue is considered complete and ready for NRC closure.

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e III. References

1. NRC Inspection Report Numbers 50-327/85-06 and 50-328/85-06, dated narch 1, 1985, David M. Vercelli to H. G. Parris
2. Response to NRC Inspection Report Numbers 50-327/85-06 and 50-328/85-06, dated March 20, 1985 H. L. Abercrombie to J. W. Hufham
3. NRC acknowledgment of TVA's response to Inspection Report Numbers 50-327/85-06 and 50-328/85-06, dated April 5, 1986, David M. Verre111 to H. G. Parris 9

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