ML20205J273

Forwards Request for Addl Info Transmitted on 990224 to T Silko of Vermont Yankee Nuclear Power Corp.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI

ML20205J273
Person / Time
Site:	Vermont Yankee
Issue date:	03/09/1999
From:	Croteau R NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-M69490, NUDOCS 9904090255
Download: ML20205J273 (3)

Text

l,- =ch o, m l MEMORANDUM TO:M i

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION, VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT, TAC NO. M69490 The attached request for additional in' formation (RAl) was transmitted on February 24 1999, to Mr. T. Silko of Vermont Yankee Nuclear Power Corporation. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAl. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50 271

Attachment:

As stated 1

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,,,,,* March 9, i m MEMORANDUM TO: Docket File FROM: Richard Croteau, Project Manager '

Project Directorate 1-2 ,,

l Division of Licensing Project Management [ . - t (( 18',3' l Office of Nuclear Reactor Regulation

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION, VERIFICATION OF SEISMIC ADEOUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT, TAC NO. M69490 The attached request for additional information (RAl) was transmitted on February 24,1999, to Mr. T. Silko of Vermont Yankee Nuclear Power Corporation. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAl. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-271

Attachment:

As stated )

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4 DRAFT I

Reauest For AdditionalInformation Reaardina the Licensee's Analysis on the Verification of l Seismic Adeauacy of Mechanical and Electrical Eauipment in Operatina Reactors. l dated uly 1.1996. Vermont Yankee Nuclear Power Station Docket Number (s) 50-271 .

The Operator Licensing and Human Performance Branch staff has completed its review of the licensee's submittal dated July 1,1996. The staff requires additionalinformation regarding i operator actions specified in the report in order to make a safety determination. '

a. Describe what reviews were performed to determine if any local operator actions required to safely shutdown the reactor (i.e., implement the SSEL) could be affected by potentially adverse environmental conditions (such as loss of lighting, excessive heat or humidity, or in-plant barriers) resulting from tSe seismic event. Describe how staffing was evaluated and describe the reviews which were conducted to ensure operators had I adequate time and resources to respond to such events.

b. Ac part of the licensee's review, were any control room structures which could impact the opcrator's ability to respond to the seismic event identified? Such items might include but are not limited to: MCR ceiling tiles, non-bolted cabinets, and non-restrained pieces of equipment (i.e., computer keyboards, monitors, stands, printers, etc.).

Describe how each of these potential sources of interactions has been evaluated and describe the schedule for implementation of the final resolutions.

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c. Describe what reviews were performed to determine if any local operator actions were required to reposition " bad actor relays." For any such activities describe how adverse environmental conditions (such as loss of lighting, excessive heat or humidity, or in-plant barriers) resulting from the seismic event were analyzed and dispositioned. Describe how staffing was evaluated and describe the reviews which were conducted to ensure operators had adequate time and resources to respond to such events.

d. Describe which of the operator actions associated with resetting SSEL equipment affected by postulated relay chatter are considered to be routine and consistent with the skill of the craft. If not considered skill of the craft, what training and operational aids were developed to ensure the operators will perform the actions required to reset affected equipment?

e. Assume the alarms associated with " bad actor relays" are expected to annunciate during the seismic event. Do the operators have to respond to those annunciators and review the annunciator response procedures associated with them for potential action?

How would those additional actions impact the operators ability to implement the l Normal, Abnormal, and Emergency Operating Procedures required to place the reactor in a safe shutdown condition?

f. To the extent that Normal, Abnormal, and Emergency Og erating Procedures were modified to provide plant staff with additional guidance on m.tigating the A-46 Seismic l Event, describe what trAing was required and provided to the licensed operators, l non-licensed operators, and other plant staff required to respond to such events.

ATTACHMENT L-