ML20217N183

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Forwards Request for Addl Info Pertaining to Operator Actions Following Events Addressed by Arkansas Nuclear One, Unit 1 & 2,summary Rept on Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML20217N183
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 04/03/1998
From: William Reckley
NRC (Affiliation Not Assigned)
To: Hutchinson C
ENTERGY OPERATIONS, INC.
References
TAC-M69426, TAC-M69427, NUDOCS 9804090038
Download: ML20217N183 (4)


Text

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! April 3, 1998'

( . Mr. C. Randy Hutchinson l . Vice President, Operations ANO Entergy_ Operations, Inc. ,

l 1448 S.R.333 ,

Russellville, AR 72801

SUBJECT:

REQUEST FOR ADD'ITIONAL INkbRMATION PERTAININ'G TO THE

. ARKANSAS NUCLEAR ONE, UNITS 1 AND 2,

SUMMARY

REPORT ON THE L VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL -

' EQUIPMENT, DATED APRIL 22,1996 (TAC NOS. M69426 AND M69427)-

Dear Mr. Hutchinson:

This is a request for additional information pertaining to operator actions following the i

events addressed by the Arkansas Nuclear One, Urdt 1 and'2, Summary Report on the Verification of Seismic Adequacy of Mechanical and Electrical Equipment dated April 22,1996.

The staffs questions on this matter are enclosed. Please contact me if you have any questions

. regarding this request for information.

l Sincerely,

ORIGINAL SIGNED BY

William Reckley, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV

. Office of Nuclear Reactor Regulation

. Docket Nos. 50-313 and 50-368

Enclosure:

Request for AdditionalInformation cc w/encls: See next page L

plSTRIBUTION.

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NUCLEAR REEULATORY COMMISSION WASHINGTON, D.C. 30806 4 001 8 April 3, 1998

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Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE ARKANSAS NUCLEAR ONE, UNITS 1 AND 2,

SUMMARY

REPORT ON THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT, DATED APRIL 22,1996 (TAC NOS. M69426 AND M69427)

Dear Mr. Hutchinson:

This is a request for additionalinformation pertaining to operator actions following the events addressed by the Arkansas Nuclear One, Unit 1 and 2, Summary Report on the Verification of Seismic Adequacy of Mechanical and Electrical Equipment dated April 22,1996.

The staff's questions on this matter are enclosed. Please contact me if you have any questions )

regarding this request for information.

Sincerely, IL William Reckley, Project Manag Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368

Enclosure:

Request for AdditionalInformation cc w/encis: See next page

t Mr. C. Randy Hutchinson I Entergy Operations, Inc. Arkansas Nuclear One, Units 1 & 2 cc:

Executive Vice President Vice President, Operations Support

& Chief Operating Officer Entergy Operations, Inc.

Entergy Operations, Inc. . P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Divisior: of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn  !

1400 L Street, N.W.

Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite ! '25 Rockville, MD 20852 Senior Resident inspector U.S. Nuclear Regulatory Commission l

P. O. Box 310 London, AR 72847 Regional Administrator, Region IV

. U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County  !

Pope County Courthouse - j Russellville, AR 72801 4

e i

i Request For Additional Informatior) Regarding the Licensee's Analysis on the Verification of Seismic Adeaumev of Mechanical and Electrical Eautoment in Ocaratino Ramae~s.

dated Acril 22.1996. Arkansas Nuclear One. Unit 1 & 2 Docket Number (s) SG StE36J The Human Factors Assessment Branch staff has completed its review of the licensee's submittal dated April 22,1996. The staff requires additionalinformation regarding operator f 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 the seismic event. Describe how staffing was evaluated j and describe the reviews which were conducted to ensure operators had adequate time j and resources to respond to such events.  ;

i

b. As part of the licensee's review, were any control room structures which could impact the '

operator'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 ofinteractions has been evaluated and describe the schedule for implementation of the final resolutions.

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

f. To the extent that Normal, Abnormal, and Emergency Operating Procedures were modified to provido plant staff with additional guidance on mitigating the A-46 Seismic Event, describe what training was required and provided to the licensed operators, non- i licensed operators, and other plant staff required to respond to such events.

ENCLOSURE