ML18153A370

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Forwards Request for Addl Info Re 971126 Summary Rept in Response to GL 87-02,related to Seismic Qualification of Mechanical & Electrical Equipment
ML18153A370
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/23/1998
From: Edison G
NRC (Affiliation Not Assigned)
To: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
GL-87-02, GL-87-2, TAC-M69484, TAC-M69485, NUDOCS 9803020179
Download: ML18153A370 (5)


Text

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~ February 23, 1998 Mr. J. P. O'Hanlon Senior vice President - Nuclear Virginia Electric and power Company 5000 Dominion Boulevard

~len Allen, VA 23060 e

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2-REQUEST FOR ADDITIONAL INFORMATION REGARDING SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (GL 87-02) (TAC NOS. M69484 AND M69485)

Dear Mr. O'Hanlon:

In your letter dated November 26, 1997, you provided a summary report in response to Generic Letter 87-02, related to seismic qualification of mechanical and electrical equipment.

The NRC staff is reviewing the summary report as discussed on February 18, 1998, with G.

Miller of your licensing staff. Additional information (enclosure) is requested in order for the staff to complete its review.. We request your response within 60 days of receipt of this letter.

Docket Nos. 50-280 and 50-281

Enclosure:

Request for Additional Information cc w/ericl: See next page Sincerely, Origin~l Signed by:

Gordon E. Edison, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation DISTRIBUTION:

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e February 23, 1998 Mr. J. P. O'Hanlon Senior vice President - Nuclear Virginia Electric and power Company 5000 Dominion Boulevard Glen Allen, VA 23060 e

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (GL 87-02) (TAC NOS. M69484 AND M69485)

Dear Mr. O'Hanlon:

In your letter dated November 26; 1997, you provided a summary report in response to Generic Letter 87-02, related to seismic qualification of mechanical and electrical equipment.

The NRC staff is reviewing the summary report as discussed on February 18, 1998, with G.

Miller of your licensing staff. Additional information (enclosure) is requested in order for the staff to complete its review. We request your response within 60 days of receipt of this letter.

Docket Nos. 50-280 and 50-281

Enclosure:

Request for Additional Information cc w/encl: See next page DISTRIBUTION:

P. T. Kuo Sincerely, Original Signed by:

Gordon E. Edison, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation ACRS Docket File PUBLIC PDll-1 R/F J. Zwolinski (A)

E. Dunnington G. Edison OGC L. Plisco, Region II

  • DOCUMENT NAME: G:\\SURRY\\M69489.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosur1t ;'N" = No copy A/.

OFFICE PM:PDII-1

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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 February 23, 1998 Mr. J. P. O'Hanlon Senior vice President - Nuclear Virginia Electric and power Company 5000 Dominion Boulevard Glen Allen, VA 23060

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (GL 87-02) (TAC NOS. M69484 AND M69485)

Dear Mr. O'Hanlon:

In your letter dated November 26, 1997, you provided a summary report in response to Generic Letter 87-02, related to seismic qualification of mechanical and el~ctrical equipment.

The NRC staff is reviewing the summary report as discussed on February 18, 1998, with G.

Miller of your licensing staff. Additional information (enclosure) is requested in order for the staff to complete its review. We request your response within 60 days of receipt of this letter.

Docket Nos. 50-280 and 50-281

Enclosure:

Request for Additional Information cc w/encl: See next page Sincerely, Gordon E. Edison, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

L Mr. J.P. O'Hanlon Virginia Electric and Power Company cc:

Mr. Michael W. Maupin, Esq.

Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. David Christian, Manager Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Robert B. Strobe, M.D., M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. J. H. McCarthy, Manager Nuclear Licensing & Operations Support Innsbrook Technical Center Virginia Electric and Power Company

- 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. R. C. Haag U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. W. R. Matthews, Manager North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117

Request For Additional Information Regarding the Verification of Seismic Adequacy of Mechanical and Electrical Equipment

a.

Describe what reviews were performed to determine if any local operator actions required to safely shut down the reactor (i.e., implement the safe shutdown equipment list (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 and describe the reviews which were conducted to ensure operators had adequate time and resources to respond to such events.

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, ~tands, printers, etc.).

Describe how each of these potential sources of interactions 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 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" 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 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 Operating Procedures were modified to provide plant staff with additional guidance on mitigating the A-46 Seismic Event, describe what training was required and provided to the licensed operators, non-licensed operators, and other plant staff required to respond to such events.

Enclosure