ML20217Q284
| ML20217Q284 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/02/1998 |
| From: | Dromerick A NRC (Affiliation Not Assigned) |
| To: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-M69435, TAC-M69436, NUDOCS 9803120146 | |
| Download: ML20217Q284 (4) | |
Text
Mr. Charles H. Cruse March 2, 1998 "Vice President - Nucle;r Energy B:ltimore G:s cnd Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 AND 2,
SUMMARY
REPORT ON THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED JUNE 28,1996 (TAC NOS. M69435 AND M69436)
Dear Mr. Cruse:
The NRC Staff is continuing its review of the licensee's submittal on verification of -
seismic adequacy of mechanical and electrical equipment in operating reactors, dated June 28, l
1996. The staff requires additionalinformation regarding operator actions specified in the report in order to make a safety determination. The information required is addressed in the enclosure.
Should you require additionalinformation, please contact me at 301-415-3473.
Sincerely, ORIGINAL BIGNED BY:
1 Alexander W. Dromerick, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 l
Enclosure:
Request for Additional Information l
I cc w/ encl: See next page
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March 2, 1998
.....p Mr. Charles H. Cruse Vice President-Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 AND 2,
SUMMARY
REPORT ON THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED JUNE 28,1996 (TAC NOS. M69435 AND M69436)
Dear Mr. Cruse:
The NRC staff is continuing its review of the licensee's submittal on verification of seismic adequacy of mechanical and electrical equipment in operating reactors, dated June 28,1996.
The staff requires additionalinformation regarding operator actions specified in the report in order to make a safety determination. The information required is addressed in the enclosure.
Should you require additionalinformation, please contact me at 301-415-3473.
Sincerely, Alexande W. Dromerick, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 I
Enclosure:
Request for Additional Information cc w/ encl: See next page
4
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Mr. Charles H. Cruse Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant cc:
i President Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland j
175 Main Street Engineering Division
(
Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire Counsel Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102 l
Baltimore, MD 21202-1631 l
Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge Patricia T. Bimie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Thomas N. Pritchett, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatell 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, TN 37411-4017 Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean, Manager Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Reauest For Additional information Rocardino the Licensee's Analysis on the Verification of Seismic Adecuacy of Mechanical and Electrical Eauipment in Operatino Reactors. dated June 28.1996. Calvert Cliffs Nuclear Power Plant. Unit Nos.1 and 2 Docket Nos. 50-317 and 50-318 The NRC staff has completed its review of the licensee's submittal dated June 28,1996. The stPIs requires additional information regarding operator actions specified in the report in order to raske 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 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 uma 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: main control room 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.
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 relcy 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 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