ML17265A599
| ML17265A599 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/10/1999 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M69449, NUDOCS 9903190020 | |
| Download: ML17265A599 (9) | |
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L)r. Robert C. Mecredy Vice President, Nuclear rations Rochester Gas and Electric Corporation 89 East Avenue p/
Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL'INFORMATION(RAI) REGARDING THE R.E.
GINNA NUCLEAR POWER PLANT,
SUMMARY
REPORT ON THE VERIFICATIONOF SEISMIC ADEQUACYOF MECHANICALAND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED JANUARY31, 1997 (TAC NO. M69449)
March 'i0, 1999
Dear Dr. Mecredy:
The NRC staff has completed its review of your submittal on verification of seismic Sincerely, adequacy of mechanical and electrical equipment in operating reactors, dated May 27, 1997.
The staff requires additional information regarding operator actions specified in the report in order to make a safety determination.
The enclosed request for additional information identifies the information needed to continue the review. A draft of the needed information was e-mailed to your staff on February 12, 1999, for the purpose of making a determination as to when you would be able to respond.
We discussed this with your staff on February 23, 1999, at which time your staff indicated that, considering the upcoming refueling outage and other activities, you would be able to respond within 90 days of the date of this letter.
Ifyou have any questions concerning this request, please advise me.
99033.'70020 9 P03i0 PDR ADQCK 05000244 P
PDR Docket No. 50-244
Enclosure:
As stated Original sianed by:
Guy S. Vissing, S nior Project Manager Project Directorate 1-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation me 81K cBBiKR LIPS R. Eckenrode G. Galletti ccw/encl: See next page DISTRIBUTION:
PUBLIC S. Bajwa R. Blough, Rl PDI-1 R/F S. Little OGC J. Zwolinski/S. Black G. Vissing ACRS DOCUMENT NAME: G:FGINNAERAI69449.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N"= No co OFFICE PH:PDI-1 HAHE Gviss'ng/rsl DATE D3
/99 LA:PDI-SLitt 03/I 0/99 D:PDI-1 SBajwa 03/
/99 Official Record Copy
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RE VEST FOR ADDITIONALINFORMATIONREGARDING THE LICENSEE'S ANALYSIS ON THE VERIFICATIONOF SEISMIC ADE UACYOF MECHANICALAND ELECTRICAL E UIPMENT IN OPERATING REACTORS DATED JANUARY31 1997 R.E. GINNA NUCLEAR POWER PLANT DOCKET NUMBER 50-244 The NRC staff has completed its review of the licensee's submittal dated January 31, 1997.
The staff requires additional information regarding operator actions specified in the report in.
order to make a safety determination.
Describe what reviews were performed to determine ifany 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 time and resources to respond to such events.
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 of interactions has been evaluated and describe the schedule for implementation of the final resolutions.
Describe what reviews were performed to determine ifany 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.
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. Ifnot 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?
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' Enclosure
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C 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.
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Sr. Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. WilliamValentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399
. Charles Donaldson, Esquire Assistant Attorney General New York Department of Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Falls Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
'Dr. Robert C. Mecredy ~
Vice President, N'uclea erations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 IIarch 10, 1999
SUBJECT:
REQUEST FOR ADDITIONALINFORMATION(RAI) REGARDING THE R.E.
GINNA NUCLEAR POWER PLANT,
SUMMARY
REPORT ON THE VERIFICATIONOF SEISMIC ADEQUACYOF MECHANICALAND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED JANUARY31, 1997 (TAC NO. M69449)
Dear Dr. Mecredy:
The NRC staff has completed its review of your submittal on verification of seismic adequacy of mechanical and electrical equipment in operating reactors, dated May 27, 1997.
The staff requires additional information regarding operator actions specified in the report in order to make a safety determination.
The enclosed request for additional information identifies the information needed to continue the review. A draft of the needed information was e-mailed to your staff on February 12, 1999, for the purpose of making a determination as to when you would be able to respond.
We discussed this with your staff on February 23, 1999, at which time your staff indicated that, considering the upcoming refueling outage and other activities, you would be able to respond within 90 days of the date of this letter.
Ifyou have any questions concerning this request, please advise me.
Sincerely, Docket No. 50-244
Enclosure:
As stated Original sianed h~:
Guy S. Vissing, Senior Project Manager Project Directorate l-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation ccw/encl: See next page DISTRIBUTION:
PUBLIC
'. Bajwa PDI-1 R/F S. Little J. Zwolinski/S. Black G. Vissing DOCUMENT NAME: G:EGINNAiRAI69449.WPD To receive a copy of this document, indicate in the box:
with attachment/enclosure "N"= No co R. Blough, Rl OGC ACRS R. Eckenrode G. Galletti "C" = Copy without attachment/enclosure "E" = Copy OFFICE PH:PDI-1 IIANE Gviss ng/rsl DATE 03
/99 E
LA:PDI-SLitt 03/ 0/99 D:PDI-1 SBajva 03/
/99
/au~ 0rr-Official Record Copy
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 bhrch 10, 1999 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATION(RAI) REGARDING THE R.E.
GINNA NUCLEAR POWER PLANT,
SUMMARY
REPORT ON THE VERIFICATIONOF SEISMIC ADEQUACYOF MECHANICALAND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED JANUARY31, 1997 (TAC NO. M69449)
Dear Dr. Mecredy:
The NRC staff has completed its review of your submittal on verification of seismic adequacy of mechanical and electrical equipment in operating reactors, dated May 27, 1997.
The staff requires additional information regarding operator actions specified in the report in order to make a safety determination.
The enclosed request for additional information identifies the information needed to continue the review. A draft of the needed information was e-mailed to your staff on February 12, 1999, for the purpose of making a determination as to when you would be able to respond.
We discussed this with your staff on February 23, 1999, at which time your staff indicated that, considering the upcoming refueling outage and other activities, you would be able to respond within 90 days of the date of this letter.
Ifyou have any questions concerning this request, please advise me.
Sincerely, Docket No. 50-244
Enclosure:
As stated cc w/encl: See next page Ps Guy S. Vissing, Seni Project Manager Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation