ML060680459
| ML060680459 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/09/2006 |
| From: | Rogge J Engineering Region 1 Branch 3 |
| To: | Korsnick M Rochester Gas & Electric Corp |
| References | |
| Download: ML060680459 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406-1415 March 9, 2006 Mrs. Mary G. Korsnick Vice President, R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519
SUBJECT:
R. E. GINNA NUCLEAR POWER PLANT - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE TRANSITION TO 10 CFR 50.48 (C) IS IN PROGRESS
Dear Mrs. Korsnick:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a triennial fire protection baseline inspection at your Ginna Nuclear Power Plant beginning in June 2006. The inspection team will be led by Mr. Leonard Cheung, a fire protection specialist from the NRC Region I Office. The team will be composed of personnel from NRC Region I. The inspection will be conducted in accordance with IP 71111.05TP, the NRCs baseline fire protection inspection procedure for plants in the process of implanting 10 CFR 50.48 (C), NFPA 805. The inspection guidance is different from the regular triennial inspections in that the inspectors will concentrate on the fire protection program infrastructure in the adequacy of compensatory measures implemented for identified departure from code requirements. The inspectors will not routinely inspect or evaluate circuit related issues.
The schedule for the inspection is as follows:
Information gathering visit - May 23 - 25, 2006 Weeks of onsite inspection - June 5 - 9, 2006, and June 19 - 23, 2006.
The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Ginna Nuclear Power Plant fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training and badging for unescorted site access. A list of the types of documents the team may be interested in reviewing, and possibly obtaining, are listed in the enclosure.
During the information gathering visit, the team will also discuss the following inspection support administrative details: office space size and location; specific documents requested to be made available to the team in their office spaces; arrangements for reactor site access (including radiation protection training, security, safety and fitness for duty requirements); and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact during the inspection.
M. Korsnick 2
We request that during the onsite inspection weeks you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the Ginna Nuclear Power Plant fire protection program including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest are those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. Also, personnel should be available at the site during the inspection who are knowledgeable regarding those plant systems required to achieve and maintain safe shutdown conditions from inside and outside the control room (including the electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant fire protection systems and features, and the Ginna Nuclear Power Plant fire protection program and its implementation.
Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection team's information or logistical needs, please contact Leonard Cheung, the team leader, in the Region I Office at (610) 337-5296.
Sincerely,
/RA/
John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No.
50-244 License No.
Enclosure:
- 1. List of Reactor Fire Protection Program Supporting Documents cc w/encl:
M. J. Wallace, President, Constellation Generation J. M. Heffley, Senior Vice President and Chief Nuclear Officer P. Eddy, Electric Division, NYS Department of Public Service C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law C. W. Fleming, Esquire, Senior Counsel, Constellation Energy Group, Inc.
P. R. Smith, New York State Energy Research and Development Authority J. Spath, SLO Designee New York State Energy Research and Development Authority T. Wideman, Director, Wayne County Emergency Management Office M. Meisenzahl, Administrator, Monroe County, Office of Emergency Preparedness T. Judson, Central New York Citizens Awareness Network
M. Korsnick 3
Distribution w/encl:
(via E-mail)
S. Collins, RA M. Dapas, DRA B. Sosa, RI OEDO R. Laufer, NRR P. Milano, PM, NRR J. Trapp, DRP C. Khan, DRP K. Kolaczyk, DRP, Senior Resident Inspector M. Marshfield, DRP, Resident Inspector S. DiMora, DRP, Resident OA Region I Docket Room (with concurrences)
ROPreports@nrc.gov DOCUMENT NAME: G:\\DRS\\Engineering Branch 3\\Cheung\\GinnaFPletter.wpd SISP Review Complete: JFR (Reviewers Initials)
After declaring this document An Official Agency Record it will/will not be released to the Public.
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRS RI/DRS
/
NAME Lcheung LSC JRogge JFR DATE 03/09/06 03/09/06 OFFICIAL RECORD COPY
Enclosure ENCLOSURE List of Reactor Fire Protection Program Supporting Documentation
[Note: This is a broad list of the documents the NRC inspection team may be interested in reviewing, and possibly obtaining, during the information gathering site visit.]
1.
The current version of the Fire Protection Program and Fire Hazards Analysis.
2.
Current versions of the fire protection program implementing procedures (e.g.,
administrative controls, surveillance testing, fire brigade).
3.
Fire brigade training program and pre-fire plans.
4.
Post-fire safe shutdown systems and separation analysis.
5.
Post-fire alternative shutdown analysis.
6.
Piping and instrumentation (flow) diagrams showing the components used to achieve and maintain hot standby and cold shutdown for fires outside the control room and those components used for those areas requiring alternative shutdown capability.
7.
Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment.
8.
Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment.
9.
Plant layout drawings which identify the general location of the post-fire emergency lighting units.
10.
Plant operating procedures which would be used and describe shutdown from inside the control room with a postulated fire occurring in any plant area outside the control room, procedures which would be used to implement alternative shutdown capability in the event of a fire in either the control or cable spreading room.
11.
Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps and suppression systems.
12.
Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
13.
A sample of significant fire protection and post-fire safe shutdown related design change packages and Generic Letter 86-10 evaluations.
14.
The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information.
2 Enclosure 15.
Temporary modification procedures.
- 16.
Organization charts of site personnel down to the level of fire protection staff personnel.
17.
If applicable, layout/arrangement drawings of potential reactor coolant/recirculation pump lube oil system leakage points and associated lube oil collection systems.
18.
A listing of the SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration.
19.
Procedures/instructions that control the configuration of the reactor plant's fire protection program, features, and post-fire safe shutdown methodology and system design.
20.
A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.
21.
Procedures/instructions that govern the implementation of plant modifications, maintenance, and special operations, and their impact on fire protection.
22.
The three most recent fire protection QA audits and/or fire protection self-assessments.
23.
Recent QA surveillances of fire protection activities.
24.
A listing of open and closed fire protection condition reports (problem reports/NCRs/EARs/problem identification and resolution reports) for the past three years.
25.
Listing of plant fire protection licensing basis documents.
26.
A listing of the NFPA code versions committed to (NFPA codes of record).
27.
A listing of plant deviations from code commitments.
28.
Actual copies of Generic Letter 86-10 evaluations.