ML063260091

From kanterella
Jump to navigation Jump to search
Notification of Conduct of a Triennial Fire Protection Baseline Inspection
ML063260091
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 11/22/2006
From: Rogge J
Engineering Region 1 Branch 3
To: Ted Sullivan
Entergy Nuclear Operations
References
Download: ML063260091 (6)


Text

November 22, 2006 Mr. Theodore A. Sullivan Site Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, VT 05354

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Sullivan:

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 Vermont Yankee Nuclear Power Station in March 2007. The inspection team will be led by Keith Young from the NRC Region I office. The team will be composed of personnel from the NRC Region I. The inspection will be conducted in accordance with NRC inspection procedure 71111.05T, the NRCs baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

@ Information gathering visit - Week of February 26, 2007

@ Weeks of onsite inspection - March 12 - 16 and March 26 - 30, 2007 The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the station 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 Enclosure 1. The team leader will contact you with specific document requests prior to the information gathering visit.

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.

We request that during the onsite inspection week you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the Vermont Yankee Nuclear Power Station fire protection program, including post-fire safe shutdown

2 Mr. Theodore A. Sullivan 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 Vermont Yankee Nuclear Power Station 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 Keith Young, the team leader in the Region I Office at (610) 337-5293.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No.

50-271 License No.

DPR-28

Enclosure:

List of Reactor Fire Protection Program Supporting Documents

3 Mr. Theodore A. Sullivan cc w/encl:

M. R. Kansler, President, Entergy Nuclear Operations, Inc.

G. J. Taylor, Chief Executive Officer, Entergy Operations J. T. Herron, Senior Vice President and Chief Operating Officer C. Schwarz, Vice-President, Operations Support O. Limpias, Vice President, Engineering J. M. DeVincentis, Manager, Licensing, Vermont Yankee Nuclear Power Station Operating Experience Coordinator, Vermont Yankee Nuclear Power Station W. Maguire, General Manager, Plant Operations, Entergy Nuclear Operations, Inc.

N. Rademacher, Director NSA, Vermont Yankee Nuclear Power Station J. F. McCann, Director, Licensing C. D. Faison, Manager, Licensing M. J. Colomb, Director of Oversight, Entergy Nuclear Operations, Inc.

T. C. McCullough, Assistant General Counsel, Entergy Nuclear Operations, Inc.

J. H. Sniezek, PWR SRC Consultant M. D. Lyster, PWR SRC Consultant S. Lousteau, Treasury Department, Entergy Services, Inc.

D. O Dowd, Administrator, Radiological Health Section, DPHS, DHHS, State of New Hampshire Chief, Safety Unit, Office of the Attorney General, Commonwealth of Mass.

J. E. Silberg, Pillsbury, Winthrop, Shaw, Pittman LLP G. D. Bisbee, Esquire, Deputy Attorney General, Environmental Protection Bureau J. Block, Esquire J. P. Matteau, Executive Director, Windham Regional Commission D. Katz, Citizens Awareness Network (CAN)

R. Shadis, New England Coalition Staff G. Sachs, President/Staff Person, c/o Stopthesale J. Giarrusso, MEMA and Commonwealth of Massachusetts, SLO Designee State of New Hampshire, SLO Designee State of Vermont, SLO Designee

4 Mr. Theodore A. Sullivan Distribution w/encl:

(via E-mail)

S. Collins, RA M. Dapas, DRA R. Powell, DRP T. Walker, DRP A. R. Blough, DRS J. Rogge, DRS K. Young, DRS B. Sosa, RI OEDO R. Laufer, NRR J. Shea, PM, NRR J. Boska, Backup PM, NRR D. Pelton, DRP, Senior Resident Inspector A. Rancourt, DRP, Resident OA Region I Docket Room (with concurrences)

ROPreports@nrc.gov (All IRs)

DRS file SUNSI Review Complete: JFR (Reviewers Initials)

DOCUMENT NAME: C:\\FileNet\\ML063260091.wpd After declaring this document An Official Agency Record it will 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 KAYoung/KAY JFRogge/JFR DATE 11/20/06 11/21/06 OFFICE NAME DATE OFFICIAL RECORD COPY

ENCLOSURE 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 systems and 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 location of the post-fire emergency lighting units.

10.

Plant operating procedures which would be used for shutdown from the control room with a postulated fire occurring in any plant area outside the control room, and 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. (Last completed copy.)

12.

Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.

13.

A list of fire protection and post-fire safe shutdown related design change packages (including their associated 10 CFR 50.59 evaluations) 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 15.

Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.)

16.

Organization charts of site personnel down to the level of fire protection staff personnel.

17.

A listing of the SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration.

18.

A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.

19.

Procedures/instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire protection.

20.

The three most recent fire protection QA audits and/or fire protection self-assessments.

21.

Recent QA surveillances of fire protection activities.

22.

A listing of open fire protection and fire safe shutdown related condition reports.

23.

A listing of fire protection and fire safe shutdown condition reports closed in the past three years.

24.

Fire protection system health reports (last 2).

25.

Lesson Plans and related training information for licensed and non-licensed operators for post-fire safe shutdown (including alternative shutdown).