ML071560434
| ML071560434 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/05/2007 |
| From: | Cain L NRC/RGN-II/DRS/EB1 |
| To: | Young D Florida Power Corp |
| References | |
| IR-07-006 | |
| Download: ML071560434 (6) | |
See also: IR 05000302/2007006
Text
June 5, 2007
Mr. Dale E. Young, Vice President
Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing &
Regulatory Programs
15760 West Power Line Street
Crystal River, FL 34428-6708
SUBJECT: NOTIFICATION OF CRYSTAL RIVER NUCLEAR PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
Dear Mr. Young:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection at your Crystal River Nuclear
Plant during the weeks of September 10, 2007, September 24-28, 2007, and October 1-5,
2007. The inspection team will be led by Mr. Robert Berryman, a Senior Reactor Inspector
from the NRC's Region II Office. This inspection will be conducted in accordance with the
baseline inspection procedure, Procedure 71111.21, Component Design Bases Inspection,
issued December 2, 2005.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and support proper system operation. The inspection will also include a review of
selected operator actions, operating experience, and modifications.
During a telephone conversation on May 31, 2007, Mr. Berryman confirmed with Mr. Dennis
Herrin of your staff, arrangements for an information gathering site visit and the three-week
onsite inspection. The schedule is as follows:
- Information gathering visit: Week of August 27-31, 2007.
- Onsite weeks: September 10-14, 2007, September 24-28, 2007, and October 1-
5, 2007.
The purpose of the information gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Walt Rodgers, a Region II Senior Reactor
Analyst, may accompany Mr. Berryman and the inspection team during the information
gathering visit to review probabilistic risk assessment data and identify risk significant
components which will be examined during the inspection.
FPC 2
The enclosure lists documents that will be needed prior to the information gathering visit.
Please contact Mr. Berryman prior to preparing copies of the materials listed in the enclosure.
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of
September 3, 2007; arrangements for site access; and the availability of knowledgeable plant
engineering and licensing personnel to serve as points of contact during the inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Berryman at (404) 562-4817 or me
at (404) 562-4876.
Sincerely,
/RA/
L. M. Cain, Acting Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-302
License No. DPR-72
Enclosure: Information Request for Crystal River Nuclear Plant Component Design Bases
Inspection
FPC 3
cc w/encl:
Daniel L. Roderick Chairman
Director Site Operations Board of County Commissioners
Crystal River Nuclear Plant (NA2C) Citrus County
Electronic Mail Distribution 110 N. Apopka Avenue
Inverness, FL 36250
Jon A. Franke
Plant General Manager Jim Mallay
Crystal River Nuclear Plant (NA2C) Framatome Technologies
Electronic Mail Distribution Electronic Mail Distribution
Phyllis Dixon
Manager Nuclear Assessment
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Michael J. Annacone
Engineering Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
R. Alexander Glenn
Associate General Counsel (MAC - BT15A)
Florida Power Corporation
Electronic Mail Distribution
Steven R. Carr
Associate General Counsel - Legal Dept.
Progress Energy Service Company, LLC
Electronic Mail Distribution
Attorney General
Department of Legal Affairs
The Capitol PL-01
Tallahassee, FL 32399-1050
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
_________________________
OFFICE RII:DRS RII:DRS RII:DRP
SIGNATURE /RA/ /RA/ /RA/
NAME R.Berryman L.M. Cain S. Ninh
DATE 6/5/2007 6/5/2007 6/5/2007 6/ /2007 6/ /2007 6/ /2007 6/ /2007
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists
should contain enough information to be easily understood to someone who has a knowledge
of pressurized water reactor technology.
1. From your most-recent probabilistic safety analysis (PSA) excluding external events
and fires:
a. Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA): one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance.
b. A list of the top 500 cutsets.
2. From your most-recent probabilistic safety analysis (PSA) including external events
and fires:
a. Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA): one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance.
b. A list of the top 500 cutsets..
3. Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide
copies of your human reliability worksheets for these items.
4. Any pre-existing evaluation or list of components and calculations with low design
margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator
close to design required output, heat exchangers close to rated design heat removal,
MOV risk-margin rankings, etc.).
5. A list of station applicability evaluations/reviews performed and documented in the
station corrective action program in the past two years for industry events, critical
equipment failures, and safety related equipment vulnerabilities [as communicated by
NRC generic communications, industry communications, 10 CFR part 21 notifications,
etc.]
6. A list of safety related SSC design modifications implemented within the last two years,
sorted by affected system.
7. This item deleted. Corrective action lists will be requested after the component sample
is determined.
8. A list of common-cause failure of components that have occurred at Crystal River and
have been identified within the last five years.
9. A list of operability evaluations completed within the last two years, sorted by associated
component or system.
5
Enclosure
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address.
11. List of equipment currently on the sites Station Equipment Reliability Issues List,
including a description of the reason(s) why each component is on that list and
summaries (if available) of your plans to address those reasons.
12. List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.
Enclosure