ML043090559
| ML043090559 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/04/2004 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-05-010 | |
| Download: ML043090559 (7) | |
See also: IR 05000260/2005010
Text
November 4, 2004
Tennessee Valley Authority
ATTN: Mr. K. W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT:
NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - SAFETY SYSTEM
DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC
INSPECTION REPORT 05000260/2005010 AND 05000296/2005010
Dear Mr. Singer:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a safety system design and performance capability inspection on the
operating Units 2 and 3 at your Browns Ferry Nuclear Plant during the weeks of January 10 and
January 24, 2005. A team of five inspectors will perform this inspection. The inspection team
will be led by Mr. R. Moore, a Senior Reactor Inspector from the NRC Region II Office. This
biennial inspection will be conducted in accordance with baseline inspection program
Attachment 71111.21, Safety System Design and Performance Capability.
This inspection will evaluate the design and capability of plant equipment which provides the
High Pressure Injection (HPI) function for design basis events. Procedures which direct the
mitigating actions for events requiring HPI will also be evaluated.
During a telephone conversation on November 1, 2004, Mr. R. Moore of my staff, and
Mr. J. Davenport of your staff, confirmed arrangements for an information gathering site visit
and the two-week onsite inspection. The schedule is as follows:
Information gathering visit: The week of December 13, 2004
Onsite inspection weeks: January 10 and January 24, 2005.
The purpose of the information gathering visit is to obtain information and documentation
outlined in the enclosure needed to support the inspection. Mr. R. Bernhard, a Region II Senior
Reactor Analyst, may accompany Mr. Moore during the information gathering visit to review
probabilistic risk assessment data and identify risk significant components which will be
examined during the inspection. Please contact Mr. Moore 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 inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space; specific documents requested to be made
available to the team in their office space; arrangements for site access, and the availability of
2
knowledgeable plant engineering and licensing personnel to serve as points of contact during
the inspection.
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. R. Moore at (404) 562-4642 or me
at (404) 562-4605.
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 Publically Available Records (PARS) component of NRCs 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).
Sincerely,
\\\\RA by Larry Mellen For\\\\
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-260, 50-296
Enclosure:
Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Operations
Tennessee Valley Authority
Electronic Mail Distribution
Michael J. Lorek, General Manager
Engineering and Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
Michael D. Skaggs
Site Vice President
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
cc w/encl contd - (See page 3)
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola, Manager
Nuclear Assurance and Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Kurt L. Krueger, Plant Manager
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
3
cc w/encl contd:
Fredrick C. Mashburn
Sr. Program Manager
Nuclear Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Timothy E. Abney, Manager
Licensing and Industry Affairs
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
State Health Officer
Alabama Dept. of Public Health
RSA Tower - Administration
Suite 1552
P. O. Box 303017
Montgomery, AL 36130-3017
Chairman
Limestone County Commission
310 West Washington Street
Athens, AL 35611
Jon R. Rupert, Vice President
Browns Ferry Unit 1 Restart
Browns Ferry Nuclear Plant
Tennessee Valley Authority
P. O. Box 2000
Decatur, AL 35609
Robert G. Jones, Restart Manager
Browns Ferry Unit 1 Restart
Browns Ferry Nuclear Plant
Tennessee Valley Authority
P. O. Box 2000
Decatur, AL 35609
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND PERFORMANCE
CAPABILITY INSPECTION
BROWNS FERRY HIGH PRESSURE INJECTION (HPI) FUNCTION
(Please provide the information electronically in searchable pdf files on CDROM. The
CDROM should be indexed and hyperlinked to facilitate ease of use. Information in
lists should contain enough information to be easily understood by someone who has a
knowledge of boiling water reactor technology.)
1.
Piping and instrumentation drawings for the following HPI systems: High Pressure
Coolant Injection (HPCI) system, Reactor Core Isolation Cooling (RCIC) system and
supporting systems.
2.
The normal operating procedures for the systems listed above. Include the procedures
which specify the normal valve alignment for these systems.
3.
Surveillance procedures used to ensure the operability of HPCI and RCIC equipment
required by your Technical Specifications.
4.
Procedures used for the operational testing of check valves in portions of the HPCI and
RCIC systems and supporting systems used during mitigation of the events requiring
HPI.
5.
Procedures for venting of HPCI and RCIC.
6.
Logic diagrams for RCIC and HPCI turbine start, shutdown. Logic diagrams for HPCI
mini-flow and full flow test line valves. Logic diagrams for suction swap over from
condensate source to suppression pool.
7.
Calibration and functional test procedures for instruments used for initiation or
termination of HPI, i.e. containment pressure, reactor pressure vessel level, RCIC flow
and pressure, HPCI flow and pressure and condenser header/CST level.
8.
Description of Loss of offsite power/Station blackout strategy.
9.
List of HPCI and RCIC equipment actuated during LOOP/SBO and design base events.
10.
A list of problem reports (PERs ?) and non routine work requests initiated since 2002
affecting the HPCI and RCIC, and support systems including their power supplies.
11.
Emergency Operating Instructions (EOIs) and supporting procedures, EOI basis
documents, step deviation document, writers guide, and users guide. Abnormal
Operating Procedures that would be used during a LOOP/SBO event or small break
LOCA.
Enclosure
2
Enclosure
12.
Calculations used to support the set points in Emergency Operating Procedures for the
HPI function.
13.
A list of engineering calculations applicable to HPCI, RCIC and support systems.
14.
A list of temporary modifications and operator workaround since 2001, related to HPCI,
RCIC and support systems.
15.
A list of operability determinations performed since 2001 related to HPCI, RCIC and
support systems.
16.
Deleted.
17.
System Health Reports and System Performance Trends for HPCI, RCIC, and support
systems going back two years.
18.
A copy of the Maintenance Rule program procedure and performance criteria for HPCI,
RCIC, and support systems. A list of plant systems currently monitored under
50.65(a)(1) and the performance goals. A list of Maintenance Rule functional failures
since 2002.
19.
Quality Assurance audits, self-assessments and third party assessments performed on
HPCI, RCIC, and support systems for 24 months. Quality Assurance audits, self-
assessments, and third party assessments performed on engineering and maintenance
department activities performed in the last 24 months.
20.
Operator training lesson plans, and job performance measures for the EOIs, EOI
support procedures, abnormal, and normal operating procedures that would be used to
mitigate events requiring the HPI function.
21.
Key electrical single line drawings of the intermediate and low voltage alternating current
(AC) and DC power systems for HPCI, RCIC, and support systems. (Paper copies (2)
are preferred for these)
22.
The electrical system load list(s) particularly DC loading for HPI equipment.
23.
A brief description of the mitigation strategy for the LOOP/SBO event and SBLOCA
event. This should include operator actions, equipment and power sources, as well as
indications and control circuits.
24.
A list of Operating Experience Program evaluations of industry, vendor, or NRC generic
issues for the past three years, related to HPCI, RCIC, and support systems equipment
or operation.
25.
A list of HPI related equipment and operator actions with a Risk Achievement Worth
(RAW) greater than 1.02.
3
Enclosure
26.
A list of PRA basic events which are important to the success of HPCI and RCIC, listed
in order of their importance to each systems functions success.
(Contact Rudy Bernhard, PRA Specialist, @ 404 562 4618 if you have questions on this
item)
27.
Design Basis Manual for major plant electrical, mechanical, and control systems.
28.
Plant Technical Specifications, Bases, and Technical Requirements Manual
29.
A current copy of the Updated Final Safety Analysis Report.
30.
System description, design base document (or equivalent) for HPCI and RCIC systems.
31.
A list of all permanent plant changes, design changes, set point changes, procedure
changes, equivalency evaluations, suitability analyses, calculations, and commercial
grade dedications related to HPI systems and equipment since 2002 .
32.
Plant procedures that provide the guidelines for the following programs: (1) Corrective
Action Program, (2) Program for the evaluation of changes, tests, and experiments
[50.59 Program], (3) Program for the incorporation of local and industry operating
experience into Browns Ferry programs and procedures, (4) the design control program
33.
A list of operations training packages which were required due to modifications related
to HPCI, RCIC, and support systems. if any.
34.
Copies of the most recent self-assessment(s) and audit(s) of the modifications process
and the 50.59 process.