ML052590523
ML052590523 | |
Person / Time | |
---|---|
Site: | Fermi |
Issue date: | 09/15/2005 |
From: | Ann Marie Stone Division of Reactor Safety III |
To: | O'Conner W Detroit Edison |
References | |
IR-05-016 | |
Download: ML052590523 (9) | |
See also: IR 05000341/2005016
Text
September 15, 2005
Mr. William OConnor, Jr.
Vice President
Nuclear Generation
Detroit Edison Company
6400 North Dixie Highway
Newport, MI 48166
SUBJECT: FERMI POWER PLANT, UNIT 2 - INFORMATION REQUEST FOR AN NRC
BIENNIAL SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY
(SSDPC) BASELINE INSPECTION 05000341/2005016(DRS)
Dear Mr. OConnor:
In our letter dated August 31, 2005, which announced our plans to begin a biennial Safety
System Design and Performance Capability (SSDPC) baseline inspection at the Fermi 2 Power
Plant, we stated that the reactor core isolation cooling and the emergency diesel generator
systems were selected for review. However, in the enclosure, we did not state the reactor core
isolation cooling system was selected. This was an error.
Enclosed is a revised request for documents needed for the inspection. As stated in our
August 31, 2005 letter, these documents have been divided into three groups. The first group
of information should be available to the NRC Region III office no later than October 27, 2005
and except as noted, should be provided electronically to Mr. Al Walker at (haw@nrc.gov). The
second group of requested documents should be made available on-site for the inspectors by
November 14, 2005. The third group lists information that will aid the inspection team in
tracking issues identified as a result of the inspection. It is important that all of these
documents are up to date and complete in order to minimize the number of additional
documents requested during the preparation and/or the onsite portions of 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
W. OConnor -2-
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).
Sincerely,
/RA/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-341
License No. NPF-43
Enclosure: Safety System Design and Performance Capability
Inspection (SSDPC) Document Request
cc w/encl: N. Peterson, Manager, Nuclear Licensing
D. Pettinari, Legal Department
Compliance Supervisor
G. White, Michigan Public Service Commission
L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division
Monroe County, Emergency Management Division
Planning Manager, Emergency Management Division
MI Department of State Police
W. OConnor -2-
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).
Sincerely,
/RA/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-341
License No. NPF-43
Enclosure: Safety System Design and Performance Capability
Inspection (SSDPC) Document Request
cc w/encl: N. Peterson, Manager, Nuclear Licensing
D. Pettinari, Legal Department
Compliance Supervisor
G. White, Michigan Public Service Commission
L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division
Monroe County, Emergency Management Division
Planning Manager, Emergency Management Division
MI Department of State Police
DOCUMENT NAME:ML052590523.wpd
X Publicly Available G Non-Publicly Available G Sensitive X Non-Sensitive
To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE RIII RIII RIII
NAME HWalker:jb EDuncan AMStone
DATE 9/15/05 9/15/05 9/15/05
OFFICIAL RECORD COPY
W.OConnor -3-
ADAMS Distribution:
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SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION (SSDPC)
DOCUMENT REQUEST
Inspection Report: 05000341/2005016(DRS)
Inspection Dates: November 14 through December 2, 2005
Inspection Procedure: IP 71111.21, Safety System Design and Performance Capability
Lead Inspector: Hershell Walker, Team Leader
(630) 829-9728
I. Information Requested for In-Office Preparation Week
The following information is requested by October 27, 2005, or sooner, to facilitate the
selection of specific items that will be reviewed during the on-site inspection week. The
team will select specific items from the information requested below and submit a list to
your staff by November 8, 2005. We request that the specific items selected from the
lists be available and ready for review on the first day of inspection. If you have any
questions regarding this information, please call the team leader as soon as possible.
All information should be sent, electronically if at all possible, to (haw@nrc.gov).
The items requested below apply only to the selected systems:
Reactor Core Isolation Cooling (RCIC) system and
Emergency Diesel Generators (EDGs) and associated support systems
(e.g., EDG Air Start, EDG Lube Oil, EDG Fuel Oil, EDG Jacket Water Cooling,
and EDG Room Cooling, EDG Service Water);
(1) one copy of the systems description, design basis documents, related training
manuals and system health reports;
(2) one copy of the normal and abnormal operating procedures;
(3) five half-size (18" x 24") copies of the piping and instrument drawings (P&IDs)
[paper copies];
(4) two half-size (18" x 24") copies of the electrical schematics, single-line and key
diagrams [paper copies];
(5) name and phone numbers of the technical contact, a regulatory contact, and the
design and system engineer(s);
(6) current management and engineering organizational chart; and
(7) list of analyses that either support or take credit for operation of the systems.
For each analysis, besides the number and title, include the purpose of the
Enclosure
calculation, the date, a technical contact, and the current status (active,
superceded, historical). Clarify any abbreviations or acronyms and give word
titles for any numbers (e.g., residual heat removal inner containment isolation
valve, rather than RH-2301-45B).
In addition to the above, specifically identify (by number) the calculations that address
each of the following areas. If a calculation cannot be identified for a particular area,
please provide an explanation of why a calculation is not necessary:
- breaker and fuse coordination calculations;
- diesel loading calculations;
- instrument uncertainty calculations;
- room temperature environmental qualification calculations for major
equipment;
- relay setting calculations;
- setpoint calculations for all technical specification or emergency
operation procedure equipment;
- time delay calculations (for any component incorporating time delay
features);
- undervoltage and degraded voltage calculations;
- voltage drop calculations for all major electrical components (motors,
MOVs);
- check valve leakage criteria calculations;
- design basis (flow rates, levels, pressures, temperatures)
confirmation calculations (including NSSS calculations);
- heat exchanger calculations;
- NPSH and total dynamic head calculations;
- operability determination support calculations;
- pressure transient/water hammer evaluations;
- pump minimum recirculation flow calculations;
- relief valve sizing calculations;
- tank over-pressurization calculations; and
- tank sizing calculations.
(8) List of all major modifications or set-point changes made to the selected systems
since pre-operational testing. Major changes are those that significantly affected
the way the system operated, for example, replacement of major components,
modification to electrical control logic, etc. Please include the number and title,
the modification purpose (description), the date, the status (whether the
calculation is active, canceled, superceded, or under revision) and a technical
contact. Spell out abbreviations, or acronyms and give word titles for any
numbers. Note if any of the modifications required prior NRC approval. One
way to provide this information is by providing the first sheet of the modification
(not the cover letter);
(9) list of open temporary modifications, if any;
(10) list of the selected systems electrical equipment/components that have been
removed from the licensees EQ Program, if any;
Enclosure
(11) list of condition reports (corrective action documents) involving the RCIC system
or EDG and its support systems that are in one of the following categories. For
each condition report, besides the number and title, clearly designate the status
(open/closed), the importance ranking, the date initiated, the date closed (if
applicable), the status of corrective actions, and a technical contact. (Note: it is
not necessary to provide a separate list for each category.)
- any condition report initiated more than 2 years prior to the inspection
that is still open;
- any condition report (open or closed) initiated in the last 2 years that
required an apparent or root cause analysis
(i.e., Category 1 or 2 condition reports);
- any condition report (open or closed) initiated in the last 2 years that
required an operability determination (include determination); and
- any condition report (open or closed) initiated in the last 2 years that
related to problems with the quality of engineering (not system
specific).
(12) the corrective maintenance history of major components for the last 2 years;
(13) list of operability evaluations as far back as retrievable. Include both those
currently relied upon and those that were previously relied upon for operability;
and
(14) list of Engineering Related Operator Workarounds.
II. Information Requested to be Available on First Day of Inspection (November 14,
2005)
We request that the following information be available to the team once they arrive
on-site. The team will select the specific documents that will be reviewed for items
(1) through (5) by November 8, 2005. Some documents, such as the Updated Final
Safety Analysis Report or the Technical Specification, do not need to be solely available
to the team (i.e., they can be located in a reference library) as long as the team has
ready access to them. However, they should be located prior to the inspection team
arriving on-site such that if the team requests any of these documents they are available
within a short time (i.e., less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />):
(1) copies of the selected calculations indicated by subject area in Item I.7,
excluding data files. Please review the calculations and also provide copies of
referenced material (such as drawings, engineering requests, vendor letters);
(2) copies of the selected MAJOR design changes, modifications, and set-point
changes as indicated in Item I.8. For each modification, as a minimum provide
the purpose, the 10 CFR 50.59 evaluation or screening, and the completed
post-modification test;
(3) copies of the selected condition reports (corrective action documents) indicated
Enclosure
in Item I.11, including any associated root/apparent cause analyses and
(4) copies of selected operability evaluations indicated in Item I.13 and plans for
restoring operability, if applicable;
(5) copies of selected work-around evaluations indicated in Item I.14 and plans for
resolution;
(6) copies of any open temporary modifications;
(7) an Index of the surveillances for ALL Technical Specification equipment
completed during the last 2 years;
(8) list of all maintenance, surveillance, and annunciator response procedures
related to the systems. Include name as well as number. For the surveillance
procedures, provide a cross-reference which shows how each technical
specification requirement is being met;
(9) one copy of each major equipment drawing (valves, pumps, tanks, strainers),
including pump head curves (1/2 size, 18" x 24");
(10) copies of isometric drawings for major flow paths (1/2 size);
(11) copies of elementary diagrams (1/2 size);
(12) index of wiring diagrams (1/2 size);
(13) copies of loop drawings (1/2 size);
(14) copies of instrumentation and control logic drawings (1/2 size);
(15) maintenance history of major components for the last 2 years;
(16) trend data on the EDG fuel oil transfer pumps and RCIC pump performance
(over last 3 years) including inservice testing, other vibration monitoring, oil
sample results, etc., as applicable;
(17) inservice testing valve tables for RCIC and EDG and support systems;
(18) inservice testing basis document for RCIC and EDG and support systems (if
available);
(19) a copy of any self-assessments and associated corrective action documents
generated in preparation for the inspection;
(20) one copy of the current plant organization charts; and
Enclosure
(21) reference materials (make available if needed):
- equipment qualification binders;
- general set of plant drawings;
- IPE/PRA report;
- pre-operational tests, including documents showing resolution of
deficiencies;
- procurement documents for major components in each system (verify
retrievable);
- relevant operating experience information (such as vendor letters or
utility experience);
- system procedures;
- Technical Specifications;
- Technical Data Book (if applicable);
- vendor manuals.
III. Information Requested to be provided throughout the inspection
(1) copies of any corrective action documents generated as a result of the teams
questions or queries during this inspection; and
(2) copies of the list of questions submitted by the team members and the
status/resolution of the information requested (provide daily during the inspection
to each team member).
If you have questions regarding the information requested, please contact the team leader.
Enclosure