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{{#Wiki_filter:January 30, 2008 | {{#Wiki_filter:January 30, 2008 | ||
P. O. Box 97, 10 Center Road, A-PY-290 Perry, OH 44081-0097 | |||
SUBJECT: PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION | Mr. Barry S. Allen | ||
Site Vice President | |||
FirstEnergy Nuclear Operating Company | |||
Perry Nuclear Power Plant | |||
P. O. Box 97, 10 Center Road, A-PY-290 | |||
Perry, OH 44081-0097 | |||
SUBJECT: | |||
PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN | |||
NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION | |||
(CDBI) 05000440/2008006(DRS) | (CDBI) 05000440/2008006(DRS) | ||
The inspection will include three weeks on-site, including the information gathering during the first on-site week. The inspection team will consist of six NRC inspectors, of which five will focus on engineering and one on operations. The current inspection schedule is as follows: | Dear Mr. Allen: | ||
* On-site weeks: May 5, 2008, through May 9, 2008; | |||
On May 5, 2008, the NRC will begin a triennial baseline Component Design Bases Inspection | |||
(CDBI) at the Perry Nuclear Power Plant. A team of six inspectors will perform this | |||
3-week inspection. This inspection will be performed in accordance with NRC Baseline | |||
Inspection Procedure (IP) 71111.21. | |||
The CDBI inspection focuses on components that have high risk and low design margins. The | |||
components to be reviewed during this baseline inspection will be identified during an in-office | |||
preparation week prior to the first week of the on-site inspection. In addition, a number of risk | |||
significant operator actions and operating experience issues, associated with the component | |||
samples, will also be selected for review. | |||
The inspection will include three weeks on-site, including the information gathering during the | |||
first on-site week. The inspection team will consist of six NRC inspectors, of which five will | |||
focus on engineering and one on operations. The current inspection schedule is as follows: | |||
* | |||
On-site weeks: May 5, 2008, through May 9, 2008; | |||
May 19, 2008, through May 23, 2008; and | |||
June 2, 2008, through June 6, 2008. | |||
The team will be preparing for the inspection, mainly during the week of April 28, 2008, as | |||
discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the | |||
inspection team during the week of May 5, 2008, to review probabilistic risk assessment data, | |||
and assist in identifying risk significant components, which will be reviewed during the | |||
inspection. | |||
Experience with previous baseline design inspections of similar depth and length has shown | |||
that these type of inspections are extremely resource intensive, both for the NRC inspectors and | |||
the licensee staff. In order to minimize the inspection impact on the site and to ensure a | |||
productive inspection for both parties, we have enclosed a request for information needed for | |||
the inspection. | |||
B. Allen | |||
-2- | |||
It is important that all of these documents are up to date and complete in order to minimize the | |||
B. Allen -2- | number of additional documents requested during the preparation and/or the on-site portions of | ||
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 on-site portions of | the inspection. Insofar as possible, this information should be provided electronically to the lead | ||
the inspection. Insofar as possible, this information should be provided electronically to the lead inspector. The information request has been divided into three groups: | inspector. The information request has been divided into three groups: | ||
* The first group lists information necessary for our initial inspection scoping activities. This information should be provided to the lead inspector no later than March 24, 2008. By April 11, 2008, the lead inspector will communicate the initial selected set of approximately 30 high risk components. | |||
* The second group of documents requested are those items needed to support our in-office preparation activities. This set of documents, including the calculations associated with the initial selected components, should be provided to the lead inspector at the Regional Office no later than April 23, 2008. During the in-office preparation activities, the team may identify | * | ||
The first group lists information necessary for our initial inspection scoping activities. | |||
This information should be provided to the lead inspector no later than March 24, 2008. By | |||
April 11, 2008, the lead inspector will communicate the initial selected set of approximately | |||
30 high risk components. | |||
* | |||
The second group of documents requested are those items needed to support our in-office | |||
preparation activities. This set of documents, including the calculations associated with the | |||
initial selected components, should be provided to the lead inspector at the Regional Office | |||
no later than April 23, 2008. During the in-office preparation activities, the team may identify | |||
additional information needed to support the inspection. | additional information needed to support the inspection. | ||
* The last group includes the additional information above as well as plant specific reference material. This information should be available to the team at Perry on May 5, 2008. It is also requested that corrective action documents and/or questions developed during the | |||
* | |||
The last group includes the additional information above as well as plant specific reference | |||
material. This information should be available to the team at Perry on May 5, 2008. It is | |||
also requested that corrective action documents and/or questions developed during the | |||
inspection be provided to the lead inspector as the documents are generated. | inspection be provided to the lead inspector as the documents are generated. | ||
The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our licensing contact for this inspection is Mr. Kenneth Russell of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the | |||
The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our licensing | |||
contact for this inspection is Mr. Kenneth Russell of your organization. If there are any | |||
questions about the inspection or the material requested in the enclosure, please contact the | |||
lead inspector at (630) 829-9727 or via e-mail at sns2@nrc.gov. | lead inspector at (630) 829-9727 or via e-mail at sns2@nrc.gov. | ||
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), 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 | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its | ||
Docket No. 50-440 | 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), 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. 50-440 | |||
License No. NPF-58 | License No. NPF-58 | ||
Enclosure: Component Design Bases Inspection (CDBI) Document Request | |||
DISTRIBUTION | Enclosure: | ||
Component Design Bases Inspection (CDBI) Document Request | |||
DISTRIBUTION | |||
See next page | |||
B. Allen | |||
-2- | |||
It is important that all of these documents are up to date and complete in order to minimize the number of | It is important that all of these documents are up to date and complete in order to minimize the number of | ||
| Line 57: | Line 133: | ||
Insofar as possible, this information should be provided electronically to the lead inspector. The | Insofar as possible, this information should be provided electronically to the lead inspector. The | ||
information request has been divided into three groups: | information request has been divided into three groups: | ||
* The first group lists information necessary for our initial inspection scoping activities. This information should be provided to the lead inspector no later than March 24, 2008. By April 11, 2008, the lead | |||
* | |||
The first group lists information necessary for our initial inspection scoping activities. This information | |||
should be provided to the lead inspector no later than March 24, 2008. By April 11, 2008, the lead | |||
inspector will communicate the initial selected set of approximately 30 high risk components. | inspector will communicate the initial selected set of approximately 30 high risk components. | ||
* The second group of documents requested are those items needed to support our in-office preparation activities. This set of documents, including the calculations associated with the initial | |||
* | |||
The second group of documents requested are those items needed to support our in-office | |||
preparation activities. This set of documents, including the calculations associated with the initial | |||
selected components, should be provided to the lead inspector at the Regional Office no later than | selected components, should be provided to the lead inspector at the Regional Office no later than | ||
April 23, 2008. During the in-office preparation activities, the team may identify additional information | April 23, 2008. During the in-office preparation activities, the team may identify additional information | ||
needed to support the inspection. | needed to support the inspection. | ||
* The last group includes the additional information above as well as plant specific reference material. This information should be available to the team at Perry on May 5, 2008. It is also requested that | |||
* | |||
The last group includes the additional information above as well as plant specific reference material. | |||
This information should be available to the team at Perry on May 5, 2008. It is also requested that | |||
corrective action documents and/or questions developed during the inspection be provided to the lead | corrective action documents and/or questions developed during the inspection be provided to the lead | ||
inspector as the documents are generated. | inspector as the documents are generated. | ||
The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our licensing contact for this inspection is Mr. Kenneth Russell of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9727 | The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our licensing contact for | ||
this inspection is Mr. Kenneth Russell of your organization. If there are any questions about the | |||
inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9727 | |||
or via e-mail at sns2@nrc.gov. | or via e-mail at sns2@nrc.gov. | ||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure | 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | 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), accessible from the | |||
NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
/RA/ | |||
Sincerely, | |||
/RA/ | |||
Ann Marie Stone, Chief | Ann Marie Stone, Chief | ||
Engineering Branch 2 | Engineering Branch 2 | ||
Division of Reactor Safety | Division of Reactor Safety | ||
Docket No. 50-440 License No. NPF-58 | |||
Docket No. 50-440 | |||
License No. NPF-58 | |||
Enclosure: | |||
Component Design Bases Inspection (CDBI) Document Request | |||
DISTRIBUTION | |||
See next page | |||
G:\\DRS\\Work in Progress\\Ltr 01 08 Perry Request for Information SNS.doc | |||
Publicly Available | |||
Non-Publicly Available | |||
Sensitive | |||
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 | |||
RIII | |||
NAME: | |||
SSheldon: ls | |||
AMStone | |||
DATE: | |||
01/28/08 | |||
01/30/08 | |||
OFFICIAL RECORD COPY | |||
Letter to Mr. Barry S. Allen from Ms. A M. Stone dated January , 2008. | |||
SUBJECT: | |||
PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN | |||
NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION | |||
(CDBI) 05000440/2008006(DRS) | |||
cc w/encl: | |||
J. Hagan, President and Chief Nuclear Officer - FENOC | |||
J. Lash, Senior Vice President of Operations and | |||
Chief Operating Officer - FENOC | |||
D. Pace, Senior Vice President, Fleet Engineering - FENOC | |||
J. Rinckel, Vice President, Fleet Oversight - FENOC | |||
Director, Fleet Regulatory Affairs - FENOC | |||
Manager, Fleet Licensing - FENOC | |||
Manager, Site Regulatory Compliance - FENOC | |||
D. Jenkins, Attorney, FirstEnergy Corp. | |||
Public Utilities Commission of Ohio | |||
Ohio State Liaison Officer | |||
R. Owen, Ohio Department of Health | |||
Letter to Mr. Barry S. Allen from Ms. A M. Stone dated January , 2008. | |||
SUBJECT: | |||
PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN | |||
NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION | |||
(CDBI) 05000440/2008006(DRS) | |||
cc w/encl: | |||
J. Hagan, President and Chief Nuclear Officer - FENOC | |||
J. Lash, Senior Vice President of Operations and | |||
Chief Operating Officer - FENOC | |||
D. Pace, Senior Vice President, Fleet Engineering - FENOC | |||
J. Rinckel, Vice President, Fleet Oversight - FENOC | |||
Director, Fleet Regulatory Affairs - FENOC | |||
Manager, Fleet Licensing - FENOC | |||
Manager, Site Regulatory Compliance - FENOC | |||
D. Jenkins, Attorney, FirstEnergy Corp. | |||
Public Utilities Commission of Ohio | |||
Ohio State Liaison Officer | |||
R. Owen, Ohio Department of Health | |||
DISTRIBUTION: | |||
RAG1 | |||
TJW2 | |||
TEB | |||
RidsNrrDirslpab | |||
JLC1 | JLC1 | ||
GEG KGO RML2 SRI Perry DRPIII | GEG | ||
DRSIII PLB1 TXN ROPreports@nrc.gov | KGO | ||
RML2 | |||
SRI Perry | |||
DRPIII | |||
DRSIII | |||
PLB1 | |||
TXN | |||
ROPreports@nrc.gov | |||
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT | INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT | ||
Inspection Dates: May 5, 2008, through May 9, 2008; | COMPONENT DESING BASES INSPECTION (CDBI) | ||
Enclosure | |||
1 | |||
Inspection Report: | |||
05000440/2008006(DRS) | |||
Inspection Dates: | |||
May 5, 2008, through May 9, 2008; | |||
May 19, 2008, through May 23, 2008; and | |||
June 2, 2008, through June 6, 2008. | |||
Inspection Procedure: | |||
IP 71111.21 Component Design Bases Inspection | |||
Lead Inspector: | |||
Stuart Sheldon, Lead Inspector | |||
(630) 829-9727 | |||
sns2@nrc.gov | |||
Inspection | I. | ||
Information Requested Prior to the On-site Information Gathering/Inspection Week | |||
The following information is requested by March 24, 2008, or sooner, to facilitate | |||
inspection preparation. If you have any questions regarding this information, please call | |||
the team leader as soon as possible. (Please provide the information electronically in | |||
inspection preparation. If you have any questions regarding this information, please call the team leader as soon as possible. (Please provide the information electronically in | pdf files, Excel, or other searchable formats, preferably on CDROM. The CDROM | ||
should contain descriptive names, and be indexed and hyperlinked to facilitate ease of | |||
use. Information in lists should contain enough information to be easily understood by | |||
someone who has knowledge of boiling water reactor technology). | someone who has knowledge of boiling water reactor technology). | ||
1. Risk ranking of top 150 components from your site specific probabilistic safety analysis (PSA) sorted by Risk Achievement Worth (RAW). Include values for Birnbaum Importance, Risk Reduction Worth (RRW), and Fussell-Veseley (FV) | |||
1. | |||
Risk ranking of top 150 components from your site specific probabilistic safety | |||
analysis (PSA) sorted by Risk Achievement Worth (RAW). Include values for | |||
Birnbaum Importance, Risk Reduction Worth (RRW), and Fussell-Veseley (FV) | |||
(as applicable). | (as applicable). | ||
2. Provide a list of the top 200 cut-sets from your PSA. | |||
3. Risk ranking of operator actions from your site specific PSA sorted by RAW. | 2. | ||
Provide copies of your human reliability worksheets for these items. | Provide a list of the top 200 cut-sets from your PSA. | ||
4. If you have an External Events or Fire PSA Model, provide the information requested in Items 1 and 2 for external events and fire. Provide narrative description of each coded event (including fire, flood zone description). | |||
5. Any pre-existing evaluation or list of components and associated 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 etc.). | 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. | |||
If you have an External Events or Fire PSA Model, provide the information | |||
requested in Items 1 and 2 for external events and fire. Provide narrative | |||
description of each coded event (including fire, flood zone description). | |||
5. | |||
Any pre-existing evaluation or list of components and associated 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 etc.). | |||
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT | |||
COMPONENT DESING BASES INSPECTION (CDBI) | |||
Enclosure | |||
2 | |||
6. | |||
List of available design (setup) margins for valves in the motor-operated valve | |||
(MOV) and air-operated valve (AOV) programs. | |||
7. | |||
List of high risk Maintenance Rule systems/components based on engineering or | |||
expert panel judgment. | |||
8. | |||
Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) | |||
category. | |||
9. | |||
Site top ten issues list (if applicable). | |||
10. | |||
A list of operating experience evaluations for the last 3 years. | |||
11. | |||
Information of any common cause failure of components experienced in the last | |||
5 years at your facility. | |||
12. | |||
List of Root Cause Evaluations associated with component failures or design | |||
issues initiated/completed in the last 5 years. | |||
13. | |||
Current management and engineering organizational chart. | |||
14. | |||
Electronic copies of Updated Final Safety Analysis Report, Technical | |||
Specifications, Technical Specifications Bases, and Technical Requirements | |||
Manual. | |||
II. | |||
Information requested (for the approx. 30 selected components) to be available by | |||
April 23, 2008, (will be reviewed by the team in the Regional office during the week | |||
of April 28, 2008). This information should be separated for each selected | |||
component, especially if provided electronically (e.g., folder with component | |||
name that includes calculations, condition reports, maintenance history, etc). | |||
1. | |||
List of condition reports (corrective action documents) associated with each of | |||
the selected components for the last 4 years. | |||
2. | |||
The corrective maintenance history associated with each of the selected | |||
components for the last 4 years. | |||
3. | |||
Copies of calculations associated with each of the selected components (if not | |||
previously provided), excluding data files. Please review the calculations and | |||
also provide copies of referenced material (such as drawings, engineering | |||
requests, and vendor letters). | |||
4. | |||
System Health Reports, System Descriptions, and/or Design Basis Documents | |||
that are associated with each of the selected components. | |||
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT | INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT | ||
COMPONENT | |||
COMPONENT DESIGN BASES INSPECTION (CDBI) | |||
Enclosure | |||
3 | |||
5. | |||
A list of modifications associated with each of the selected components. | |||
6. | |||
Copies of operability evaluations associated with each of the selected | |||
components and plans for restoring operability, if applicable. | |||
7. | |||
Copies of selected operator work-around evaluations associated with each of the | |||
12. Provide list of PRA assumptions regarding operator actions and the associated procedures. III. Additional Information to be provided on May 5, 2008 on-site (for final 15 - 20 selected components) | |||
selected components and plans for resolution, if applicable. | |||
8. | |||
Copies of any open temporary modifications associated with each of the selected | |||
components, if applicable. | |||
4* IPE/PRA report; | 9. | ||
* Procurement documents for components selected (verify retrievable); | Trend data on the selected electrical/mechanical components performance for | ||
* Plant procedures (normal, abnormal, emergency, surveillance, etc.); and | last 3 years (For example, pumps performance including in-service testing, other | ||
* Vendor manuals. | vibration monitoring, oil sample results, etc., as applicable). | ||
If you have questions regarding the information requested, please contact the lead inspector. | 10. | ||
A copy of any internal/external self-assessments and associated corrective | |||
action documents generated in preparation for the inspection. | |||
11. | |||
A copy of engineering/operations related audits completed in the last 2 years. | |||
12. | |||
Provide list of PRA assumptions regarding operator actions and the associated | |||
procedures. | |||
III. | |||
Additional Information to be provided on May 5, 2008 on-site (for final 15 - 20 | |||
selected components) | |||
During the in-office preparation activities, the team will be making final selections and | |||
may identify additional information needed to support the inspection. The lead inspector | |||
will provide a list of the additional information needed during the week of April 28, 2008. | |||
IV. | |||
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. | |||
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). | |||
3. | |||
One complete set of P&IDs and one line electrical drawings (paper copies). | |||
4. | |||
Reference materials. (make available if needed during all on-site weeks): | |||
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT | |||
COMPONENT DESIGN BASES INSPECTION (CDBI) | |||
Enclosure | |||
4 | |||
* | |||
IPE/PRA report; | |||
* | |||
Procurement documents for components selected (verify retrievable); | |||
* | |||
Plant procedures (normal, abnormal, emergency, surveillance, etc.); and | |||
* | |||
Vendor manuals. | |||
If you have questions regarding the information requested, please contact the lead inspector. | |||
}} | }} | ||
Latest revision as of 18:27, 14 January 2025
| ML080310280 | |
| Person / Time | |
|---|---|
| Site: | Perry |
| Issue date: | 01/30/2008 |
| From: | Ann Marie Stone NRC/RGN-III/DRS/EB2 |
| To: | Allen B FirstEnergy Nuclear Operating Co |
| References | |
| Download: ML080310280 (9) | |
See also: IR 05000440/2008006
Text
January 30, 2008
Mr. Barry S. Allen
Site Vice President
FirstEnergy Nuclear Operating Company
Perry Nuclear Power Plant
P. O. Box 97, 10 Center Road, A-PY-290
Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN
NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
Dear Mr. Allen:
On May 5, 2008, the NRC will begin a triennial baseline Component Design Bases Inspection
(CDBI) at the Perry Nuclear Power Plant. A team of six inspectors will perform this
3-week inspection. This inspection will be performed in accordance with NRC Baseline
Inspection Procedure (IP) 71111.21.
The CDBI inspection focuses on components that have high risk and low design margins. The
components to be reviewed during this baseline inspection will be identified during an in-office
preparation week prior to the first week of the on-site inspection. In addition, a number of risk
significant operator actions and operating experience issues, associated with the component
samples, will also be selected for review.
The inspection will include three weeks on-site, including the information gathering during the
first on-site week. The inspection team will consist of six NRC inspectors, of which five will
focus on engineering and one on operations. The current inspection schedule is as follows:
On-site weeks: May 5, 2008, through May 9, 2008;
May 19, 2008, through May 23, 2008; and
June 2, 2008, through June 6, 2008.
The team will be preparing for the inspection, mainly during the week of April 28, 2008, as
discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the
inspection team during the week of May 5, 2008, to review probabilistic risk assessment data,
and assist in identifying risk significant components, which will be reviewed during the
inspection.
Experience with previous baseline design inspections of similar depth and length has shown
that these type of inspections are extremely resource intensive, both for the NRC inspectors and
the licensee staff. In order to minimize the inspection impact on the site and to ensure a
productive inspection for both parties, we have enclosed a request for information needed for
the inspection.
B. Allen
-2-
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 on-site portions of
the inspection. Insofar as possible, this information should be provided electronically to the lead
inspector. The information request has been divided into three groups:
The first group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector no later than March 24, 2008. By
April 11, 2008, the lead inspector will communicate the initial selected set of approximately
30 high risk components.
The second group of documents requested are those items needed to support our in-office
preparation activities. This set of documents, including the calculations associated with the
initial selected components, should be provided to the lead inspector at the Regional Office
no later than April 23, 2008. During the in-office preparation activities, the team may identify
additional information needed to support the inspection.
The last group includes the additional information above as well as plant specific reference
material. This information should be available to the team at Perry on May 5, 2008. It is
also requested that corrective action documents and/or questions developed during the
inspection be provided to the lead inspector as the documents are generated.
The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our licensing
contact for this inspection is Mr. Kenneth Russell of your organization. If there are any
questions about the inspection or the material requested in the enclosure, please contact the
lead inspector at (630) 829-9727 or via e-mail at sns2@nrc.gov.
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), 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. 50-440
License No. NPF-58
Enclosure:
Component Design Bases Inspection (CDBI) Document Request
DISTRIBUTION
See next page
B. Allen
-2-
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 on-site portions of the inspection.
Insofar as possible, this information should be provided electronically to the lead inspector. The
information request has been divided into three groups:
The first group lists information necessary for our initial inspection scoping activities. This information
should be provided to the lead inspector no later than March 24, 2008. By April 11, 2008, the lead
inspector will communicate the initial selected set of approximately 30 high risk components.
The second group of documents requested are those items needed to support our in-office
preparation activities. This set of documents, including the calculations associated with the initial
selected components, should be provided to the lead inspector at the Regional Office no later than
April 23, 2008. During the in-office preparation activities, the team may identify additional information
needed to support the inspection.
The last group includes the additional information above as well as plant specific reference material.
This information should be available to the team at Perry on May 5, 2008. It is also requested that
corrective action documents and/or questions developed during the inspection be provided to the lead
inspector as the documents are generated.
The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our licensing contact for
this inspection is Mr. Kenneth Russell of your organization. If there are any questions about the
inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9727
or via e-mail at sns2@nrc.gov.
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), 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. 50-440
License No. NPF-58
Enclosure:
Component Design Bases Inspection (CDBI) Document Request
DISTRIBUTION
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G:\\DRS\\Work in Progress\\Ltr 01 08 Perry Request for Information SNS.doc
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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
RIII
NAME:
SSheldon: ls
AMStone
DATE:
01/28/08
01/30/08
OFFICIAL RECORD COPY
Letter to Mr. Barry S. Allen from Ms. A M. Stone dated January , 2008.
SUBJECT:
PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN
NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
cc w/encl:
J. Hagan, President and Chief Nuclear Officer - FENOC
J. Lash, Senior Vice President of Operations and
Chief Operating Officer - FENOC
D. Pace, Senior Vice President, Fleet Engineering - FENOC
J. Rinckel, Vice President, Fleet Oversight - FENOC
Director, Fleet Regulatory Affairs - FENOC
Manager, Fleet Licensing - FENOC
Manager, Site Regulatory Compliance - FENOC
D. Jenkins, Attorney, FirstEnergy Corp.
Public Utilities Commission of Ohio
Ohio State Liaison Officer
R. Owen, Ohio Department of Health
Letter to Mr. Barry S. Allen from Ms. A M. Stone dated January , 2008.
SUBJECT:
PERRY NUCLEAR POWER PLANT REQUEST FOR INFORMATION FOR AN
NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
cc w/encl:
J. Hagan, President and Chief Nuclear Officer - FENOC
J. Lash, Senior Vice President of Operations and
Chief Operating Officer - FENOC
D. Pace, Senior Vice President, Fleet Engineering - FENOC
J. Rinckel, Vice President, Fleet Oversight - FENOC
Director, Fleet Regulatory Affairs - FENOC
Manager, Fleet Licensing - FENOC
Manager, Site Regulatory Compliance - FENOC
D. Jenkins, Attorney, FirstEnergy Corp.
Public Utilities Commission of Ohio
Ohio State Liaison Officer
R. Owen, Ohio Department of Health
DISTRIBUTION:
RAG1
TJW2
TEB
RidsNrrDirslpab
JLC1
GEG
KGO
RML2
SRI Perry
DRPIII
DRSIII
PLB1
TXN
ROPreports@nrc.gov
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESING BASES INSPECTION (CDBI)
Enclosure
1
Inspection Report: 05000440/2008006(DRS)
Inspection Dates:
May 5, 2008, through May 9, 2008;
May 19, 2008, through May 23, 2008; and
June 2, 2008, through June 6, 2008.
Inspection Procedure:
IP 71111.21 Component Design Bases Inspection
Lead Inspector:
Stuart Sheldon, Lead Inspector
(630) 829-9727
sns2@nrc.gov
I.
Information Requested Prior to the On-site Information Gathering/Inspection Week
The following information is requested by March 24, 2008, or sooner, to facilitate
inspection preparation. If you have any questions regarding this information, please call
the team leader as soon as possible. (Please provide the information electronically in
pdf files, Excel, or other searchable formats, preferably on CDROM. The CDROM
should contain descriptive names, and be indexed and hyperlinked to facilitate ease of
use. Information in lists should contain enough information to be easily understood by
someone who has knowledge of boiling water reactor technology).
1.
Risk ranking of top 150 components from your site specific probabilistic safety
analysis (PSA) sorted by Risk Achievement Worth (RAW). Include values for
Birnbaum Importance, Risk Reduction Worth (RRW), and Fussell-Veseley (FV)
(as applicable).
2.
Provide a list of the top 200 cut-sets from your PSA.
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.
If you have an External Events or Fire PSA Model, provide the information
requested in Items 1 and 2 for external events and fire. Provide narrative
description of each coded event (including fire, flood zone description).
5.
Any pre-existing evaluation or list of components and associated 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 etc.).
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESING BASES INSPECTION (CDBI)
Enclosure
2
6.
List of available design (setup) margins for valves in the motor-operated valve
(MOV) and air-operated valve (AOV) programs.
7.
List of high risk Maintenance Rule systems/components based on engineering or
expert panel judgment.
8.
Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1)
category.
9.
Site top ten issues list (if applicable).
10.
A list of operating experience evaluations for the last 3 years.
11.
Information of any common cause failure of components experienced in the last
5 years at your facility.
12.
List of Root Cause Evaluations associated with component failures or design
issues initiated/completed in the last 5 years.
13.
Current management and engineering organizational chart.
14.
Electronic copies of Updated Final Safety Analysis Report, Technical
Specifications, Technical Specifications Bases, and Technical Requirements
Manual.
II.
Information requested (for the approx. 30 selected components) to be available by
April 23, 2008, (will be reviewed by the team in the Regional office during the week
of April 28, 2008). This information should be separated for each selected
component, especially if provided electronically (e.g., folder with component
name that includes calculations, condition reports, maintenance history, etc).
1.
List of condition reports (corrective action documents) associated with each of
the selected components for the last 4 years.
2.
The corrective maintenance history associated with each of the selected
components for the last 4 years.
3.
Copies of calculations associated with each of the selected components (if not
previously provided), excluding data files. Please review the calculations and
also provide copies of referenced material (such as drawings, engineering
requests, and vendor letters).
4.
System Health Reports, System Descriptions, and/or Design Basis Documents
that are associated with each of the selected components.
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
3
5.
A list of modifications associated with each of the selected components.
6.
Copies of operability evaluations associated with each of the selected
components and plans for restoring operability, if applicable.
7.
Copies of selected operator work-around evaluations associated with each of the
selected components and plans for resolution, if applicable.
8.
Copies of any open temporary modifications associated with each of the selected
components, if applicable.
9.
Trend data on the selected electrical/mechanical components performance for
last 3 years (For example, pumps performance including in-service testing, other
vibration monitoring, oil sample results, etc., as applicable).
10.
A copy of any internal/external self-assessments and associated corrective
action documents generated in preparation for the inspection.
11.
A copy of engineering/operations related audits completed in the last 2 years.
12.
Provide list of PRA assumptions regarding operator actions and the associated
procedures.
III.
Additional Information to be provided on May 5, 2008 on-site (for final 15 - 20
selected components)
During the in-office preparation activities, the team will be making final selections and
may identify additional information needed to support the inspection. The lead inspector
will provide a list of the additional information needed during the week of April 28, 2008.
IV.
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.
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).
3.
One complete set of P&IDs and one line electrical drawings (paper copies).
4.
Reference materials. (make available if needed during all on-site weeks):
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
4
IPE/PRA report;
Procurement documents for components selected (verify retrievable);
Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
Vendor manuals.
If you have questions regarding the information requested, please contact the lead inspector.