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| issue date = 04/22/2010 | | issue date = 04/22/2010 | ||
| title = Notification of Inspection (NRC Inspection Report 05000483-10-003) and Request for Information | | title = Notification of Inspection (NRC Inspection Report 05000483-10-003) and Request for Information | ||
| author name = Farnholtz T | | author name = Farnholtz T | ||
| author affiliation = NRC/RGN-IV/DRS/EB-1 | | author affiliation = NRC/RGN-IV/DRS/EB-1 | ||
| addressee name = Heflin A | | addressee name = Heflin A | ||
| addressee affiliation = AmerenUE | | addressee affiliation = AmerenUE | ||
| docket = 05000483 | | docket = 05000483 | ||
| Line 14: | Line 14: | ||
| page count = 7 | | page count = 7 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000483/2010003]] | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY | {{#Wiki_filter:UNITED STATES | ||
COMMISSION | NUCLEAR REGULATORY COMMISSION | ||
REGION IV 612 EAST LAMAR BLVD, SUITE 400 ARLINGTON, TEXAS 76011-4125 | REGION IV | ||
April 22, 2010 Mr.Adam C.Heflin, Senior Vice President and Chief Nuclear Officer AmerenUE P.O.Box 620 Fulton, MO 65251 SUBJECT: CALLAWAY NUCLEAR POWER PLANT-NOTIFICATION | 612 EAST LAMAR BLVD, SUITE 400 | ||
OF INSPECTION (NRC INSPECTION | ARLINGTON, TEXAS 76011-4125 | ||
REPORT 05000483/2010003) | April 22, 2010 | ||
AND REQUEST FOR INFORMATION | Mr. Adam C. Heflin, Senior Vice | ||
Dear Mr.Heflin: On June 7-18, 2010, Reactor Inspectors | President and Chief Nuclear Officer | ||
from NRC's Region IV office will perform the baseline inspection | AmerenUE | ||
of heat sink performance | P.O. Box 620 | ||
and changes, tests, experiments, and permanent plant modifications | Fulton, MO 65251 | ||
at Callaway Nuclear Power Plant, using NRC Inspection | SUBJECT: | ||
Procedure 71111.07,"Heat Sink Performance", and NRC Inspection | CALLAWAY NUCLEAR POWER PLANT - NOTIFICATION OF INSPECTION | ||
Procedure 71111.17,"Evaluations | (NRC INSPECTION REPORT 05000483/2010003) AND REQUEST FOR | ||
of Changes, Tests, Experiments, and | INFORMATION | ||
has shown that this inspection | Dear Mr. Heflin: | ||
is resource intensive both for the NRC inspectors | On June 7-18, 2010, Reactor Inspectors from NRC's Region IV office will perform the baseline | ||
and your staff.In order to minimize the impact to your onsite resources and to ensure a productive | inspection of heat sink performance and changes, tests, experiments, and permanent plant | ||
inspection, we have enclosed | modifications at Callaway Nuclear Power Plant, using NRC Inspection Procedure 71111.07, | ||
documents needed for this inspection. | "Heat Sink Performance", and NRC Inspection Procedure 71111.17, "Evaluations of Changes, | ||
Upon review of these documents, the inspectors | Tests, Experiments, and Permanent Plant Modifications." | ||
will select additional | Experience has shown that this inspection is resource intensive both for the NRC inspectors | ||
documentation | and your staff. In order to minimize the impact to your onsite resources and to ensure a | ||
for review upon arrival.It is important that all of these documents are up to date and complete in order to minimize the number of additional | productive inspection, we have enclosed a request for documents needed for this inspection. | ||
documents requested during the preparation | Upon review of these documents, the inspectors will select additional documentation for review | ||
and/or the onsite portions of the inspection. | upon arrival. It is important that all of these documents are up to date and complete in order to | ||
We have discussed the schedule for these inspection | minimize the number of additional documents requested during the preparation and/or the | ||
activities | onsite portions of the inspection. | ||
with your staff and understand | We have discussed the schedule for these inspection activities with your staff and understand | ||
that our regulatory | that our regulatory contact for this inspection will be Steve Petzel of your regulatory affairs | ||
contact for this inspection | organization. if there are any questions about this inspection or the material requested, please | ||
will be Steve Petzel of your regulatory | contact the lead inspector James Adams at (817) 860-8294 or by email | ||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its | |||
if there are any questions about this inspection | enclosure will be available electronically for public inspection in the NRC Public Document | ||
or the material requested, please contact the lead inspector James Adams at (817)860-8294 or by email In accordance | Room or from the Publicly Available Records (PARS) component of NRC's document system | ||
with 10 CFR 2.390 of the NRC's"Rules of Practice," a copy of this letter and its enclosure will be available electronically | (ADAMS). ADAMS is accessible from the NRC Web site at .!:lllirJJJt:!:!:£.~LCQ.J~~ilillD9.:: | ||
for public inspection | ~~~~---=...;. (the Public Electronic Reading Room). | ||
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(the Public Electronic | AmerenUE | ||
Reading Room). | Sincerely, L | ||
AmerenUE Sincerely, L.C Thomas Farnholtz, Chief Engineering | . C | ||
Branch 1 Division of Reactor Safety Docket: 50-483 License: NPF-30 Enclosure: | Thomas Farnholtz, Chief | ||
Evaluations | Engineering Branch 1 | ||
of Changes, Tests, or Experiments | Division of Reactor Safety | ||
and Permanent Plant Modifications | Docket: | ||
and Heat Exchanger Performance | 50-483 | ||
Document Request cc w/enclosure: | License: NPF-30 | ||
Mr.Luke H.Graessle Director, Operations | Enclosure: | ||
Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications and Heat | |||
Exchanger Performance Document Request | |||
cc w/enclosure: | |||
AmerenUE John O'Neill, Esq.Pillsbury Winthrop Shaw Pittman LLP 2300 N.Street, N.W.Washington, DC 20037 Missouri Public Service Commission | Mr. Luke H. Graessle | ||
P.O.Box 360 Jefferson City, MO 65102-0360 | Director, Operations Support | ||
Dru Buntin Director of Government | AmerenUE | ||
P.O. Box 620 | |||
of Natural Resources P.O.Box 176 Jefferson City, MO 65102-0176 | Fulton, MO 65251 | ||
Mr.Rick A Muench, President and Chief Executive officer Wolf Creek Nuclear Operating Corporation | E. Hope Bradley | ||
P.O.Box411 Burlington, KS 66839-3-Kathleen Logan Smith, Executive Director and Kay Drey, Representative, Board of Directors Missouri Coalition for the Environment | Manager, Protective Services | ||
6267 Delmar Boulevard, Suite 2E St.Louis, MO 63130 Presiding Commissioner | AmerenUE | ||
Callaway County Court House 10 East Fifth Street Fulton, MO 65251 Director, Missouri State Emergency Management | P.O. Box 620 | ||
Fulton, MO 65251 | |||
Chief, Technological | Mr. Scott Sandbothe, Manager | ||
Hazards Branch FEMA Region VII 9221 Ward Parkway, Suite 300 Kansas City, MO 64114-3372 | Plant Support | ||
Mr.Scott Clardy, Administrator | AmerenUE | ||
Section for Disease Controi Missouri Department | P.O. Box 620 | ||
of Health and Senior Services P.O.Box 570 Jefferson City, MO 65102-0570 | Fulton, MO 65251 | ||
AmerenUE Certrec Corporation | R. E. Farnam | ||
4200 South Hulen, Suite 422 Fort Worth, TX 76109 Mr.Keith G.Henke, Planner II Division of Community and Public Health Office of Emergency Coordination | Assistant Manager, Technical | ||
Missouri Department | Training | ||
of Health and Senior Services 930 Wildwood Drive P.O.Box 570 Jefferson City, MO 65102-4- | AmerenUE | ||
Evaluations | P.O. Box 620 | ||
of Changes, Tests, or Experiments | Fulton, MO 65251 | ||
and Permanent Plant Modifications | J. S. Geyer | ||
Radiation Protection Manager | |||
AmerenUE | |||
P.O. Box 620 | |||
Fulton, MO 65251 | |||
AmerenUE | |||
John O'Neill, Esq. | |||
Pillsbury Winthrop Shaw Pittman LLP | |||
2300 N. Street, N.W. | |||
Washington, DC 20037 | |||
Missouri Public Service Commission | |||
P.O. Box 360 | |||
Jefferson City, MO 65102-0360 | |||
Dru Buntin | |||
Director of Government Affairs | |||
Department of Natural Resources | |||
P.O. Box 176 | |||
Jefferson City, MO 65102-0176 | |||
Mr. Rick A Muench, President and | |||
Chief Executive officer | |||
Wolf Creek Nuclear Operating Corporation | |||
P.O. Box411 | |||
Burlington, KS 66839 | |||
- 3 - | |||
Kathleen Logan Smith, Executive Director and | |||
Kay Drey, Representative, Board of Directors | |||
Missouri Coalition for the Environment | |||
6267 Delmar Boulevard, Suite 2E | |||
St. Louis, MO 63130 | |||
Presiding Commissioner | |||
Callaway County Court House | |||
10 East Fifth Street | |||
Fulton, MO 65251 | |||
Director, Missouri State Emergency | |||
Management Agency | |||
P.O. Box 116 | |||
Jefferson City, MO 65102-0116 | |||
Chief, Technological Hazards Branch | |||
FEMA Region VII | |||
9221 Ward Parkway, Suite 300 | |||
Kansas City, MO 64114-3372 | |||
Mr. Scott Clardy, Administrator | |||
Section for Disease Controi | |||
Missouri Department of Health and | |||
Senior Services | |||
P.O. Box 570 | |||
Jefferson City, MO 65102-0570 | |||
AmerenUE | |||
Certrec Corporation | |||
4200 South Hulen, Suite 422 | |||
Fort Worth, TX 76109 | |||
Mr. Keith G. Henke, Planner II | |||
Division of Community and Public Health | |||
Office of Emergency Coordination | |||
Missouri Department of Health and | |||
Senior Services | |||
930 Wildwood Drive | |||
P.O. Box 570 | |||
Jefferson City, MO 65102 | |||
- 4- | |||
Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications | |||
Heat Sink Performance | Heat Sink Performance | ||
Inspection | Inspection Dates: | ||
Dates: Inspection | Inspection Procedures: | ||
Procedures: | |||
Inspectors: | Inspectors: | ||
June 7-18,2010 IP 71111.07"Heat Sink Performance" IP 71111.17"Evaluation | June 7-18,2010 | ||
of Changes, Tests, or Experiments | IP 71111.07 "Heat Sink Performance" | ||
IP 71111.17 "Evaluation of Changes, Tests, or Experiments and | |||
Requested for the In-Office Preparation | Permanent Plant Modifications" | ||
James Adams, Reactor Inspector, Lead Inspector | |||
should be sent to the Region IV office in hard copy or electronic | Theresa Buchanan, Reactor Inspector | ||
format (Certrec database preferred), in care of James Adams, by May 31, 2010, to facilitate | Abin Fairbanks, Reactor Inspector | ||
Dustin Reinert, Reactor Inspector | |||
week.The inspectors | Information Requested for the In-Office Preparation Week | ||
will select specific items from the information | The following information should be sent to the Region IV office in hard copy or electronic | ||
requested below and then request from your staff additional | format (Certrec database preferred), in care of James Adams, by May 31, 2010, to facilitate the | ||
documents needed during the onsite inspection | selection of specific items that will be reviewed during the onsite inspection week. The | ||
weeks.We ask that the specific items requested be available and ready for review on the first day of inspection. | inspectors will select specific items from the information requested below and then request from | ||
Also, we request that you categorize | your staff additional documents needed during the onsite inspection weeks. We ask that the | ||
the documents in your response with the numbered list below.Please provide requested documentation | specific items requested be available and ready for review on the first day of inspection. Also, | ||
electronically | we request that you categorize the documents in your response with the numbered list below. | ||
if possible.If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation | Please provide requested documentation electronically if possible. If requested documents are | ||
during the first day of the onsite inspection. | large and only hard copy formats are available, please inform the inspector(s), and provide | ||
If you have any questions regarding this information | subject documentation during the first day of the onsite inspection. If you have any questions | ||
request, please call the lead inspector as soon as possible.Inspection | regarding this information request, please call the lead inspector as soon as possible. | ||
Procedure 71111.07 Prior to May 31, 2010, the inspectors | Inspection Procedure 71111.07 | ||
will contact your regulatory | Prior to May 31, 2010, the inspectors will contact your regulatory affairs organization with the | ||
affairs organization | sample of two to four heat exchangers and/or heat sinks that will be selected for the inspection. | ||
with the sample of two to four heat exchangers | Once the inspectors select the inspection sample, they will be requesting the following | ||
and/or heat sinks that will be selected for the inspection. | information for the selected sample: | ||
Once the inspectors | 1. | ||
select the inspection | Callaway Nuclear Power Plant responses and commitments to NRC Generic Letter 89- | ||
sample, they will be requesting | 13. | ||
the following information | 2. | ||
for the selected sample: 1.Callaway Nuclear Power Plant responses and commitments | Heat exchanger test program/procedures, including the specific heat exchanger testing | ||
to NRC Generic | and cleaning procedures for each selected heat exchanger. | ||
for each selected heat exchanger. | 3. | ||
3.FSAR sections for selected heat exchangers. | FSAR sections for selected heat exchangers. | ||
4.Biofouling/chemistry | 4. | ||
control program/procedures | Biofouling/chemistry control program/procedures for selected heat exchangers. | ||
for selected heat exchangers. | - 1 - | ||
-1-Enclosure | Enclosure | ||
5.Operations | |||
training manual sections and design basis notebooks for the selected heat exchangers. | 5. | ||
6.Vendor specifications | Operations training manual sections and design basis notebooks for the selected heat | ||
and recommendations | exchangers. | ||
for selected heat exchangers. | 6. | ||
This should include data that can be used to determine design heat transfer coefficient | Vendor specifications and recommendations for selected heat exchangers. This should | ||
include data that can be used to determine design heat transfer coefficient and | |||
maintenance. | determine vendor recommended maintenance. | ||
7.Design heat transfer coefficient | 7. | ||
and fouling factors for selected heat exchangers. | Design heat transfer coefficient and fouling factors for selected heat exchangers. | ||
8.Water hammer evaluations | 8. | ||
for selected heat exchangers (if performed). | Water hammer evaluations for selected heat exchangers (if performed). | ||
9.System health reports for the selected heat exchangers. | 9. | ||
10.Test/Inspection | System health reports for the selected heat exchangers. | ||
results and reports covering the last 3 years for the selected heat exchangers. | 10. Test/Inspection results and reports covering the last 3 years for the selected heat | ||
11.Trended performance | exchangers. | ||
for the selected heat exchangers. | 11. Trended performance for the selected heat exchangers. | ||
12.System flow balance test results of the selected heat exchangers | 12. System flow balance test results of the selected heat exchangers for last 3 years. | ||
for last 3 years.13.Any applicable | 13. Any applicable eddy current tests for the selected heat exchangers. | ||
eddy current tests for the selected heat exchangers. | 14. If any selected heat exchanger systems are scheduled to be opened during the onsite | ||
14.If any selected heat exchanger systems are scheduled to be opened during the onsite week, the team would like to observe the interior of the system.15.A list of corrective | week, the team would like to observe the interior of the system. | ||
maintenance | 15. A list of corrective maintenance performed in the last 3 years for the selected heat | ||
performed in the last 3 years for the selected heat exchangers. | exchangers. | ||
16.A list of | 16. A list of corrective action documents issued in the last 3 years for the selected heat | ||
issued in the last 3 years for the selected heat exchangers. | exchangers. | ||
Inspection | Inspection Procedure 71111.17 | ||
Procedure 71111.17 1.A list with descriptions, of all 50.59 screenings (or equivalent) | 1. | ||
performed since August 3, 2007, which did not result in an evaluation. | A list with descriptions, of all 50.59 screenings (or equivalent) performed since August 3, | ||
Note: Description | 2007, which did not result in an evaluation. Note: Description of screenings should be | ||
of screenings | brief, but of sufficient detail that inspectors can determine the significance of the issue. | ||
should be brief, but of sufficient | 2. | ||
detail that inspectors | A list with descriptions, of all 10 CFR 50.59 evaluations performed which did not result in | ||
can determine the significance | an application for license amendment to NRC from August 3, 2007, to the present. | ||
of the issue.2.A list with descriptions, of all 10 CFR 50.59 evaluations | Note: Description of evaluations should be brief, but of sufficient detail so that inspectors | ||
performed which did not result in an application | can determine the significance of the issue. | ||
for license amendment to NRC from August 3, 2007, to the present.Note: Description | 3. | ||
of evaluations | Callaway Nuclear Power Plant procedure(s) for conducting 10 CFR 50.59 screenings | ||
should be brief, but of sufficient | |||
detail so that inspectors | |||
can determine the significance | |||
of the issue.3.Callaway Nuclear Power | |||
conducting | |||
10 CFR 50.59 screenings | |||
and evaluations. | and evaluations. | ||
A A 1:.-.1..*.:.s.1--1 | A | ||
.-1:_II r-..-........-..-J.:...-1\.-J.:__-I_._...L I_J._-I.1. | A | ||
UI all vUIIl:::l..-lIVl::: | 1:.-.1. .*.:.s.1- | ||
f"\l..-lIUII | -1 | ||
UUI..-UIIIl:::IIl;:> | :_.L:_~_ .-1: _II r-..- ........-..-J.:.. .- | ||
1l:::laLl:::U | 1\\ .-J.: __ | ||
LU'JU.'J::;al..-lIVllIl:::;:>, including screenings | -I_._ .. | ||
and evaluations | .L | ||
from August 3, 2007, to the present.-2-Enclosure | I_J._-I | ||
5.A list with descriptions | .1._ | ||
of all permanent plant modifications | r-:r'\\ | ||
dating from August 3, 2007.Include sufficient | r::'f"\\ __J.:. .:.s.: __ | ||
detail to enable the inspector to determine the significance | '"to | ||
of each modification. | f"\\ II;:>L Willi Ul:::;:>l..-lqJlIUII;:> UI all vUIIl:::l..-lIVl::: f"\\l..-lIUII UUI..-UIIIl:::IIl;:> 1l:::laLl:::U LU 'JU.'J::; al..-lIVllIl:::;:>, | ||
For this inspection, permanent plant modifications | including screenings and evaluations from August 3, 2007, to the present. | ||
include permanent plant changes, design changes, setpoint changes, procedure changes, equivalency | - 2 - | ||
evaluations, suitability | Enclosure | ||
analyses, calculations, and commercial | |||
grade dedications. | 5. | ||
6.Callaway Nuclear Power Plant procedure for implementing | A list with descriptions of all permanent plant modifications dating from August 3, 2007. | ||
and controlling | Include sufficient detail to enable the inspector to determine the significance of each | ||
modification. For this inspection, permanent plant modifications include permanent plant | |||
7.A list with descriptions, of all updates to the Callaway Nuclear Power Plant Final Safety Analysis Report performed per 10 CFR 50.71(e)from August 3,2007, to the present.Note: Description | changes, design changes, setpoint changes, procedure changes, equivalency | ||
of evaluations | evaluations, suitability analyses, calculations, and commercial grade dedications. | ||
should be brief, but of sufficient | 6. | ||
detail that inspectors | Callaway Nuclear Power Plant procedure for implementing and controlling permanent | ||
can determine the significance | plant modifications. | ||
of the issue.8.A list with descriptions | 7. | ||
of all Corrective | A list with descriptions, of all updates to the Callaway Nuclear Power Plant Final Safety | ||
Action documents related to your permanent plant modification | Analysis Report performed per 10 CFR 50.71(e) from August 3,2007, to the present. | ||
program and its implementation | Note: Description of evaluations should be brief, but of sufficient detail that inspectors | ||
since August 3, 2007.Include sufficient | can determine the significance of the issue. | ||
detail to enable the inspector to determine the significance | 8. | ||
of each modification. | A list with descriptions of all Corrective Action documents related to your permanent | ||
9.A listing of personnel qualified to prepare 50.59 screenings | plant modification program and its implementation since August 3, 2007. Include | ||
and evaluations, including qualification | sufficient detail to enable the inspector to determine the significance of each | ||
dates.10.A listing of personnel qualified to review and approve 50.59 screenings | modification. | ||
and/or evaluations, including qualification | 9. | ||
dates.Inspector Contact Information: | A listing of personnel qualified to prepare 50.59 screenings and evaluations, including | ||
James Adams Reactor Inspector 817-860-8294 Theresa Buchanan Reactor Inspector 817-276-6503 Mailing Address: US NRC Region IV Attn: James Adams 612 E.Lamar Blvd., Suite 400 Arlington, TX 76011-4125 | qualification dates. | ||
Abin Fairbanks Reactor Inspector 817-860-8158 | 10. A listing of personnel qualified to review and approve 50.59 screenings and/or | ||
Dustin Reinert Reactor Inspector 817-860-8244-3-Enclosure | evaluations, including qualification dates. | ||
Inspector Contact Information: | |||
James Adams | |||
Reactor Inspector | |||
817-860-8294 | |||
Theresa Buchanan | |||
Reactor Inspector | |||
817-276-6503 | |||
Mailing Address: | |||
US NRC Region IV | |||
Attn: James Adams | |||
612 E. Lamar Blvd., Suite 400 | |||
Arlington, TX 76011-4125 | |||
Abin Fairbanks | |||
Reactor Inspector | |||
817-860-8158 | |||
Dustin Reinert | |||
Reactor Inspector | |||
817-860-8244 | |||
- 3 - | |||
Enclosure | |||
}} | }} | ||
Latest revision as of 05:30, 14 January 2025
| ML101121011 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 04/22/2010 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Heflin A AmerenUE |
| References | |
| IR-10-003 | |
| Download: ML101121011 (7) | |
See also: IR 05000483/2010003
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION IV
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, TEXAS 76011-4125
April 22, 2010
Mr. Adam C. Heflin, Senior Vice
President and Chief Nuclear Officer
AmerenUE
P.O. Box 620
Fulton, MO 65251
SUBJECT:
CALLAWAY NUCLEAR POWER PLANT - NOTIFICATION OF INSPECTION
(NRC INSPECTION REPORT 05000483/2010003) AND REQUEST FOR
INFORMATION
Dear Mr. Heflin:
On June 7-18, 2010, Reactor Inspectors from NRC's Region IV office will perform the baseline
inspection of heat sink performance and changes, tests, experiments, and permanent plant
modifications at Callaway Nuclear Power Plant, using NRC Inspection Procedure 71111.07,
"Heat Sink Performance", and NRC Inspection Procedure 71111.17, "Evaluations of Changes,
Tests, Experiments, and Permanent Plant Modifications."
Experience has shown that this inspection is resource intensive both for the NRC inspectors
and your staff. In order to minimize the impact to your onsite resources and to ensure a
productive inspection, we have enclosed a request for documents needed for this inspection.
Upon review of these documents, the inspectors will select additional documentation for review
upon arrival. 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.
We have discussed the schedule for these inspection activities with your staff and understand
that our regulatory contact for this inspection will be Steve Petzel of your regulatory affairs
organization. if there are any questions about this inspection or the material requested, please
contact the lead inspector James Adams at (817) 860-8294 or by email
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 .!:lllirJJJt:!:!:£.~LCQ.J~~ilillD9.::
~~~~---=...;. (the Public Electronic Reading Room).
AmerenUE
Sincerely, L
. C
Thomas Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket:
50-483
License: NPF-30
Enclosure:
Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications and Heat
Exchanger Performance Document Request
cc w/enclosure:
Mr. Luke H. Graessle
Director, Operations Support
AmerenUE
P.O. Box 620
Fulton, MO 65251
E. Hope Bradley
Manager, Protective Services
AmerenUE
P.O. Box 620
Fulton, MO 65251
Mr. Scott Sandbothe, Manager
Plant Support
AmerenUE
P.O. Box 620
Fulton, MO 65251
R. E. Farnam
Assistant Manager, Technical
Training
AmerenUE
P.O. Box 620
Fulton, MO 65251
J. S. Geyer
Radiation Protection Manager
AmerenUE
P.O. Box 620
Fulton, MO 65251
AmerenUE
John O'Neill, Esq.
Pillsbury Winthrop Shaw Pittman LLP
2300 N. Street, N.W.
Washington, DC 20037
Missouri Public Service Commission
P.O. Box 360
Jefferson City, MO 65102-0360
Dru Buntin
Director of Government Affairs
Department of Natural Resources
P.O. Box 176
Jefferson City, MO 65102-0176
Mr. Rick A Muench, President and
Chief Executive officer
Wolf Creek Nuclear Operating Corporation
P.O. Box411
Burlington, KS 66839
- 3 -
Kathleen Logan Smith, Executive Director and
Kay Drey, Representative, Board of Directors
Missouri Coalition for the Environment
6267 Delmar Boulevard, Suite 2E
St. Louis, MO 63130
Presiding Commissioner
Callaway County Court House
10 East Fifth Street
Fulton, MO 65251
Director, Missouri State Emergency
Management Agency
P.O. Box 116
Jefferson City, MO 65102-0116
Chief, Technological Hazards Branch
FEMA Region VII
9221 Ward Parkway, Suite 300
Kansas City, MO 64114-3372
Mr. Scott Clardy, Administrator
Section for Disease Controi
Missouri Department of Health and
Senior Services
P.O. Box 570
Jefferson City, MO 65102-0570
AmerenUE
Certrec Corporation
4200 South Hulen, Suite 422
Fort Worth, TX 76109
Mr. Keith G. Henke, Planner II
Division of Community and Public Health
Office of Emergency Coordination
Missouri Department of Health and
Senior Services
930 Wildwood Drive
P.O. Box 570
Jefferson City, MO 65102
- 4-
Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
Heat Sink Performance
Inspection Dates:
Inspection Procedures:
Inspectors:
June 7-18,2010
IP 71111.07 "Heat Sink Performance"
IP 71111.17 "Evaluation of Changes, Tests, or Experiments and
Permanent Plant Modifications"
James Adams, Reactor Inspector, Lead Inspector
Theresa Buchanan, Reactor Inspector
Abin Fairbanks, Reactor Inspector
Dustin Reinert, Reactor Inspector
Information Requested for the In-Office Preparation Week
The following information should be sent to the Region IV office in hard copy or electronic
format (Certrec database preferred), in care of James Adams, by May 31, 2010, to facilitate the
selection of specific items that will be reviewed during the onsite inspection week. The
inspectors will select specific items from the information requested below and then request from
your staff additional documents needed during the onsite inspection weeks. We ask that the
specific items requested be available and ready for review on the first day of inspection. Also,
we request that you categorize the documents in your response with the numbered list below.
Please provide requested documentation electronically if possible. If requested documents are
large and only hard copy formats are available, please inform the inspector(s), and provide
subject documentation during the first day of the onsite inspection. If you have any questions
regarding this information request, please call the lead inspector as soon as possible.
Prior to May 31, 2010, the inspectors will contact your regulatory affairs organization with the
sample of two to four heat exchangers and/or heat sinks that will be selected for the inspection.
Once the inspectors select the inspection sample, they will be requesting the following
information for the selected sample:
1.
Callaway Nuclear Power Plant responses and commitments to NRC Generic Letter 89-
13.
2.
Heat exchanger test program/procedures, including the specific heat exchanger testing
and cleaning procedures for each selected heat exchanger.
3.
FSAR sections for selected heat exchangers.
4.
Biofouling/chemistry control program/procedures for selected heat exchangers.
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Enclosure
5.
Operations training manual sections and design basis notebooks for the selected heat
exchangers.
6.
Vendor specifications and recommendations for selected heat exchangers. This should
include data that can be used to determine design heat transfer coefficient and
determine vendor recommended maintenance.
7.
Design heat transfer coefficient and fouling factors for selected heat exchangers.
8.
Water hammer evaluations for selected heat exchangers (if performed).
9.
System health reports for the selected heat exchangers.
10. Test/Inspection results and reports covering the last 3 years for the selected heat
exchangers.
11. Trended performance for the selected heat exchangers.
12. System flow balance test results of the selected heat exchangers for last 3 years.
13. Any applicable eddy current tests for the selected heat exchangers.
14. If any selected heat exchanger systems are scheduled to be opened during the onsite
week, the team would like to observe the interior of the system.
15. A list of corrective maintenance performed in the last 3 years for the selected heat
exchangers.
16. A list of corrective action documents issued in the last 3 years for the selected heat
exchangers.
1.
A list with descriptions, of all 50.59 screenings (or equivalent) performed since August 3,
2007, which did not result in an evaluation. Note: Description of screenings should be
brief, but of sufficient detail that inspectors can determine the significance of the issue.
2.
A list with descriptions, of all 10 CFR 50.59 evaluations performed which did not result in
an application for license amendment to NRC from August 3, 2007, to the present.
Note: Description of evaluations should be brief, but of sufficient detail so that inspectors
can determine the significance of the issue.
3.
Callaway Nuclear Power Plant procedure(s) for conducting 10 CFR 50.59 screenings
and evaluations.
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including screenings and evaluations from August 3, 2007, to the present.
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Enclosure
5.
A list with descriptions of all permanent plant modifications dating from August 3, 2007.
Include sufficient detail to enable the inspector to determine the significance of each
modification. For this inspection, permanent plant modifications include permanent plant
changes, design changes, setpoint changes, procedure changes, equivalency
evaluations, suitability analyses, calculations, and commercial grade dedications.
6.
Callaway Nuclear Power Plant procedure for implementing and controlling permanent
plant modifications.
7.
A list with descriptions, of all updates to the Callaway Nuclear Power Plant Final Safety
Analysis Report performed per 10 CFR 50.71(e) from August 3,2007, to the present.
Note: Description of evaluations should be brief, but of sufficient detail that inspectors
can determine the significance of the issue.
8.
A list with descriptions of all Corrective Action documents related to your permanent
plant modification program and its implementation since August 3, 2007. Include
sufficient detail to enable the inspector to determine the significance of each
modification.
9.
A listing of personnel qualified to prepare 50.59 screenings and evaluations, including
qualification dates.
10. A listing of personnel qualified to review and approve 50.59 screenings and/or
evaluations, including qualification dates.
Inspector Contact Information:
James Adams
Reactor Inspector
817-860-8294
Reactor Inspector
817-276-6503
Mailing Address:
US NRC Region IV
Attn: James Adams
612 E. Lamar Blvd., Suite 400
Arlington, TX 76011-4125
Abin Fairbanks
Reactor Inspector
817-860-8158
Reactor Inspector
817-860-8244
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Enclosure