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| number = ML101121011 | | number = ML101121011 | ||
| issue date = 04/22/2010 | | issue date = 04/22/2010 | ||
| title = | | 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: CALLAWAY NUCLEAR POWER PLANT - NOTIFICATION OF INSPECTION | ||
Procedure 71111.07,"Heat Sink Performance", and NRC Inspection | (NRC INSPECTION REPORT 05000483/2010003) AND REQUEST FOR | ||
Procedure 71111.17,"Evaluations | INFORMATION | ||
of Changes, Tests, Experiments, and | Dear Mr. Heflin: | ||
has shown that this inspection | On June 7-18, 2010, Reactor Inspectors from NRC's Region IV office will perform the baseline | ||
is resource intensive both for the NRC inspectors | inspection of heat sink performance and changes, tests, experiments, and permanent plant | ||
and your staff.In order to minimize the impact to your onsite resources and to ensure a productive | modifications at Callaway Nuclear Power Plant, using NRC Inspection Procedure 71111.07, | ||
inspection, we have enclosed | "Heat Sink Performance", and NRC Inspection Procedure 71111.17, "Evaluations of Changes, | ||
documents needed for this inspection. | Tests, Experiments, and Permanent Plant Modifications." | ||
Upon review of these documents, the inspectors | Experience has shown that this inspection is resource intensive both for the NRC inspectors | ||
will select additional | and your staff. In order to minimize the impact to your onsite resources and to ensure a | ||
documentation | productive inspection, we have enclosed a request for documents needed for this inspection. | ||
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 | Upon review of these documents, the inspectors will select additional documentation for review | ||
documents requested during the preparation | upon arrival. It is important that all of these documents are up to date and complete in order to | ||
and/or the onsite portions of the inspection. | minimize the number of additional documents requested during the preparation and/or the | ||
We have discussed the schedule for these inspection | onsite portions of the inspection. | ||
activities | We have discussed the schedule for these inspection activities with your staff and understand | ||
with your staff and understand | that our regulatory contact for this inspection will be Steve Petzel of your regulatory affairs | ||
that our regulatory | organization. if there are any questions about this inspection or the material requested, please | ||
contact for this inspection | contact the lead inspector James Adams at (817) 860-8294 or by email | ||
will be Steve Petzel of your regulatory | 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 | |||
if there are any questions about this inspection | Room or from the Publicly Available Records (PARS) component of NRC's document system | ||
or the material requested, please contact the lead inspector James Adams at (817)860-8294 or by email In accordance | (ADAMS). ADAMS is accessible from the NRC Web site at .!:lllirJJJt:!:!:£.~LCQ.J~~ilillD9.:: | ||
with 10 CFR 2.390 of the NRC's"Rules of Practice," a copy of this letter and its enclosure will be available electronically | ~~~~---=...;. (the Public Electronic Reading Room). | ||
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 | AmerenUE | ||
from the NRC Web site at(the Public Electronic | Sincerely, L | ||
Reading Room). | . C | ||
AmerenUE Sincerely, L.C Thomas Farnholtz, Chief Engineering | Thomas Farnholtz, Chief | ||
Branch 1 Division of Reactor Safety Docket: 50-483 License: NPF-30 Enclosure: | Engineering Branch 1 | ||
Evaluations | Division of Reactor Safety | ||
of Changes, Tests, or Experiments | Docket: 50-483 | ||
and Permanent Plant Modifications | License: NPF-30 | ||
and Heat Exchanger Performance | Enclosure: | ||
Document Request cc w/enclosure: | Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications and Heat | ||
Mr.Luke H.Graessle Director, Operations | Exchanger Performance Document Request | ||
cc w/enclosure: | |||
Mr. Luke H. Graessle | |||
Director, Operations Support | |||
AmerenUE John O'Neill, Esq.Pillsbury Winthrop Shaw Pittman LLP 2300 N.Street, N.W.Washington, DC 20037 Missouri Public Service Commission | AmerenUE | ||
P.O.Box 360 Jefferson City, MO 65102-0360 | P.O. Box 620 | ||
Dru Buntin Director of Government | Fulton, MO 65251 | ||
E. Hope Bradley | |||
of Natural Resources P.O.Box 176 Jefferson City, MO 65102-0176 | Manager, Protective Services | ||
Mr.Rick A Muench, President and Chief Executive officer Wolf Creek Nuclear Operating Corporation | AmerenUE | ||
P.O.Box411 Burlington, KS 66839 | P.O. Box 620 | ||
6267 Delmar Boulevard, Suite 2E St.Louis, MO 63130 Presiding Commissioner | Fulton, MO 65251 | ||
Callaway County Court House 10 East Fifth Street Fulton, MO 65251 Director, Missouri State Emergency Management | Mr. Scott Sandbothe, Manager | ||
Plant Support | |||
Chief, Technological | AmerenUE | ||
Hazards Branch FEMA Region VII 9221 Ward Parkway, Suite 300 Kansas City, MO 64114-3372 | P.O. Box 620 | ||
Mr.Scott Clardy, Administrator | Fulton, MO 65251 | ||
Section for Disease Controi Missouri Department | R. E. Farnam | ||
of Health and Senior Services P.O.Box 570 Jefferson City, MO 65102-0570 | Assistant Manager, Technical | ||
AmerenUE Certrec Corporation | Training | ||
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 | AmerenUE | ||
Missouri Department | P.O. Box 620 | ||
of Health and Senior Services 930 Wildwood Drive P.O.Box 570 Jefferson City, MO 65102 | Fulton, MO 65251 | ||
Evaluations | J. S. Geyer | ||
of Changes, Tests, or Experiments | Radiation Protection Manager | ||
and Permanent Plant Modifications | AmerenUE | ||
Heat Sink Performance | P.O. Box 620 | ||
Inspection | Fulton, MO 65251 | ||
Dates: | |||
AmerenUE -3- | |||
John O'Neill, Esq. | |||
June 7-18,2010 IP 71111.07"Heat Sink Performance" IP 71111.17"Evaluation | Pillsbury Winthrop Shaw Pittman LLP | ||
of Changes, Tests, or Experiments | 2300 N. Street, N.W. | ||
Washington, DC 20037 | |||
Requested for the In-Office Preparation | Missouri Public Service Commission | ||
P.O. Box 360 | |||
should be sent to the Region IV office in hard copy or electronic | Jefferson City, MO 65102-0360 | ||
format (Certrec database preferred), in care of James Adams, by May 31, 2010, to facilitate | Dru Buntin | ||
Director of Government Affairs | |||
week.The inspectors | Department of Natural Resources | ||
will select specific items from the information | P.O. Box 176 | ||
requested below and then request from your staff additional | Jefferson City, MO 65102-0176 | ||
documents needed during the onsite inspection | Mr. Rick A Muench, President and | ||
weeks.We ask that the specific items requested be available and ready for review on the first day of inspection. | Chief Executive officer | ||
Also, we request that you categorize | Wolf Creek Nuclear Operating Corporation | ||
the documents in your response with the numbered list below.Please provide requested documentation | P.O. Box411 | ||
electronically | Burlington, KS 66839 | ||
if possible.If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation | Kathleen Logan Smith, Executive Director and | ||
during the first day of the onsite inspection. | Kay Drey, Representative, Board of Directors | ||
If you have any questions regarding this information | Missouri Coalition for the Environment | ||
request, please call the lead inspector as soon as possible.Inspection | 6267 Delmar Boulevard, Suite 2E | ||
Procedure 71111.07 Prior to May 31, 2010, the inspectors | St. Louis, MO 63130 | ||
will contact your regulatory | Presiding Commissioner | ||
affairs organization | Callaway County Court House | ||
with the sample of two to four heat exchangers | 10 East Fifth Street | ||
and/or heat sinks that will be selected for the inspection. | Fulton, MO 65251 | ||
Once the inspectors | Director, Missouri State Emergency | ||
select the inspection | Management Agency | ||
sample, they will be requesting | P.O. Box 116 | ||
the following information | Jefferson City, MO 65102-0116 | ||
for the selected sample: 1.Callaway Nuclear Power Plant responses and commitments | Chief, Technological Hazards Branch | ||
to NRC Generic | FEMA Region VII | ||
for each selected heat exchanger. | 9221 Ward Parkway, Suite 300 | ||
3.FSAR sections for selected heat exchangers. | Kansas City, MO 64114-3372 | ||
4.Biofouling/chemistry | Mr. Scott Clardy, Administrator | ||
control program/procedures | Section for Disease Controi | ||
for selected heat exchangers. | Missouri Department of Health and | ||
-1-Enclosure | Senior Services | ||
5.Operations | P.O. Box 570 | ||
training manual sections and design basis notebooks for the selected heat exchangers. | Jefferson City, MO 65102-0570 | ||
6.Vendor specifications | |||
and recommendations | AmerenUE - 4- | ||
for selected heat exchangers. | Certrec Corporation | ||
This should include data that can be used to determine design heat transfer coefficient | 4200 South Hulen, Suite 422 | ||
Fort Worth, TX 76109 | |||
maintenance. | Mr. Keith G. Henke, Planner II | ||
7.Design heat transfer coefficient | Division of Community and Public Health | ||
and fouling factors for selected heat exchangers. | Office of Emergency Coordination | ||
8.Water hammer evaluations | Missouri Department of Health and | ||
for selected heat exchangers (if performed). | Senior Services | ||
9.System health reports for the selected heat exchangers. | 930 Wildwood Drive | ||
10.Test/Inspection | P.O. Box 570 | ||
results and reports covering the last 3 years for the selected heat exchangers. | Jefferson City, MO 65102 | ||
11.Trended performance | |||
for the selected heat exchangers. | Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications | ||
12.System flow balance test results of the selected heat exchangers | Heat Sink Performance | ||
for last 3 years.13.Any applicable | Inspection Dates: June 7-18,2010 | ||
eddy current tests for the selected heat exchangers. | Inspection Procedures: IP 71111.07 "Heat Sink Performance" | ||
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 | IP 71111.17 "Evaluation of Changes, Tests, or Experiments and | ||
maintenance | Permanent Plant Modifications" | ||
performed in the last 3 years for the selected heat exchangers. | Inspectors: James Adams, Reactor Inspector, Lead Inspector | ||
16.A list of | Theresa Buchanan, Reactor Inspector | ||
issued in the last 3 years for the selected heat exchangers. | Abin Fairbanks, Reactor Inspector | ||
Inspection | Dustin Reinert, Reactor Inspector | ||
Procedure 71111.17 1.A list with descriptions, of all 50.59 screenings (or equivalent) | Information Requested for the In-Office Preparation Week | ||
performed since August 3, 2007, which did not result in an evaluation. | The following information should be sent to the Region IV office in hard copy or electronic | ||
Note: Description | format (Certrec database preferred), in care of James Adams, by May 31, 2010, to facilitate the | ||
of screenings | selection of specific items that will be reviewed during the onsite inspection week. The | ||
should be brief, but of sufficient | inspectors will select specific items from the information requested below and then request from | ||
detail that inspectors | your staff additional documents needed during the onsite inspection weeks. We ask that the | ||
can determine the significance | specific items requested be available and ready for review on the first day of inspection. Also, | ||
of the issue.2.A list with descriptions, of all 10 CFR 50.59 evaluations | we request that you categorize the documents in your response with the numbered list below. | ||
performed which did not result in an application | Please provide requested documentation electronically if possible. If requested documents are | ||
for license amendment to NRC from August 3, 2007, to the present.Note: Description | large and only hard copy formats are available, please inform the inspector(s), and provide | ||
of evaluations | subject documentation during the first day of the onsite inspection. If you have any questions | ||
should be brief, but of sufficient | regarding this information request, please call the lead inspector as soon as possible. | ||
detail so that inspectors | Inspection Procedure 71111.07 | ||
can determine the significance | Prior to May 31, 2010, the inspectors will contact your regulatory affairs organization with the | ||
of the issue.3.Callaway Nuclear Power | sample of two to four heat exchangers and/or heat sinks that will be selected for the inspection. | ||
conducting | Once the inspectors select the inspection sample, they will be requesting the following | ||
10 CFR 50.59 screenings | information for the selected sample: | ||
and evaluations. | 1. Callaway Nuclear Power Plant responses and commitments to NRC Generic Letter 89- | ||
A A 1:.-.1..*.:.s.1--1 | 13. | ||
.-1:_II r-..-........-..-J.:...-1\.-J.: | 2. Heat exchanger test program/procedures, including the specific heat exchanger testing | ||
UI all vUIIl:::l..-lIVl::: | and cleaning procedures for each selected heat exchanger. | ||
f"\l..-lIUII | 3. FSAR sections for selected heat exchangers. | ||
UUI..-UIIIl:::IIl;:> | 4. Biofouling/chemistry control program/procedures for selected heat exchangers. | ||
1l:::laLl:::U | - 1- Enclosure | ||
LU'JU.'J::;al..-lIVllIl:::;:>, including screenings | |||
and evaluations | 5. Operations training manual sections and design basis notebooks for the selected heat | ||
from August 3, 2007, to the present.-2-Enclosure | exchangers. | ||
5.A list with descriptions | 6. Vendor specifications and recommendations for selected heat exchangers. This should | ||
of all permanent plant modifications | include data that can be used to determine design heat transfer coefficient and | ||
dating from August 3, 2007.Include sufficient | determine vendor recommended maintenance. | ||
detail to enable the inspector to determine the significance | 7. Design heat transfer coefficient and fouling factors for selected heat exchangers. | ||
of each modification. | 8. Water hammer evaluations for selected heat exchangers (if performed). | ||
For this inspection, permanent plant modifications | 9. System health reports for the selected heat exchangers. | ||
include permanent plant changes, design changes, setpoint changes, procedure changes, equivalency | 10. Test/Inspection results and reports covering the last 3 years for the selected heat | ||
evaluations, suitability | exchangers. | ||
analyses, calculations, and commercial | 11. Trended performance for the selected heat exchangers. | ||
grade dedications. | 12. System flow balance test results of the selected heat exchangers for last 3 years. | ||
6.Callaway Nuclear Power Plant procedure for implementing | 13. Any applicable eddy current tests for the selected heat exchangers. | ||
and controlling | 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. | |||
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 | 15. A list of corrective maintenance performed in the last 3 years for the selected heat | ||
of evaluations | exchangers. | ||
should be brief, but of sufficient | 16. A list of corrective action documents issued in the last 3 years for the selected heat | ||
detail that inspectors | exchangers. | ||
can determine the significance | Inspection Procedure 71111.17 | ||
of the issue.8.A list with descriptions | 1. A list with descriptions, of all 50.59 screenings (or equivalent) performed since August 3, | ||
of all Corrective | 2007, which did not result in an evaluation. Note: Description of screenings should be | ||
Action documents related to your permanent plant modification | brief, but of sufficient detail that inspectors can determine the significance of the issue. | ||
program and its implementation | 2. A list with descriptions, of all 10 CFR 50.59 evaluations performed which did not result in | ||
since August 3, 2007.Include sufficient | an application for license amendment to NRC from August 3, 2007, to the present. | ||
detail to enable the inspector to determine the significance | Note: Description of evaluations should be brief, but of sufficient detail so that inspectors | ||
of each modification. | can determine the significance of the issue. | ||
9.A listing of personnel qualified to prepare 50.59 screenings | 3. Callaway Nuclear Power Plant procedure(s) for conducting 10 CFR 50.59 screenings | ||
and evaluations, including qualification | and evaluations. | ||
dates.10.A listing of personnel qualified to review and approve 50.59 screenings | A A 1:.-.1. .*. :.s.1- -1 :_.L:_~_ .-1: _II r-..- ........-. .-J.: . . .- 1\ .-J.: _ _ -I_._ .. .L I_J._-I .1._ r-:r'\ r::'f"\ _ _ J.: . . :.s.: __ | ||
and/or evaluations, including qualification | '"to 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:::;:>, | ||
dates.Inspector Contact Information: | including screenings and evaluations from August 3, 2007, to the present. | ||
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 | -2- 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 Abin Fairbanks | |||
Reactor Inspector Reactor Inspector | |||
817-860-8294 817-860-8158 | |||
Theresa Buchanan Dustin Reinert | |||
Reactor Inspector Reactor Inspector | |||
817-276-6503 817-860-8244 | |||
Mailing Address: | |||
US NRC Region IV | |||
Attn: James Adams | |||
612 E. Lamar Blvd., Suite 400 | |||
Arlington, TX 76011-4125 | |||
-3- Enclosure | |||
}} | }} | ||
Latest revision as of 20:36, 13 November 2019
| 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 -3-
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
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 - 4-
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
Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
Heat Sink Performance
Inspection Dates: June 7-18,2010
Inspection Procedures: IP 71111.07 "Heat Sink Performance"
IP 71111.17 "Evaluation of Changes, Tests, or Experiments and
Permanent Plant Modifications"
Inspectors: 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.
- 1- 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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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 Abin Fairbanks
Reactor Inspector Reactor Inspector
817-860-8294 817-860-8158
Theresa Buchanan Dustin Reinert
Reactor Inspector Reactor Inspector
817-276-6503 817-860-8244
Mailing Address:
US NRC Region IV
Attn: James Adams
612 E. Lamar Blvd., Suite 400
Arlington, TX 76011-4125
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