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| issue date = 07/24/2007 | | issue date = 07/24/2007 | ||
| title = Errata for Comanche Peak - NRC Integrated IR 05000445-07-002 and 05000446-07-002 | | title = Errata for Comanche Peak - NRC Integrated IR 05000445-07-002 and 05000446-07-002 | ||
| author name = Johnson C | | author name = Johnson C | ||
| author affiliation = NRC/RGN-IV/DRP/RPB-A | | author affiliation = NRC/RGN-IV/DRP/RPB-A | ||
| addressee name = Blevins M | | addressee name = Blevins M | ||
| Line 14: | Line 14: | ||
| page count = 9 | | page count = 9 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000445/2007002]] | ||
=Text= | =Text= | ||
{{#Wiki_filter:July 24, | {{#Wiki_filter:July 24, 2007 | ||
Mike Blevins, Senior Vice President | |||
and Chief Nuclear Officer | |||
TXU Power | TXU Power | ||
ATTN: Regulatory Affairs | ATTN: Regulatory Affairs | ||
Comanche Peak Steam Electric Station | Comanche Peak Steam Electric Station | ||
P.O. Box 1002 | P.O. Box 1002 | ||
Glen Rose, TX | Glen Rose, TX 76043 | ||
05000446/ | SUBJECT: ERRATA FOR COMANCHE PEAK STEAM ELECTRIC STATION - NRC | ||
Please append the following enclosure to the applicable sections of the Report Details in | INTEGRATED INSPECTION REPORT 05000445/2007002 AND | ||
05000446/2007002 | |||
Dear Mr. Blevins: | |||
Please append the following enclosure to the applicable sections of the Report Details in NRC | |||
Inspection Report 05000445/2007002 and 05000446/2007002, dated May 4, 2007. This | |||
enclosure documents inspection activities associated with NRC Temporary Instruction | enclosure documents inspection activities associated with NRC Temporary Instruction | ||
2515/166. These activities were conducted during the three-month inspection period of | 2515/166. These activities were conducted during the three-month inspection period of | ||
January 1 through March 23, 2007.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, | January 1 through March 23, 2007. | ||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its | |||
enclosure, and your response (if any) will be made available electronically for public inspection | |||
in the NRC Public Document Room or from the Publicly Available Records (PARS) component | in the NRC Public Document Room or from the Publicly Available Records (PARS) component | ||
of | of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at | ||
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).Should you have any questions concerning this inspection, we will be pleased to discuss | http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | ||
Division of Reactor | Should you have any questions concerning this inspection, we will be pleased to discuss them | ||
with you. | |||
Sincerely, | |||
/RA/ | |||
Claude E. Johnson, Chief | |||
Project Branch A | |||
Division of Reactor Projects | |||
Dockets: 50-445 | |||
50-446 | |||
Licenses: NPF-87 | Licenses: NPF-87 | ||
NPF-89 | NPF-89 | ||
TXU Power- 2 -Enclosure:As | |||
TXU Power | |||
- 2 - | |||
Enclosure: | |||
As stated | |||
cc w/Enclosure: | |||
Fred W. Madden, Director | |||
Regulatory Affairs | Regulatory Affairs | ||
TXU Power | TXU Power | ||
P.O. Box 1002 | P.O. Box 1002 | ||
Glen Rose, TX | Glen Rose, TX 76043 | ||
George L. Edgar, Esq. | |||
Morgan Lewis | |||
1111 Pennsylvania Avenue, NW | 1111 Pennsylvania Avenue, NW | ||
Washington, DC | Washington, DC 20004 | ||
Terry Parks, Chief Inspector | |||
Texas Department of Licensing | |||
and Regulation | and Regulation | ||
Boiler Program | Boiler Program | ||
P.O. Box 12157 | P.O. Box 12157 | ||
Austin, TX | Austin, TX 78711 | ||
The Honorable Walter Maynard | |||
Somervell County Judge | |||
P.O. Box 851 | P.O. Box 851 | ||
Glen Rose, TX | Glen Rose, TX 76043 | ||
Richard A. Ratliff, Chief | |||
Bureau of Radiation Control | |||
Texas Department of Health | Texas Department of Health | ||
1100 West 49th Street | 1100 West 49th Street | ||
Austin, TX 78756- | Austin, TX 78756-3189 | ||
Environmental and Natural | |||
Resources Policy Director | |||
Office of the Governor | Office of the Governor | ||
P.O. Box 12428 | P.O. Box 12428 | ||
Austin, TX 78711- | Austin, TX 78711-3189 | ||
Brian Almon | |||
Public Utility Commission | |||
William B. Travis Building | William B. Travis Building | ||
P.O. Box 13326 | P.O. Box 13326 | ||
Austin, TX 78711-3326 | Austin, TX 78711-3326 | ||
TXU Power- 3 -Susan M. | |||
TXU Power | |||
- 3 - | |||
Susan M. Jablonski | |||
Office of Permitting, Remediation | |||
and Registration | and Registration | ||
Texas Commission on | Texas Commission on | ||
| Line 62: | Line 100: | ||
MC-122 | MC-122 | ||
P.O. Box 13087 | P.O. Box 13087 | ||
Austin, TX 78711-3087 | Austin, TX 78711-3087 | ||
TXU Power- 4 -Electronic distribution by RIV:Regional Administrator (BSM1)DRP Director (ATH)DRS Director (RJC1)DRS Deputy Director (WBJ)Senior Resident Inspector (DBA)Branch Chief, DRP/A (CEJ1)Senior Project Engineer, DRP/A (TRF)Team Leader, DRP/TSS (FLB2)RITS Coordinator (MSH3)DRS STA (DAP)M. Kunowski, OEDO RIV Coordinator (MAK3)ROPreports | |||
CP Site Secretary (ESS)SUNSI Review Completed: | TXU Power | ||
G Non-Publicly Available | - 4 - | ||
G Sensitive Non- | Electronic distribution by RIV: | ||
Enclosure-1- | Regional Administrator (BSM1) | ||
Generic Letter 2004-02, | DRP Director (ATH) | ||
Recirculation During Design Basis Accidents at Pressurized Water Reactors. | DRS Director (RJC1) | ||
accordance with 10 CFR 50.59 processes.The inspector observed the installation of sump strainers and other | DRS Deputy Director (WBJ) | ||
Senior Resident Inspector (DBA) | |||
Branch Chief, DRP/A (CEJ1) | |||
Senior Project Engineer, DRP/A (TRF) | |||
Team Leader, DRP/TSS (FLB2) | |||
RITS Coordinator (MSH3) | |||
DRS STA (DAP) | |||
M. Kunowski, OEDO RIV Coordinator (MAK3) | |||
ROPreports | |||
CP Site Secretary (ESS) | |||
SUNSI Review Completed: GAG__ ADAMS: / Yes | |||
G No Initials: ___GAG___ | |||
/ Publicly Available G Non-Publicly Available G Sensitive | |||
/ Non-Sensitive | |||
S:\\DRS\\REPORTS\\ CP2007-02RP Errata-GAG\\ ML | |||
RIV:RI:DRS/EB1 | |||
SRI:DRP/A | |||
C:DRS/EB1 | |||
STA:DRS/ | |||
C:DRP/A | |||
GAGeorge | |||
DBAllen | |||
DAPowers | |||
DAPowers | |||
CEJohnson | |||
/RA/ | |||
e-GAG | |||
/RA/ | |||
/RA/ | |||
/RA/ | |||
7/13/07 | |||
7/16/07 | |||
7/16/07 | |||
7/24/07 | |||
7/24/07 | |||
OFFICIAL RECORD COPY | |||
T=Telephone E=E-mail F=Fax | |||
Enclosure | |||
-1- | |||
ENCLOSURE | |||
4. | |||
OTHER ACTIVITIES | |||
4OA5 Other | |||
NRC Temporary Instruction 2515/166, PWR Containment Sump Blockage, | |||
Unit 1(Open) | |||
Results for the preliminary inspection of Comanche Peak Steam Electric Station | |||
(CPSES), Unit 2, were documented in Inspection Report 05000446/2006005. | |||
From March 12-14, 2007, the inspector reviewed the licensees implementation of Unit 1 | |||
plant modifications and procedure changes committed to in the licensees response to | |||
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency | |||
Recirculation During Design Basis Accidents at Pressurized Water Reactors. In | |||
addition, the inspector verified that the changes were reviewed and documented in | |||
accordance with 10 CFR 50.59 processes. | |||
The inspector observed the installation of sump strainers and other physical | |||
modifications in Unit 1. In addition, the inspector reviewed setpoint changes to the | |||
swapover point from the refueling water storage tank to the emergency recirculation | swapover point from the refueling water storage tank to the emergency recirculation | ||
sump. The setpoint changes were approved by NRC before the modification was | sump. The setpoint changes were approved by NRC before the modification was | ||
completed. Changes to the containment coatings programs, latent debris programs, | completed. Changes to the containment coatings programs, latent debris programs, | ||
and other programmatic changes, as committed, were not completed because of delays | and other programmatic changes, as committed, were not completed because of delays | ||
in the final acceptance of test results for chemical and downstream effects. At the time of the inspection, only 11 of 22 commitments have been fully completed. Final review and acceptance of chemical and downstream effects will be completed by | in the final acceptance of test results for chemical and downstream effects. | ||
At the time of the inspection, only 11 of 22 commitments have been fully completed. | |||
Final review and acceptance of chemical and downstream effects will be completed by | |||
the Office of Nuclear Reactor Regulation (NRR) at a later date. Since final acceptance | the Office of Nuclear Reactor Regulation (NRR) at a later date. Since final acceptance | ||
of the | of the licensees commitments were not complete, the inspector evaluated the | ||
recirculation sump modifications to the original design basis, Regulatory Guide 1.82, | recirculation sump modifications to the original design basis, Regulatory Guide 1.82, | ||
Revision 0, ?Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident. | Revision 0, ?Water Sources for Long-Term Recirculation Cooling Following a Loss-of- | ||
remain open. | Coolant Accident. Pending final submittal and acceptance of licensees commitments | ||
to Generic Letter 2004-02. Temporary Instruction 166 for CPSES Units 1 and 2 will | |||
remain open. | |||
4OA6 Exit Meeting Summary | |||
The inspector presented the inspection results of Temporary Instruction 2515/166 to | |||
Mr. R. Flores, Site Vice President, and other members of the licensees management | |||
staff at a pre-exit interview on March 14, 2007. The licensee's management | staff at a pre-exit interview on March 14, 2007. The licensee's management | ||
acknowledged the findings and observations presented. The inspector communicated | acknowledged the findings and observations presented. The inspector communicated | ||
to the | to the licensees management that a final exit will occur at a later date pending NRRs | ||
final acceptance of the | final acceptance of the licensees commitments to Generic Letter 2004-02. In addition, | ||
the inspector asked the licensee's management whether any materials examined during | the inspector asked the licensee's management whether any materials examined during | ||
the inspection should be considered proprietary. No proprietary information was | the inspection should be considered proprietary. No proprietary information was | ||
identified. | identified. | ||
Enclosure-2- | |||
Enclosure-3-SUPPLEMENTAL | Enclosure | ||
-2- | |||
Enclosure | |||
-3- | |||
SUPPLEMENTAL INFORMATION | |||
PARTIAL LIST OF PERSONS CONTACTED | |||
Licensee Personnel: | |||
R. Flores, Site Vice President | |||
S. Smith, Director, Site Engineering | |||
T. Hope, Regulatory Performance | T. Hope, Regulatory Performance | ||
S. Maier, Design Engineering Analysis Manager | S. Maier, Design Engineering Analysis Manager | ||
J. Meyer, Technical Support Manager | J. Meyer, Technical Support Manager | ||
C. Feist, Design Engineer | C. Feist, Design Engineer | ||
J. Seawright, Regulatory | J. Seawright, Regulatory Affairs | ||
DOCUMENTS REVIEWED | |||
and MSLB | 4OA5 Other: NRC Temporary Instruction 2515/166 | ||
Calculations | |||
NUMBER | |||
TITLE | |||
REVISION | |||
ME-CA-0000-5066 | |||
Calculation of Minimum Flood Level in the Containment | |||
Building Following a Large Break LOCA, Small Break | |||
and MSLB | |||
2 | |||
PCI-5472-S01 | |||
Structural Evaluation of the Emergency Sump Suction | |||
Strainers | |||
2 | |||
Evaluations and Engineering Reports | |||
NUMBER | |||
TITLE | |||
REVISION/DATE | |||
ER-119 | |||
Unit 2 GSI 191 Debris Source Term Confirmatory | |||
Walkdown Report | |||
0 | |||
ER-ME-118 | |||
DEBRIS SOURCE INVENTORY | |||
CONFIRMATORY WALKDOWN | |||
REPORT for Comanche Peak Steam Electric | REPORT for Comanche Peak Steam Electric | ||
Station - UNIT 1 | Station - UNIT 1 | ||
0 | |||
ER-ME-123 | |||
GSI-191 Scoping Study Comanche Peak Steam | |||
Electric Station Units 1 and 2 | |||
0 | |||
EVAL 2001-2201- | |||
05-00 | |||
Sump Performance Analysis: Upstream Effects | |||
08-01-2005 | |||
EVAL 2001-2201- | |||
10-00 | |||
Sump Performance Analysis: Debris Generation | |||
08-01-2005 | |||
EVAL 2001-2201- | |||
12-00 | |||
Sump Performance Analysis: NPSH and Head | |||
Loss | |||
08-01-2005 | |||
2 | Enclosure | ||
-4- | |||
1 | Final Design Authorization | ||
NUMBER | |||
DESCRIPTION | |||
REVISION/DATE | |||
2002-1952-02-01 | |||
Modify the Radiation Barrier around Incore | |||
Instrumentation Guide Tubes | |||
1 | |||
2002-1952-03-01 | |||
Incorporate IDA for as-built configuration | |||
1 | |||
2002-1952-04-01 | |||
Revise SK-0003 to incorporate as-built details for | |||
the door | |||
1 | |||
2005-3364-07-00 | |||
Remove the wire mesh cages from old Hot Tool | |||
Room and Fuel Transfer Tube | |||
0 | |||
Drawings | |||
NUMBER | |||
TITLE | |||
REVISION/DATE | |||
SFS-CP-GA-00 | |||
Comanche Peak Units 1 & 2 Sure-Flow Strainer | |||
General Arrangement | |||
4 | |||
SFS-CP-GA-01- | |||
001 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer General Notes | |||
7 | |||
SFS-CP-GA-01- | |||
002 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer General Notes | |||
7 | |||
SFS-CP-GA-02 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer General Arrangement - Sump | |||
2 | |||
5 | |||
SFS-CP-GA-03 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer General Arrangement - Sump | |||
1 | |||
5 | |||
SFS-CP-GA-04 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer Sections & Details | |||
3 | |||
SFS-CP-GA-05 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer Plenum Box | |||
3 | |||
SFS-CP-GA-06 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer - Sump 2 Mounting Track | |||
10 | |||
SFS-CP-GA-07 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer - Sump 1 Mounting Track | |||
10 | |||
SFS-CP-GA-09 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer General Arrangement - Sump | |||
Cover Assembly | Cover Assembly | ||
3 | |||
SFS-CP-GA-10 | |||
Comanche Peak Units 1 & 2 | |||
Sure-Flow Strainer General Arrangement - Floor | |||
Drain Strainer | Drain Strainer | ||
2 | 2 | ||
Enclosure-5- | |||
Enclosure | |||
-5- | |||
Miscellaneous | |||
NUMBER | |||
DESCRIPTION | |||
Revision/Date | |||
TXX-06062 | |||
Updated Response to Requested Information Part 2 | |||
of Generic Letter 2004-02 | |||
3-31-2006 | |||
TXX-06196 | |||
Updated Response to Requested Information Part 2 | |||
of Generic Letter 2004-02 | |||
12-13-2006 | |||
Corrective Action Document | |||
2005-003364-16-00 | |||
}} | }} | ||
Latest revision as of 22:50, 14 January 2025
| ML072050235 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 07/24/2007 |
| From: | Clay Johnson NRC/RGN-IV/DRP/RPB-A |
| To: | Blevins M TXU Power |
| References | |
| IR-07-002 | |
| Download: ML072050235 (9) | |
See also: IR 05000445/2007002
Text
July 24, 2007
Mike Blevins, Senior Vice President
and Chief Nuclear Officer
TXU Power
ATTN: Regulatory Affairs
Comanche Peak Steam Electric Station
P.O. Box 1002
Glen Rose, TX 76043
SUBJECT: ERRATA FOR COMANCHE PEAK STEAM ELECTRIC STATION - NRC
INTEGRATED INSPECTION REPORT 05000445/2007002 AND
Dear Mr. Blevins:
Please append the following enclosure to the applicable sections of the Report Details in NRC
Inspection Report 05000445/2007002 and 05000446/2007002, dated May 4, 2007. This
enclosure documents inspection activities associated with NRC Temporary Instruction
2515/166. These activities were conducted during the three-month inspection period of
January 1 through March 23, 2007.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response (if any) will be made available electronically for public inspection
in the NRC Public Document Room or from the Publicly Available Records (PARS) component
of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, we will be pleased to discuss them
with you.
Sincerely,
/RA/
Claude E. Johnson, Chief
Project Branch A
Division of Reactor Projects
Dockets: 50-445
50-446
Licenses: NPF-87
TXU Power
- 2 -
Enclosure:
As stated
cc w/Enclosure:
Fred W. Madden, Director
Regulatory Affairs
TXU Power
P.O. Box 1002
Glen Rose, TX 76043
George L. Edgar, Esq.
Morgan Lewis
1111 Pennsylvania Avenue, NW
Washington, DC 20004
Terry Parks, Chief Inspector
Texas Department of Licensing
and Regulation
Boiler Program
P.O. Box 12157
Austin, TX 78711
The Honorable Walter Maynard
Somervell County Judge
P.O. Box 851
Glen Rose, TX 76043
Richard A. Ratliff, Chief
Bureau of Radiation Control
Texas Department of Health
1100 West 49th Street
Austin, TX 78756-3189
Environmental and Natural
Resources Policy Director
Office of the Governor
P.O. Box 12428
Austin, TX 78711-3189
Brian Almon
Public Utility Commission
William B. Travis Building
P.O. Box 13326
Austin, TX 78711-3326
TXU Power
- 3 -
Susan M. Jablonski
Office of Permitting, Remediation
and Registration
Texas Commission on
Environmental Quality
MC-122
P.O. Box 13087
Austin, TX 78711-3087
TXU Power
- 4 -
Electronic distribution by RIV:
Regional Administrator (BSM1)
DRP Director (ATH)
DRS Director (RJC1)
DRS Deputy Director (WBJ)
Senior Resident Inspector (DBA)
Branch Chief, DRP/A (CEJ1)
Senior Project Engineer, DRP/A (TRF)
Team Leader, DRP/TSS (FLB2)
RITS Coordinator (MSH3)
M. Kunowski, OEDO RIV Coordinator (MAK3)
ROPreports
CP Site Secretary (ESS)
SUNSI Review Completed: GAG__ ADAMS: / Yes
G No Initials: ___GAG___
/ Publicly Available G Non-Publicly Available G Sensitive
/ Non-Sensitive
S:\\DRS\\REPORTS\\ CP2007-02RP Errata-GAG\\ ML
RIV:RI:DRS/EB1
SRI:DRP/A
C:DRS/EB1
STA:DRS/
C:DRP/A
GAGeorge
DBAllen
DAPowers
DAPowers
CEJohnson
/RA/
e-GAG
/RA/
/RA/
/RA/
7/13/07
7/16/07
7/16/07
7/24/07
7/24/07
OFFICIAL RECORD COPY
T=Telephone E=E-mail F=Fax
Enclosure
-1-
ENCLOSURE
4.
OTHER ACTIVITIES
4OA5 Other
NRC Temporary Instruction 2515/166, PWR Containment Sump Blockage,
Unit 1(Open)
Results for the preliminary inspection of Comanche Peak Steam Electric Station
(CPSES), Unit 2, were documented in Inspection Report 05000446/2006005.
From March 12-14, 2007, the inspector reviewed the licensees implementation of Unit 1
plant modifications and procedure changes committed to in the licensees response to
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized Water Reactors. In
addition, the inspector verified that the changes were reviewed and documented in
accordance with 10 CFR 50.59 processes.
The inspector observed the installation of sump strainers and other physical
modifications in Unit 1. In addition, the inspector reviewed setpoint changes to the
swapover point from the refueling water storage tank to the emergency recirculation
sump. The setpoint changes were approved by NRC before the modification was
completed. Changes to the containment coatings programs, latent debris programs,
and other programmatic changes, as committed, were not completed because of delays
in the final acceptance of test results for chemical and downstream effects.
At the time of the inspection, only 11 of 22 commitments have been fully completed.
Final review and acceptance of chemical and downstream effects will be completed by
the Office of Nuclear Reactor Regulation (NRR) at a later date. Since final acceptance
of the licensees commitments were not complete, the inspector evaluated the
recirculation sump modifications to the original design basis, Regulatory Guide 1.82,
Revision 0, ?Water Sources for Long-Term Recirculation Cooling Following a Loss-of-
Coolant Accident. Pending final submittal and acceptance of licensees commitments
to Generic Letter 2004-02. Temporary Instruction 166 for CPSES Units 1 and 2 will
remain open.
4OA6 Exit Meeting Summary
The inspector presented the inspection results of Temporary Instruction 2515/166 to
Mr. R. Flores, Site Vice President, and other members of the licensees management
staff at a pre-exit interview on March 14, 2007. The licensee's management
acknowledged the findings and observations presented. The inspector communicated
to the licensees management that a final exit will occur at a later date pending NRRs
final acceptance of the licensees commitments to Generic Letter 2004-02. In addition,
the inspector asked the licensee's management whether any materials examined during
the inspection should be considered proprietary. No proprietary information was
identified.
Enclosure
-2-
Enclosure
-3-
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel:
R. Flores, Site Vice President
S. Smith, Director, Site Engineering
T. Hope, Regulatory Performance
S. Maier, Design Engineering Analysis Manager
J. Meyer, Technical Support Manager
C. Feist, Design Engineer
J. Seawright, Regulatory Affairs
DOCUMENTS REVIEWED
4OA5 Other: NRC Temporary Instruction 2515/166
Calculations
NUMBER
TITLE
REVISION
ME-CA-0000-5066
Calculation of Minimum Flood Level in the Containment
Building Following a Large Break LOCA, Small Break
and MSLB
2
PCI-5472-S01
Structural Evaluation of the Emergency Sump Suction
Strainers
2
Evaluations and Engineering Reports
NUMBER
TITLE
REVISION/DATE
ER-119
Unit 2 GSI 191 Debris Source Term Confirmatory
Walkdown Report
0
ER-ME-118
DEBRIS SOURCE INVENTORY
CONFIRMATORY WALKDOWN
REPORT for Comanche Peak Steam Electric
Station - UNIT 1
0
ER-ME-123
GSI-191 Scoping Study Comanche Peak Steam
Electric Station Units 1 and 2
0
EVAL 2001-2201-
05-00
Sump Performance Analysis: Upstream Effects
08-01-2005
EVAL 2001-2201-
10-00
Sump Performance Analysis: Debris Generation
08-01-2005
EVAL 2001-2201-
12-00
Sump Performance Analysis: NPSH and Head
Loss
08-01-2005
Enclosure
-4-
Final Design Authorization
NUMBER
DESCRIPTION
REVISION/DATE
2002-1952-02-01
Modify the Radiation Barrier around Incore
Instrumentation Guide Tubes
1
2002-1952-03-01
Incorporate IDA for as-built configuration
1
2002-1952-04-01
Revise SK-0003 to incorporate as-built details for
the door
1
2005-3364-07-00
Remove the wire mesh cages from old Hot Tool
Room and Fuel Transfer Tube
0
Drawings
NUMBER
TITLE
REVISION/DATE
SFS-CP-GA-00
Comanche Peak Units 1 & 2 Sure-Flow Strainer
General Arrangement
4
SFS-CP-GA-01-
001
Comanche Peak Units 1 & 2
Sure-Flow Strainer General Notes
7
SFS-CP-GA-01-
002
Comanche Peak Units 1 & 2
Sure-Flow Strainer General Notes
7
SFS-CP-GA-02
Comanche Peak Units 1 & 2
Sure-Flow Strainer General Arrangement - Sump
2
5
SFS-CP-GA-03
Comanche Peak Units 1 & 2
Sure-Flow Strainer General Arrangement - Sump
1
5
SFS-CP-GA-04
Comanche Peak Units 1 & 2
Sure-Flow Strainer Sections & Details
3
SFS-CP-GA-05
Comanche Peak Units 1 & 2
Sure-Flow Strainer Plenum Box
3
SFS-CP-GA-06
Comanche Peak Units 1 & 2
Sure-Flow Strainer - Sump 2 Mounting Track
10
SFS-CP-GA-07
Comanche Peak Units 1 & 2
Sure-Flow Strainer - Sump 1 Mounting Track
10
SFS-CP-GA-09
Comanche Peak Units 1 & 2
Sure-Flow Strainer General Arrangement - Sump
Cover Assembly
3
SFS-CP-GA-10
Comanche Peak Units 1 & 2
Sure-Flow Strainer General Arrangement - Floor
Drain Strainer
2
Enclosure
-5-
Miscellaneous
NUMBER
DESCRIPTION
Revision/Date
Updated Response to Requested Information Part 2
3-31-2006
Updated Response to Requested Information Part 2
12-13-2006
Corrective Action Document
2005-003364-16-00