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{{#Wiki_filter:DukeKELVIN                                                                   CatawbaHENDERSON Nuclear Station MSite                                                                                   Vice President Carolinas Duke Energy Carolinas,LLC 4800 Concord Rd.
{{#Wiki_filter:DukeKELVIN HENDERSON Catawba Nuclear Station MSite Vice President Carolinas Duke Energy Carolinas, LLC 4800 Concord Rd.
York, SC 29745 803-701-4251 SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)
York, SC 29745 803-701-4251 SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED March 28, 2013                                                                 10 CFR 50.54(f)
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED March 28, 2013 10 CFR 50.54(f)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852


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==Reference:==
==Reference:==
: 1. NRC Letter, Request for Information Pursuantto Title 10 of the Code of FederalRegulations 50.54(o RegardingRecommendations 2.1, 2.3, and 9,3 of the Near-Term Task Force Review of Insights form the Fukushima Dai-lchi Accident, dated March 12, 2012
: 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(o Regarding Recommendations 2.1, 2.3, and 9,3 of the Near-Term Task Force Review of Insights form the Fukushima Dai-lchi Accident, dated March 12, 2012
: 2. EPRI Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012
: 2. EPRI Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012
: 3. NRC Letter, Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, "Seismic Walkdown Guidance",dated May 31, 2012
: 3. NRC Letter, Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, "Seismic Walkdown Guidance", dated May 31, 2012
: 4. Duke Energy's 180-Day Response to March 12, 2012, Request for Information Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights for the Fukushima Dai-IchiAccident SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)
: 4. Duke Energy's 180-Day Response to March 12, 2012, Request for Information Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights for the Fukushima Dai-Ichi Accident SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED www.duke-energy.com ron
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED www.duke-energy.com ron


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UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED


j - .A 4t SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)
j -
.A 4t SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission March 28, 2012 Page 3 xc:
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission March 28, 2012 Page 3 xc:
V.M. McCree, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 Eric J. Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13-H16M 11555 Rockville Pike Rockville, MD 20852-2738 J.H. Thompson, Project Manager U.S. Regulatory Commission One White Flint North, Mailstop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto NRC Senior Resident Catawba Nuclear Station Document Control Desk (Electronic Disk)
V.M. McCree, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 Eric J. Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13-H16M 11555 Rockville Pike Rockville, MD 20852-2738 J.H. Thompson, Project Manager U.S. Regulatory Commission One White Flint North, Mailstop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto NRC Senior Resident Catawba Nuclear Station Document Control Desk (Electronic Disk)
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UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED


CNC-1206.03-00-0203 Rev 0 Attachment 1 A Page 1 of 36 Attachment 1 Page 1 of 36 Unit I SWEL - 1 "Base List" The Catawba Unit 1 SWEL - 1 "base list" is a copy of the original IPEEE list for Unit 1, as recorded in Calculation CNC-1535.00-00-0005, rev. 0. A copy is provided as Attachment 1.
CNC-1206.03-00-0203 Rev 0 A Page 1 of 36 Page 1 of 36 Unit I SWEL - 1 "Base List" The Catawba Unit 1 SWEL - 1 "base list" is a copy of the original IPEEE list for Unit 1, as recorded in Calculation CNC-1535.00-00-0005, rev. 0.
A copy is provided as Attachment 1.


SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)
SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)
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UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED
UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED


Rev 0 CNC-1206.03-00-0203 A Page 1 of36 1
CNC-1206.03-00-0203 Rev 0 A Page 1 of36 Page 1 of 36 Unit I SWEL - 1 "Base List" The Catawba Unit 1 SWEL-1 "base list" is a copy of the original IPEEE list for Unit 1, as recorded in Calculation CNC-1535.00-00-0005, rev. 0. A copy is provided as Attachment 1.
Attachment Page 1 of 36 in
              - 1 "Base List"                                                         Unit 1, as recorded Unit I SWEL                                                 original IPEEE list for is a copy of the 1 SWEL-  1 "base list"                        as Attachment 1.
Catawba    Unit                                  is provided The                                rev. 0. A copy Calculation CNC-1535.00-00-0005,


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 2 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1 535.00-00-0005 Rev. 0 sht I of Lt Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study By:   *J, 13 .*               612L[t Ck. By:   JT         '
CNC-1206.03-00-0203 Rev 0 A Page 2 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1 535.00-00-0005 Rev. 0 sht I of Lt Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study By: *J, 13.*
Attachment 1 Page 2 of 36 PROBLEM STATEMENT:
612L[t Ck. By:
JT Page 2 of 36 PROBLEM STATEMENT:
NRC Generic Letter 88-20 requests nuclear plant licensees to perform Individual Plant Examinations for Extrernal Events (IPEEE) for several topics including seismic events. NUREG 1407 identifies acceptable methods for performing the Seismic IPEEE. The purpose of the seismic examination is to review the seismic margin of selected plant structures, components, and Iquipment for seismic vulnerabilities using a review level seismic event of
NRC Generic Letter 88-20 requests nuclear plant licensees to perform Individual Plant Examinations for Extrernal Events (IPEEE) for several topics including seismic events. NUREG 1407 identifies acceptable methods for performing the Seismic IPEEE. The purpose of the seismic examination is to review the seismic margin of selected plant structures, components, and Iquipment for seismic vulnerabilities using a review level seismic event of
    /0.30g peak ground acceleration. A seismic margir) assessment was already done of CNS Unit 2 for an EPRI trial plant review.yin 1986 and 1987. It used the criteria of EPRI NP-6041 and was documented in EPRI NP-6359 (see the reference list below). The method selected for the Catawba Seismic IPEEE consists of the EPRI Seismic Margins Methodology and the existing Catawba Probabilistic Risk Asse9!ment (PRA) along with the enhancements outlined in NUREG-1407, Use is made of work already done in the EPRI trial plant seismic margin assessment. Walkdown and evaluation documentation from that assessment is included along .with more recent walkdown and evaluation documentation in the attachments to this /
/0.30g peak ground acceleration. A seismic margir) assessment was already done of CNS Unit 2 for an EPRI trial plant review.yin 1986 and 1987. It used the criteria of EPRI NP-6041 and was documented in EPRI NP-6359 (see the reference list below). The method selected for the Catawba Seismic IPEEE consists of the EPRI Seismic Margins Methodology and the existing Catawba Probabilistic Risk Asse9!ment (PRA) along with the enhancements outlined in NUREG-1407, Use is made of work already done in the EPRI trial plant seismic margin assessment. Walkdown and evaluation documentation from that assessment is included along.with more recent walkdown and evaluation documentation in the attachments to this /
calculation. Walkdo-wns also serve the purpose of helping to validate the seismic portions of the Catawba PRA. The Seismic Review Team (SRT) for the walkdowns consisted of W.M. Hogan, D.A. Kaul, J.T.Gruber, and W.B/
calculation. Walkdo-wns also serve the purpose of helping to validate the seismic portions of the Catawba PRA. The Seismic Review Team (SRT) for the walkdowns consisted of W.M. Hogan, D.A. Kaul, J.T.Gruber, and W.B/
Shoemaker. All are registered professional engineers. The SRT for the earlier seismic margin assessment consisted of D.R. Kulla, W. B. /
Shoemaker. All are registered professional engineers. The SRT for the earlier seismic margin assessment consisted of D.R. Kulla, W. B. /
Shoemaker, B.F. Henley, and R.D. Campbell. All are registered professional engineers. No training was available at the time the earlier work was done.
Shoemaker, B.F. Henley, and R.D. Campbell. All are registered professional engineers. No training was available at the time the earlier work was done.
R. D. Campbell is a recognized industry expert in the area of seismic evaluations of nuclear power plants. He was the primary author of the EPRI seismic margins criteria document, Reference (1). The Catawba Seismic Margins Assessment as documented in Reference (3) is recognized throughout the industry and is referenced in NUREG 1407. Given the standards available at the time each of the two portions of the seismic review was done, the Seismic Review Team meets the requirements and intent of EPRI NP-6041 and NUREG 1407.
R. D. Campbell is a recognized industry expert in the area of seismic evaluations of nuclear power plants. He was the primary author of the EPRI seismic margins criteria document, Reference (1).
The Catawba Seismic Margins Assessment as documented in Reference (3) is recognized throughout the industry and is referenced in NUREG 1407. Given the standards available at the time each of the two portions of the seismic review was done, the Seismic Review Team meets the requirements and intent of EPRI NP-6041 and NUREG 1407.
This calculation and its attachments provide the documentation jor the seismic walkdown and evaluation for the CNS Seismic IPEEE. /
This calculation and its attachments provide the documentation jor the seismic walkdown and evaluation for the CNS Seismic IPEEE. /
The Safe Shutdown Equipment Lists (components to cover on walkdowns) 9      were provided by P. T. Farish in a letter of March 11, 1993, file no. CN-1 535.00 (copy in attachment to this catc.) .
The Safe Shutdown Equipment Lists (components to cover on walkdowns) were provided by P. T. Farish in a letter of March 11, 1993, file no. CN-9 1
535.00 (copy in attachment to this catc.).


CNC-1206.03-00-0203 Rev 0 A Page 3 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535.00-00-0005 Rev. 0 sht 2 of Lf Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study BCk.                                       By: *7~
CNC-1206.03-00-0203 Rev 0 A Page 3 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535.00-00-0005 Rev. 0 sht 2 of Lf Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study BCk.
Attachment 1 QA CONDITION                                                                   Page 3 of 36 This calculation is non QA Condition               /
By: *7~
DESIGN / ANALYTICAL METHOD This calcuation performs no design, and it is not used to support any design 7 basis designs. In the calculation attachments information gathered in seismic margin walkdowns is compiled, and evaluations are performed using the methods given in EPRI NP-6041. Any other method that may be used are documented where such methods are used in the attachments.
QA CONDITION Page 3 of 36 This calculation is non QA Condition /
APPLICABLE CODES AND STANDARDS EPRI NP-6041 and NUREG-1 407 are used. Where other codes and           /
DESIGN / ANALYTICAL METHOD This calcuation performs no design, and it is not used to support any design 7 basis designs. In the calculation attachments information gathered in seismic margin walkdowns is compiled, and evaluations are performed using the methods given in EPRI NP-6041.
Any other method that may be used are documented where such methods are used in the attachments.
APPLICABLE CODES AND STANDARDS EPRI NP-6041 and NUREG-1 407 are used. Where other codes and  
/
standards are recommended by these two publications such codes and standards are referenced.
standards are recommended by these two publications such codes and standards are referenced.
DESIGN INPUTS Evaluation inputs are identified as applicable in the attachments.
DESIGN INPUTS Evaluation inputs are identified as applicable in the attachments.
FSAR The FSAR does not address IPEEE. This calculation has no impact on the     7' FSAR.
FSAR The FSAR does not address IPEEE. This calculation has no impact on the 7' FSAR.
ASSUMPTIONS Structure and equipment qualification data in design documents were used to help evaluate seismic margin. Other assumptions are identified as applicable in the attachments.
ASSUMPTIONS Structure and equipment qualification data in design documents were used to help evaluate seismic margin. Other assumptions are identified as applicable in the attachments.
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CNC-1206.03-00-0203 Rev 0 A Page 4 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535,00-00-0005 Rev. 0 sht 3 of .1 Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study By: tA)gJXAý         i.ý   (,(2-Iqf   Ck. By:*fZ     ,/(;/4~
CNC-1206.03-00-0203 Rev 0 A Page 4 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535,00-00-0005 Rev. 0 sht 3 of.1 Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study By: tA)gJXAý i.ý
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SOURCES OF INFORMATION / REFERENCES (1) NUREG 1407, "Procedural and Submittal Guidance for the Individual Plant Examination of External Events," June, 1911 (2) EPRI NP 6041, "A Methodology for Assessment of Nuclear Plant Seismic Margin," Rev 0, Oct., 1988, Rev. 1,Aug., 1991 (3)EPRI NP-6359, Seismic Margin Assessment Margin Assessment of the Catawba Nuclear Station," April, 1989 (4)P. T. Farish letter to W. B. Shoemaker of March 11, 1993, IPEEE Safe Shutdown Equipment Lists, file CN-1535.00.
SOURCES OF INFORMATION / REFERENCES (1) NUREG 1407, "Procedural and Submittal Guidance for the Individual Plant Examination of External Events," June, 1911 (2) EPRI NP 6041, "A Methodology for Assessment of Nuclear Plant Seismic Margin," Rev 0, Oct., 1988, Rev. 1,Aug., 1991 (3)EPRI NP-6359, Seismic Margin Assessment Margin Assessment of the Catawba Nuclear Station," April, 1989 (4)P. T. Farish letter to W. B. Shoemaker of March 11, 1993, IPEEE Safe Shutdown Equipment Lists, file CN-1535.00.
Other sources of information and references are sited where appropriate in the attachments.
Other sources of information and references are sited where appropriate in the attachments.
CALCULATION The results of the walkdowns, evaluations and other backup information are provided in the attachments.
CALCULATION The results of the walkdowns, evaluations and other backup information are provided in the attachments.
CONCLUSION No significant areas of plant vulnerability were identified. Modification of the Diesel Generator Battery racks (and addition of spacers) was implemented largely as a result of the EPRI trial plant seismic margin assessment (NSMs CN-1 1161 and CN-20540) . One or two other minor improvements were made to the station which slightly reduced seismic vulnerabilties. These improvements are noted where appropriate in the /
CONCLUSION No significant areas of plant vulnerability were identified. Modification of the Diesel Generator Battery racks (and addition of spacers) was implemented largely as a result of the EPRI trial plant seismic margin assessment (NSMs CN-1 1161 and CN-20540). One or two other minor improvements were made to the station which slightly reduced seismic vulnerabilties. These improvements are noted where appropriate in the  
/
calculation attachments.
calculation attachments.
Attachment 1 Page 4 of 36
Page 4 of 36


CNC-1 206.03-00-0203 Rev 0 Attachment 1lA Page 5 of 36
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CNC-1 206.03-00-0203 Rev 0 Attachment 1A Page 7 of 36 A-TLA     t~vvc-N T         I   Tro     Ct) r 133 SO-, 00- 0     -0 0S&sect; pAG.E 2.
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March 11, 1993 Catawba Nuclear Station Re:   Catawba Nuclear Station, Units 1 & 2 Individual Plant Examination - External Events Safe Shutdown Equipment Lists File: CN-1535.00 Please find attached for your use and information a copy of the safe shutdown equipment lists (SSELs) for Unit I as well as the lists of equipment required for the containment performance evaluation of Units I & 2.
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March 11, 1993 Catawba Nuclear Station Re:
Catawba Nuclear Station, Units 1 & 2 Individual Plant Examination - External Events Safe Shutdown Equipment Lists File: CN-1535.00 Please find attached for your use and information a copy of the safe shutdown equipment lists (SSELs) for Unit I as well as the lists of equipment required for the containment performance evaluation of Units I & 2.
Questions regarding the equipment selection may be directed to me at 382-6755.
Questions regarding the equipment selection may be directed to me at 382-6755.
P. T. Parish, Engineer I      Nu clear Engineering - Severe Accident Analysis Nuclear Services Attachment cc:   P.M. Abraham R. W. McAuley H. D. Brewer R. C. Bucy (CNS)
P. T. Parish, Engineer Nu clear Engineering - Severe Accident Analysis Nuclear Services Attachment cc:
P.M. Abraham R. W. McAuley H. D. Brewer R. C. Bucy (CNS)
R. S. Bondurant (CNS)
R. S. Bondurant (CNS)
J. H. Knuti (CNS)
J. H. Knuti (CNS)
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CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 9 of 36 Ei 004 GENERIC LETTER 88-20; SUPPLEMENT 4 INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT I In the NRC policy statement on severe accidents, issued on August 8, 1985, the Commission concluded that existing nuclear power plants pose no undue risks to the public health and safety.
CNC-1206.03-00-0203 Rev 0 A Page 9 of 36 Ei 004 GENERIC LETTER 88-20; SUPPLEMENT 4 INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT I In the NRC policy statement on severe accidents, issued on August 8, 1985, the Commission concluded that existing nuclear power plants pose no undue risks to the public health and safety.
The Commission also concluded that systematic plant-specific examinations are beneficial in identifying plant vulnerabilities to severe accidents that could be fixed with low cost improvements. The staff issued Generic Letter 88-20 on 11/23/88, requesting that each Licensee conduct an individual plant examination (IPE) for internally initiated events. To satisfy the IPE requirement, Duke utilized the Catawba PRA report, which included the analysis of internal and external events. The Catawba IPE was submitted to the NRC in September 1992.
The Commission also concluded that systematic plant-specific examinations are beneficial in identifying plant vulnerabilities to severe accidents that could be fixed with low cost improvements. The staff issued Generic Letter 88-20 on 11/23/88, requesting that each Licensee conduct an individual plant examination (IPE) for internally initiated events. To satisfy the IPE requirement, Duke utilized the Catawba PRA report, which included the analysis of internal and external events. The Catawba IPE was submitted to the NRC in September 1992.
Supplement 4 to G.L. 88-20 was issued on 6/28/91 and requested a systematic, individual plant examination for severe accidents initiated by external events (IPEEE). Among the events to be assessed was the plant's response to a seismic event.
Supplement 4 to G.L. 88-20 was issued on 6/28/91 and requested a systematic, individual plant examination for severe accidents initiated by external events (IPEEE). Among the events to be assessed was the plant's response to a seismic event.
There are two acceptable methods for responding to the IPEEE, as identified in NUREG-1407 and EPRI NP-6041, Rev. 1; (1) use of the seismic PRA and (2) the Seismic Margin Assessment S     (SMA) method. In addition, NUREG-1407 includes an assessment to identify vulnerabilitles that involve the early failure of containment functions. In order to determine the seismic acceptability of the plant, walkdowns will be conducted of the various systems required to achieve safe shutdown and maintain containment performance, To this end, a listing of the various components and structures required for safe shutdown and containment performance will be prepared for use by the Catawba Seismic Review Team (SRI) to carry out the plant walkdowns.
There are two acceptable methods for responding to the IPEEE, as identified in NUREG-1407 and EPRI NP-6041, Rev. 1; (1) use of the seismic PRA and (2) the Seismic Margin Assessment S
(SMA) method. In addition, NUREG-1407 includes an assessment to identify vulnerabilitles that involve the early failure of containment functions.
In order to determine the seismic acceptability of the plant, walkdowns will be conducted of the various systems required to achieve safe shutdown and maintain containment performance, To this end, a listing of the various components and structures required for safe shutdown and containment performance will be prepared for use by the Catawba Seismic Review Team (SRI) to carry out the plant walkdowns.
The purpose of this document is to identify the various components and structures required for safe shutdown and containment performance after a seismic event and to detail the selection process employed. The listings generated herein will be used by the Catawba SRT in conducting walkdowns to assess the plant's response to a seismic event.
The purpose of this document is to identify the various components and structures required for safe shutdown and containment performance after a seismic event and to detail the selection process employed. The listings generated herein will be used by the Catawba SRT in conducting walkdowns to assess the plant's response to a seismic event.
Methods of 1PEEE Resolati~o~
Methods of 1PEEE Resolati~o~
As mentioned above, there are two acceptable methods for IPEEE resolution. These are detailed below, Final selection of the components and structures are based upon these two methods.
As mentioned above, there are two acceptable methods for IPEEE resolution. These are detailed below, Final selection of the components and structures are based upon these two methods.
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CNC-1206.03-00-0203 Rev 0 A Page 10 of 36 Catawba has previously generated a seismic PRA as part of its formal PRA report.
CNC-1206.03-00-0203 Rev 0 A Page 10 of 36 Catawba has previously generated a seismic PRA as part of its formal PRA report.
Iidtially, seismic hazard curves for peak acceleration were developed (Catawba currently uses hazard curves developed by EPRI using the Seismicity Owners Group methodology for seismic hazards analysis of nuclear power plant Sites in the central and eastern U.S.).
Iidtially, seismic hazard curves for peak acceleration were developed (Catawba currently uses hazard curves developed by EPRI using the Seismicity Owners Group methodology for seismic hazards analysis of nuclear power plant Sites in the central and eastern U.S.).
Next, an event tree was generated to characterize the plant response to a seismic event.
Next, an event tree was generated to characterize the plant response to a seismic event.
With the subsequent core melt sequences identified, a fault tree was then produced to determine the failure sequences (cut sets) of interest. Using previously estimated fragilitics of key components and structures, the conditional probability of failure as a function of ground acceleration was ascertained. Finally, a resulting set of dominant accident sequences was developed based upon a convolution of the fragilities, fault tree cut sets, and the seismic hazard curve.
With the subsequent core melt sequences identified, a fault tree was then produced to determine the failure sequences (cut sets) of interest. Using previously estimated fragilitics of key components and structures, the conditional probability of failure as a function of ground acceleration was ascertained.
The plant component fragilities used in the analysis were calculated by Structural Mechanics Associates. The walkdowns by the SRT will complement these fragility estimates.
Finally, a resulting set of dominant accident sequences was developed based upon a convolution of the fragilities, fault tree cut sets, and the seismic hazard curve.
The plant component fragilities used in the analysis were calculated by Structural Mechanics Associates.
The walkdowns by the SRT will complement these fragility estimates.
Thus, the seismic PRA method primarily identifies areas of seismic vulnerability by determining a set of dominant accident seluences and components.
Thus, the seismic PRA method primarily identifies areas of seismic vulnerability by determining a set of dominant accident seluences and components.
: 2)   SMA         bMthd-The SMA method, as described in NP-6041, defines an earthquake level (or a 'margin')
: 2)
above the design basis earthquake for which the ability to safely shut the plant down can be demonstrated with high confidence in a cost-effective manner. It is the NRC staffs judgment that the use of a 0.3g review level earthquake for most nuclear plant sites in the central and eastern U.S. would serve to meet the objectives of the IPEEE. The SMA process is based upon a systems "success path" approach that defines and evaluates the capacity of the components required to bring the plant to a safe shutdown condition (either hot or cold) for 72 hours (further assumptions used in the analysis are given in the "Basic Assumptions" section of this report). Since several possible success paths may exist, cognizant engineering and operations personnel are needed for proper selection,. Once chosen, a walkdown of the selected shutdown paths will determine whether the components and structures identified therein are in compliance with the 'seismic margin'.
SMA bMthd-The SMA method, as described in NP-6041, defines an earthquake level (or a 'margin')
above the design basis earthquake for which the ability to safely shut the plant down can be demonstrated with high confidence in a cost-effective manner.
It is the NRC staffs judgment that the use of a 0.3g review level earthquake for most nuclear plant sites in the central and eastern U.S. would serve to meet the objectives of the IPEEE. The SMA process is based upon a systems "success path" approach that defines and evaluates the capacity of the components required to bring the plant to a safe shutdown condition (either hot or cold) for 72 hours (further assumptions used in the analysis are given in the "Basic Assumptions" section of this report). Since several possible success paths may exist, cognizant engineering and operations personnel are needed for proper selection,.
Once chosen, a walkdown of the selected shutdown paths will determine whether the components and structures identified therein are in compliance with the 'seismic margin'.
Furthermore, the NRC defines Catawba as a 'focused-scope' plant requiring an evaluation of low-seismic-ruggedness relays in the shutdown paths. The relays associated with the shutdown paths will be reviewed against a 'bad actors' list (from EPRI NP-7148SL). The related power supply cabinets will also be reviewed for seismic ruggedness.
Furthermore, the NRC defines Catawba as a 'focused-scope' plant requiring an evaluation of low-seismic-ruggedness relays in the shutdown paths. The relays associated with the shutdown paths will be reviewed against a 'bad actors' list (from EPRI NP-7148SL). The related power supply cabinets will also be reviewed for seismic ruggedness.
Method of Selection for Safe Shutdown Eo5unm.n A review of the current Catawba PRA report was conducted to determine those components and systems considered as important to safe plant shutdown from a PRA perspective. The review included the Seismic fault tree (PRA report Section 3.2) and the Small-Break LOCA fault tree (PRA report Section 2.3) along with their respective transfers to other system trees. The individual shutdown system fault trees were also reviewed to obtain other key components,
Method of Selection for Safe Shutdown Eo5unm.n A review of the current Catawba PRA report was conducted to determine those components and systems considered as important to safe plant shutdown from a PRA perspective. The review included the Seismic fault tree (PRA report Section 3.2) and the Small-Break LOCA fault tree (PRA report Section 2.3) along with their respective transfers to other system trees.
                                              ,".                                                          Attachment 1 Page 10 of 36
The individual shutdown system fault trees were also reviewed to obtain other key components, Page 10 of 36


CNC-1 206.03-00-0203 Rev 0 Attachment 1A Page 11 of 36 power sources, etc. The components and stnictures of concern to the seismic PRA are so noted in the resulting equipment lists.                                                                 U 1   -,
CNC-1 206.03-00-0203 Rev 0 A Page 11 of 36 power sources, etc. The components and stnictures of concern to the seismic PRA are so noted in the resulting equipment lists.
Next, in accordance with NP-6041, two success paths (primary & alternate) per the SMA approach were selected to perform each of the following shutdown functions:
U 1 Next, in accordance with NP-6041, two success paths (primary & alternate) per the SMA approach were selected to perform each of the following shutdown functions:
o     Reactivity Control o     RCS Pressure and Inventory Control o     Decay Heat Removal The Catawba Unit 2 SMA pilot study (EPR NIP-6359) was also used as a guide for success path selection, All the primary and alternate 'front-liue' systems required to execute each shutdown function are shown in Table I along with their 'support' systems.
o Reactivity Control o
RCS Pressure and Inventory Control o
Decay Heat Removal The Catawba Unit 2 SMA pilot study (EPR NIP-6359) was also used as a guide for success path selection, All the primary and alternate 'front-liue' systems required to execute each shutdown function are shown in Table I along with their 'support' systems.
With the proper front-line and supporting systems identified, engineers traced out the success paths on the respective system flow diagrams, relying upon their knowledge and experience.
With the proper front-line and supporting systems identified, engineers traced out the success paths on the respective system flow diagrams, relying upon their knowledge and experience.
Individual components and instruments were noted and listed. Several components were designated as "pressure boundary integrity only" which signifies components which ame part of the pressure boundary but do not perform an active function.
Individual components and instruments were noted and listed.
Several components were designated as "pressure boundary integrity only" which signifies components which ame part of the pressure boundary but do not perform an active function.
Method of Selection for Con..tainrnent PerfoQMna.
Method of Selection for Con..tainrnent PerfoQMna.
The equipment and structures necessary to support containment performance were selected per guidance from NUREG-1407. The PRA report was used to generate an initial listing and included the Seismic Containment Safeguards fault tree (PRA report Section 3.2) and the Containment Safeguards fault tree (PRA report Chapter 4) along with their respective transfers to other system trees. The individual system fault trees (including the Containment Isolation fault tree) were also reviewed to obtain other key components, power sources, etc.
The equipment and structures necessary to support containment performance were selected per guidance from NUREG-1407.
The PRA report was used to generate an initial listing and included the Seismic Containment Safeguards fault tree (PRA report Section 3.2) and the Containment Safeguards fault tree (PRA report Chapter 4) along with their respective transfers to other system trees. The individual system fault trees (including the Containment Isolation fault tree) were also reviewed to obtain other key components, power sources, etc.
Following their preparation, the initial equipment lists were reviewed by licensed operators for sound selection methodology and conformance to existing procedures. Other systems engineers were included as necessary to complete the review. The resulting comments were incorporated and the finalized safe shutdown and containment performance equipment lists are given in Tables 2 through 5. A diskette with these tables will be given to the SRT so that walkdown information can be added per reporting requirements.
Following their preparation, the initial equipment lists were reviewed by licensed operators for sound selection methodology and conformance to existing procedures. Other systems engineers were included as necessary to complete the review. The resulting comments were incorporated and the finalized safe shutdown and containment performance equipment lists are given in Tables 2 through 5. A diskette with these tables will be given to the SRT so that walkdown information can be added per reporting requirements.
: 1)     Per IPEEE guidelines, the plant undergoes a seismic event and loses off-site power. A small-break LOCA (I in,) is also incurred. The plant must maintain shutdown status for 72 hours.
: 1)
: 2)     Plant shutdown is conducted using cold leg injection. For a small-break LOCA. the cold leg accumulators are excluded since this is a relatively controlled shutdown situation.
Per IPEEE guidelines, the plant undergoes a seismic event and loses off-site power. A small-break LOCA (I in,) is also incurred. The plant must maintain shutdown status for 72 hours.
: 2)
Plant shutdown is conducted using cold leg injection. For a small-break LOCA. the cold leg accumulators are excluded since this is a relatively controlled shutdown situation.
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CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 12 of 36 Li .0
CNC-1206.03-00-0203 Rev 0 A Page 12 of 36 Li  
: 3)     Assume initial suction is from the RWST (rather than through the Volume Control Tank) until RCS temperature and pressure are low enough to initiate RHR.
.0
: 4)     Aswrie manual valves, check valves, non-active relief valves, and piping are seismically rugged-
: 3)
: 5)   The analysis is based upon bringing the plant to hot shutdown with the option of going to cold shutdown with RHR.
Assume initial suction is from the RWST (rather than through the Volume Control Tank) until RCS temperature and pressure are low enough to initiate RHR.
: 6)   Instead of the normal Containment Spray System (NS), the RHR Auxiliary Spray headers will be used to mitigate any containment pressure increases.
: 4)
Aswrie manual valves, check valves, non-active relief valves, and piping are seismically rugged-
: 5)
The analysis is based upon bringing the plant to hot shutdown with the option of going to cold shutdown with RHR.
: 6)
Instead of the normal Containment Spray System (NS), the RHR Auxiliary Spray headers will be used to mitigate any containment pressure increases.
References
References
: 1)   NUREG- 1407; "Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities"
: 1)
: 2)     EPRI NP-6041, Rev. 1; "A Methodology for Assessment of Nuclear Power Plant Seismic Margin"
NUREG-1407; "Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities"
: 3)     EPRI NP-7148SL;         "Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality"
: 2)
: 4)     EPRI NP-6359; "Seismic Margin Assessment o' the Catawba Nuclear Station"
EPRI NP-6041, Rev. 1; "A Methodology for Assessment of Nuclear Power Plant Seismic Margin"
: 5)     Catawba Flow Diagrams -
: 3)
CN-1553-1.0, -1.1; NC System CN-1554--1.0, -1.1, -1.2. -1.5, -1.6, -1.7; NV System CN-1557 (2557)-l.0; VX System CN-1557-2.0; VZ System CN- 1561 series: ND System CN-1562-l.0, -1.1, -1.2, -1.3; NI System CN-1563-1.0; NS System CN-1571-1,0; FW System CN-1573-1.0, -1.1, -2.0, -2.1, -2.2; KCSystem CN-1574- 1.0, -1.,-1.2, -1.4, -2.0, -2.1,-2.4, -2.5; RN System CN-1577-1.0,-1.1,4-.2,-1.3; VASystem CN-1578-1,0, -1.1, -1.2, -1.4, -1.5; VC System CN-1578-2,x series; YCSystem CN-1579-1.0; VD System CN-1591-I,I; CFSystem CN-1592 series; CA System CN-1593-1.0, -1.1, -1.2, 1..3, -1.7 series; SM, SV Systems CN-1609 series; D/G Support Systems (KD, LD, FD, VC, VN)
EPRI NP-7148SL; "Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality"
: 6)   Catawba Final Safety Analysis Report (FSAR); dated 10/91
: 4)
,    7)   Catawba Probabilistic Risk Assessment Report; dated 9/22/92
EPRI NP-6359; "Seismic Margin Assessment o' the Catawba Nuclear Station"
::::'Attachment                                 Page 12 of 361
: 5)
Catawba Flow Diagrams -
CN-1553-1.0, -1.1; NC System CN-1554--1.0, -1.1, -1.2. -1.5, -1.6, -1.7; NV System CN-1557 (2557)-l.0; VX System CN-1557-2.0; VZ System CN-1561 series: ND System CN-1562-l.0, -1.1, -1.2, -1.3; NI System CN-1563-1.0; NS System CN-1571-1,0; FW System CN-1573-1.0, -1.1, -2.0, -2.1, -2.2; KCSystem CN-1574-1.0, -1.,-1.2, -1.4, -2.0, -2.1,-2.4, -2.5; RN System CN-1577-1.0,-1.1,4-.2,-1.3; VASystem CN-1578-1,0, -1.1, -1.2, -1.4, -1.5; VC System CN-1578-2,x series; YCSystem CN-1579-1.0; VD System CN-1591-I,I; CFSystem CN-1592 series; CA System CN-1593-1.0, -1.1, -1.2, 1..3, -1.7 series; SM, SV Systems CN-1609 series; D/G Support Systems (KD, LD, FD, VC, VN)
: 6)
Catawba Final Safety Analysis Report (FSAR); dated 10/91
: 7)
Catawba Probabilistic Risk Assessment Report; dated 9/22/92
::::'Attachment 1
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CNC- 1206.03-00-0203 Rev 0 Attachment 1A Page 13 of 36
CNC-1206.03-00-0203 Rev 0 A Page 13 of 36
                                                                                              @I Ges
@I Ges Several individuals were involved with the preparation and review of this report; however, those primarily responsible are listed below:
.      Several individuals were involved with the preparation and review of this report; however, those primarily responsible are listed below:
Name
Name                                 )YorkAM Paul T. Farish                   Nuclear Services / Nuclear Engineering William B. Shoemaker              Catawba / Civil Engineering Russell C. Bucy                  Catawba / Mechanical Engineering R. Stuart Bondurant              Catawba / Electrical Engineering John -i, Knuti                    Catawba / Operations 19 Attachment 1 Page 13 of 36
)YorkAM Paul T. Farish William B. Shoemaker Russell C. Bucy R. Stuart Bondurant John -i, Knuti Nuclear Services / Nuclear Engineering Catawba / Civil Engineering Catawba / Mechanical Engineering Catawba / Electrical Engineering Catawba / Operations 19 Page 13 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 14 of 36 TABLE 1-                                             609 LISTING OF PRIMARY & ALTERNATE StHUTDOWN PATHS 0       Reactivity Control         -
CNC-1206.03-00-0203 Rev 0 A Page 14 of 36 TABLE 1-609 LISTING OF PRIMARY & ALTERNATE StHUTDOWN PATHS 0
Reactivity Control -
Primary Path:
Primary Path:
Front-line System - Reactor Protection System (control rod insertion / Reactor Trip Breakers)
Front-line System - Reactor Protection System (control rod insertion / Reactor Trip Breakers)
Support Systems - None Alternate Path:
Support Systems - None Alternate Path:
Front-line Systems - NV, NI (emergency boration flowpath), FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC. Vz, YC o       RCS Pressure and Inventory Control-
Front-line Systems - NV, NI (emergency boration flowpath), FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC. Vz, YC o
)               Primary Path:
RCS Pressure and Inventory Control-
)
Primary Path:
Front-line Systems & Components - CA (Motor-Driven Pumps), SO PORVs, Main Steam Isolation Valves, SG Safety Relief Valves, NV, NI (not required for inventory control for 1" SBLOCA). FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, Vz, YC Alternate Path:
Front-line Systems & Components - CA (Motor-Driven Pumps), SO PORVs, Main Steam Isolation Valves, SG Safety Relief Valves, NV, NI (not required for inventory control for 1" SBLOCA). FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, Vz, YC Alternate Path:
Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg accumulators for PORV actuation)
Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg accumulators for PORV actuation)
Support Systems - RN, KC, Diesel Generators & supporting systems *; VA, VC, VZ, YC The following systems are assumed to be used for all DIG support functions:
Support Systems - RN, KC, Diesel Generators & supporting systems *; VA, VC, VZ, YC The following systems are assumed to be used for all DIG support functions:
FD, KD, LD, VD, VG, VN
FD, KD, LD, VD, VG, VN Page 14 of 36
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CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 15 of 36 TABLE I (cont.)-                                   ~h ~ (3 d         LISTING OF PRIMARY & ALTERNATE SHUTDOWN PATHS 0       Decay Heat Removal           -
CNC-1206.03-00-0203 Rev 0 A Page 15 of 36 TABLE I (cont.)-
~h  
~ (3 d
LISTING OF PRIMARY & ALTERNATE SHUTDOWN PATHS 0
Decay Heat Removal -
Primary Path:
Primary Path:
Front-line Systems & Components - CA (Motor-Driven Pumps). SG PORVs, ND (if cold shutdown is needed)
Front-line Systems & Components - CA (Motor-Driven Pumps). SG PORVs, ND (if cold shutdown is needed)
Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, VZ, YC Alternate Path:
Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, VZ, YC Alternate Path:
Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg acctnulators for PORV actuation), ND (if cold shutdown is needed)
Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg acctnulators for PORV actuation), ND (if cold shutdown is needed)
Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, Vz, YC The following systems are assumed to be used for all DIG support functions:
Support Systems - RN, KC, VC, Vz, YC Diesel Generators & supporting systems *, VA, The following systems are assumed to be used for all DIG support functions:
FD, KD, LD, VD, VG, VN IJ IJ 1:.11.)                                                                         Attachment 1 Page 15 of 36
FD, KD, LD, VD, VG, VN IJ IJ 1:.1 1.)
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CNC-1206.03-00-0203 Rev 0 Attachment IA Page 16 of 36 TABLE 2 .                                               I rC.I.I MECHANICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN
CNC-1206.03-00-0203 Rev 0 Attachment IA Page 16 of 36 TABLE 2.
('B' tro!n components are shown In parentheses. A detailed wolkdown of these components is not necessary if the 'B' train configuration Is simllar to he 'A train. I
I rC.I.I MECHANICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN
                                                    -_Line                     Included In           Press. bndry.
('B' tro!n components are shown In parentheses. A detailed wolkdown of these components is not
CA SYSTEM COMPONENTS                         Size (in.)         Seismic PRA           Integrity onty AO 6 A56     -(40)             ____4                           _
)
AOV     1CA60   (44)                                       4       _        ___-                  _
9 necessary if the 'B' train configuration Is simllar to he 'A train. I
MOV ICA7A                                             !      10                                           x___
-_Line Included In Press. bndry.
MOV ICAllA           (9B)                                   10                                           X MOV ICA15A (18B)                                             6                                                     ,
CA SYSTEM COMPONENTS Size (in.)
MOV 1CA,54B (38A)                                             4                                           x X_
Seismic PRA Integrity onty AO 6 A56  
MOV 1CA58A (42B)                                             4                                                       ....
-(40)
MOV 1CA62A (468)                                             4                   _      _                    __
____4 AOV 1CA60 (44) 4 MOV ICA7A 10 x___
MOV 1CA66B (50A)                                             4                                           x MOV ICA174                     -                          .8                                             x           -__
MOV ICAllA (9B) 10 X
MOV     1CA175                                               8                             ._X_,._
MOV ICA15A (18B) 6 MOV 1CA,54B (38A) 4 x
AUTO.-RECIRC. VALVE 1CA27 (32)                                     ]
X_
AUTO.-RECIRC. VALVE 1CA20                                                                     --.
MOV 1CA58A (42B) 4 MOV 1CA62A (468) 4 MOV 1CA66B (50A) 4 x
TURBINE DRIVEN PUMP 1                                                               X
MOV ICA174  
)  TDP TURBINE LUBE OIL COOLER MOTOR DRIVEN PUMP IA (18)
.8 x
UPPER SURGE TANK                                                                     X CONDENSER HOTWELL                                                                   x CONDENSATE STORAGE TANK                                                             x The following Unit I components were included on the Unit 2 walkdown:
MOV 1CA175 8  
MOV ICAB5B                                                               __
._X_,._
MOV ICA116A HYDRAULIC VLV 1CF33 HYDRAULIC VLV 1CF42 HYDRAULIC VLV 1CF51                                                                                                 '
AUTO.-RECIRC. VALVE 1CA27 (32)  
HYDRAULIC VLV ICF6*                                 I               --
]
DIESEL GENERATOR AND SUPPORTING                       Line             Included In           Press. bndry.
AUTO.-RECIRC. VALVE 1CA20 TURBINE DRIVEN PUMP 1 X
COMPONENTS                           Size (In.)         Seismic PRA           lntegrity on.y__
TDP TURBINE LUBE OIL COOLER MOTOR DRIVEN PUMP IA (18)
DIESEL GENERATOR IA (1B)                                                           x 9 SOLENOID VALVE 1FD22 (62)                                   2 FD D/G FUEL OIL FILTER 1A 01B)                                                                                               -i Page 1 IJ I..                                                                                                     Attachment 1 Page 16 of 36
UPPER SURGE TANK X
CONDENSER HOTWELL x
CONDENSATE STORAGE TANK x
The following Unit I components were included on the Unit 2 walkdown:
MOV ICAB5B MOV ICA116A HYDRAULIC VLV 1CF33 HYDRAULIC VLV 1CF42 HYDRAULIC VLV 1CF51 HYDRAULIC VLV ICF6*
I DIESEL GENERATOR AND SUPPORTING Line Included In Press. bndry.
COMPONENTS Size (In.)
Seismic PRA lntegrity on.y__
DIESEL GENERATOR IA (1B) x SOLENOID VALVE 1 FD22 (62) 2 FD D/G FUEL OIL FILTER 1A 01B)
-i Page 1 IJ I..
Page 16 of 36


CNC-1206.03-00-0 2 0 3 Rev 0 Attachment 1A Page 17 of 36 TABLE 2 -                                          fil oi-l DIESEL GENERATOR AND SUPPORTING                   .*U--_ ine                 Included In         Press. bndry.,
CNC-1206.03-00-0 2 0 3 Rev 0 A Page 17 of 36 fil oi-l TABLE 2 -
COMPONENTS (con1.)                           Inize (in.)               mic PRA FD   DIG FUEL OIL DAY TANK IA(1B) 013).                                                                        ..    ......
DIESEL GENERATOR AND SUPPORTING  
I-D D/G FUEL OIL PUMP STRAINER IA (1 B)
.*U--_ ine Included In Press. bndry.,
FD   D/G FUEL OIL STORAGE TANKS 1A1, 1A2 (111, 1B2)
COMPONENTS (con1.)
FD   DI.G_ FUEL OIL PUMP IA (0B)                                         -I.
Inize (in.)
mic PRA FD DIG FUEL OIL DAY TANK IA(1B) 013).
I-D D/G FUEL OIL PUMP STRAINER IA (1 B)
FD D/G FUEL OIL STORAGE TANKS 1A1, 1A2 (111, 1B2)
FD DI.G_ FUEL OIL PUMP IA (0B)  
-I.
KD D/G ENGINE JACKET WATER COOLER 1A (IB)
KD D/G ENGINE JACKET WATER COOLER 1A (IB)
KD D/G ENGINE JACKET WATER CIRC. PUMP IA (18)                                                   /
KD D/G ENGINE JACKET WATER CIRC. PUMP IA (18)  
/
KD D/G ENGINE JACKET WATER STANDPIPE IA (18)
KD D/G ENGINE JACKET WATER STANDPIPE IA (18)
AOVTLD4       (34)     ________                                  3       _          ____
AOVTLD4 (34) 3 AOV ILD27 (57)
AOV     ILD27 (57)                                                             __3_       _
__3_
SOLENOID VLV ILD122 (123)                                         2                                         x LD D/G GOVERNOR LUBE OIL COOLER                         -    -                                                          _-
SOLENOID VLV ILD122 (123) 2 x
LD D/G LUBE OIL FILTER )A (B)>                                                                     _
LD D/G GOVERNOR LUBE OIL COOLER LD D/G LUBE OIL FILTER )A (B)>
LD D/G LUBE OIL COOLER IA (I)
LD D/G LUBE OIL COOLER IA (I)
LD D/G LUBE OIL STRAINER IAI (1BI) & 1A2 (iB2)                               __
LD D/G LUBE OIL STRAINER IAI (1BI) & 1A2 (iB2)
UDD/G LUBE OILSUMP TANK IA (11)                                                 _      _  _                  __
UDD/G LUBE OILSUMP TANK IA (11)
LG D/G ENGINE LUBE OIL PUMP IA (1 B)                                                   _
LG D/G ENGINE LUBE OIL PUMP IA (1 B)
VD ELECTRO-HYDRAUUC DAMPER IDSF-D-1 (7) __                                                                    _
VD ELECTRO-HYDRAUUC DAMPER IDSF-D-1 (7)
VD EI.ECTRO-HYDRAULIC DAMPER 1DSF-D-2 (8)
VD EI.ECTRO-HYDRAULIC DAMPER 1DSF-D-2 (8)
VD ELECTRO-HYDRAULIC DAMPER 1DSF-D-3 (9)                                       ____
VD ELECTRO-HYDRAULIC DAMPER 1DSF-D-3 (9)
VD ELECTRO-HYDRAUUC DAMPER 1DSF-D-4 (10)))-_
VD ELECTRO-HYDRAUUC DAMPER 1DSF-D-4 (10) ))-_
)1 DIESEL BLDG. VENTILATION FANS I A1, 1A2 (0B1,81 B2)._
DIESEL BLDG. VENTILATION FANS I A1, 1 A2 (0B1,81 B2)._
SOLENOID VALVE 1VG25 (69)                                                 _                                              __
SOLENOID VALVE 1 VG25 (69)
SOLENOID VALVE IVG26 (70)                                         3 SOLENOID VALVE IVG27 (71)                                         3 SOLENOID VALVE 1VG28 (72)                                         3     _            _                            _  ..
SOLENOID VALVE IVG26 (70) 3 SOLENOID VALVE IVG27 (71) 3 SOLENOID VALVE 1VG28 (72) 3 VG D/G ENGINE STARTING AIR TANKS 1AI, IA2 (181, 132)
VG D/G ENGINE STARTING AIR TANKS 1AI, IA2 (181, 132)
VN D/G ENGINE ITWAKE AIR FILTERS IA 1, 1A2 (1B I 182)
VN D/G ENGINE ITWAKE AIR FILTERS IA 1, 1A2 (1BI 182)
VN D/G ENGINE INTAKE AIR SILENCERS IAl. 1A2 (11. 1B2)
VN D/G ENGINE INTAKE AIR SILENCERS IAl. 1A2 (11. 1B2)
VN D/G ENGINE EXHAUSTSILENCER WA,IA2 (181, 182)
VN D/G ENGINE EXHAUSTSILENCER WA, IA2 (181, 182)
YVN D/G ENGINE AFTERCOOLERS ]A, 1A2 (111, 1152)
YVN D/G ENGINE AFTERCOOLERS ]A, 1A2 (111, 1152)
VN D/G ENGINE TURBO-CHARGER WA,1A2 (113, 1132)                                 _
VN D/G ENGINE TURBO-CHARGER WA, 1A2 (113, 1132)  
                                                                  .. _Une         Itncluded In         Press. bndry. __
.. _Une I tncluded In Press. bndry. __
FW SYSTEM COMPONENTS                     -      Size (In.),       Seismic PRA           Integrity only MOV     lIA     (32B)                                           4...                         ._-
FW SYSTEM COMPONENTS Size (In.),
MOV 1FW27A (558)                                                 12     _    _
Seismic PRA Integrity only MOV lIA (32B) 4...
MOV 1FW33A (498)_                                                 2           ___,                                      ----
MOV 1FW27A (558) 12 MOV 1FW33A (498)_
9 RWST (REFUEUNG WATER STORAGE TANK)                           _                          X Page 2 ID 1-           ":.. .. ....
2 2 RWST (REFUEUNG WATER STORAGE TANK)
                                                  .:it   1 : I 1. "
X
1                                                                                          Attachment 1 Page 17 of 36
)1 9
Page 2 ID 1-1
...:it 1 : I.1 "
Page 17 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 18 of 36 TABLE 2 -                                      ~I &i:~
CNC-1206.03-00-0203 Rev 0 A Page 18 of 36
KC SSE           _OPNN ______          Une         Included In     Pross. bndry.
~I &i:~
SYSTEM COMPONENTS               Size (in.)     Seismic PRA I   integrity only   _
TABLE 2 -
q  AqV 1KC57A       (828)                           12 AOV 1KCD29                                         2 MOV IEKCA (2B)                                   20                                         -
KC SSE
MOV 1KC3A (18B)                                   10 MOV IKCSOA (53B)                                 20 MOV 1KC51A (548)                                 4                               -X MOV IKC56A (818)                                 16 MOV IKC230A (2280)                               8 MOV IKCC37A (40B)                                 6 KC HX JA (IB)
_OPNN Une Included In Pross. bndry.
SYSTEM COMPONENTS Size (in.)
Seismic PRA I integrity only q
AqV 1KC57A (828) 12 AOV 1KCD29 2
MOV IEKCA (2B) 20 MOV 1KC3A (18B) 10 MOV IKCSOA (53B) 20 MOV 1KC51A (548) 4  
-X MOV IKC56A (818) 16 MOV IKC230A (2280) 8 MOV IKCC37A (40B) 6 KC HX JA (IB)
KC PUMPS IAI, 1A2 (IBI, 8112)
KC PUMPS IAI, 1A2 (IBI, 8112)
KC SURGE TANK IA (IB)
KC SURGE TANK IA (IB)
RHR PUMP MECH. SEAL HX IA (I6)B).
RHR PUMP MECH. SEAL HX IA (I6) B).
KC PUMPS IA, 1A2 (I81, 182) MOTOR COOLERS '
KC PUMPS IA, 1A2 (I81, 182) MOTOR COOLERS '
AUX. SHUTDOWN PANEL AREA AIR COND. UNIT 1A                                          X CA MOTOR-DRIVEN PUMP IA (18) MOTOR COOLER RHR PUMP MOTOR COOLER IA (.18)                                                                     __
AUX. SHUTDOWN PANEL AREA AIR COND. UNIT 1 A X
NI PUMP MOTOR COOLER IA (1B)                                                       X NI PUMP BEARING OIL COOLER IA (1 B)                                                 X NS PUMP MOTOR COOLER IA (IB)                                                       XI_
CA MOTOR-DRIVEN PUMP IA (18) MOTOR COOLER RHR PUMP MOTOR COOLER IA (.18)
NI PUMP MOTOR COOLER IA (1B)
X NI PUMP BEARING OIL COOLER IA (1 B)
X NS PUMP MOTOR COOLER IA (IB)
XI_
NV PUMP MOTOR COOLER IA (18)
NV PUMP MOTOR COOLER IA (18)
NV PUMP MOTOR SPEED REDUCER OIL COOLER I A (I B)
NV PUMP MOTOR SPEED REDUCER OIL COOLER I A (I B)
Une       . .Included in     Press. bndry.
Une  
NC SYSTEM COMPONENTS '_'size               (In.)   Seismic PRA     integrity only     '_
.Included in Press. bndry.
SAFE*Y REUEF VALVE 1NC 1                         6               X         _        _
NC SYSTEM COMPONENTS '_'size (In.)
SAFETY REUEF VALVE I NC2                         6               X SAFETY REUEF VALVE 1NC3                           6               X PZR PORV INC32B                         -'3                     X PZR PORV 1NC34A                                   3               X PZR PORV INC36B                                   3               X         _._
Seismic PRA integrity only SAFE*Y REUEF VALVE 1NC 1 6
MOV INC31B                                       3 MOV INC33A                                       3 MOV   1NC35B                                     3 PZR HEATER BANK A (B) .....
X SAFETY REUEF VALVE I NC2 6
Page 3 Attachment 1 Page 18 of 36
X SAFETY REUEF VALVE 1NC3 6
X PZR PORV INC32B  
-'3 X
PZR PORV 1NC34A 3
X PZR PORV INC36B 3
X MOV INC31B 3
MOV INC33A 3
MOV 1NC35B 3
PZR HEATER BANK A (B).....
Page 3 Page 18 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 19 of 36 TABLE 2 -                                   .,i ('14 ND SYSTEM COMPONENTS       _Line  {]Size (In.)j I  IncludedPR.A Seismtc  In ._itgiyol Press. bndy._
CNC-1206.03-00-0203 Rev 0 A Page 19 of 36 TABLE 2 -
A w AOV 1ND26 (60)                                           8 AOV IND27 (61)                                         8 MOV   INDIB (36B)                                     12 MOV   IND2A (37A)                                     12 MOV   1ND24A (588)                                     2 MOV   IND25A (598)                                     2 MOV   I ND32A (65B)                                   2                               x .....
.,i ('14
MOV   IND90 (9?)                                     2                         _
_Line I
ND PUMP IA (18)
Included In Press. bndy._
NDHX 1A (1B)                                                       x MOV IND28A was included on the Unit 2 walkdown.
ND SYSTEM COMPONENTS
_        Une     Included In       Press. bndry, NI SYSTEM COMPONENTS                   Size (in.) Seismic PRA       Integrity only_
{]Size (In.)j Seismtc PR.A._itgiyol A
AOV   INi50 (72)                                       1 AOV   1NI56                                             1                               x AOV   1Ni57                                           0.75                             X AOV     1N8                                           0.75                             x AOV   1N161 (84)                                       1                                     "
w AOV 1ND26 (60) 8 AOV IND27 (61) 8 MOV INDIB (36B) 12 MOV IND2A (37A) 12 MOV 1ND24A (588) 2 MOV IND25A (598) 2 MOV I ND32A (65B) 2 x.....
AOV   I N167                                           I                               X AOV   IN168                                           0.75                             X AOV   IN169   ...                                    0.75                             X AOV   IN178                                             I                               X AOV   1N179                                           0.75                             X AOV   INf80                                           0.75                             X AOV   IN190                                             I                               X AOV   IN191                                         0.75                               X AOV 1NI92                                           0.75                               X AOV 1N1391 (3.93)                           _      0.75                               X AOV .N1392 (394)                                     0.75                               X MOV   I*N19A (OB)                                     4 MOV   1N154A (76A)                                     10                               X MOV   1N165B (88B)                                     10                               X MOV   iNIIOOB                                         8                               X MOV   INII03A (135B)                                   6                               X MOV 1NI115A,(144A)                                     2                               X MOV INII18A (150B)                                   . 4,_....
MOV IND90 (9?)
4                               X MOV 1NI120B                                         0,75 MOV INI!21A (052B)                                     4                               X 1N136B4MOV                                      8 MOV 1NI147B_                                           2                               X Page 4
2 ND PUMP IA (18)
                  )" l30], ()                   :1.
NDHX 1A (1B) x MOV IND28A was included on the Unit 2 walkdown.
Attachment 1 Page 19 of 36
Une Included In Press. bndry, NI SYSTEM COMPONENTS Size (in.)
Seismic PRA Integrity only_
AOV INi50 (72) 1 AOV 1NI56 1
x AOV 1Ni57 0.75 X
AOV 1N8 0.75 x
AOV 1N161 (84) 1 AOV I N167 I
X AOV IN168 0.75 X
AOV IN169 0.75 X
AOV IN178 I
X AOV 1N179 0.75 X
AOV INf80 0.75 X
AOV IN190 I
X AOV IN191 0.75 X
AOV 1NI92 0.75 X
AOV 1N1391 (3.93) 0.75 X
AOV.N1392 (394) 0.75 X
MOV I*N19A (OB) 4 MOV 1N154A (76A) 10 X
MOV 1N165B (88B) 10 X
MOV iNIIOOB 8
X MOV INII03A (135B) 6 X
MOV 1NI115A,(144A) 2 X
MOV INII18A (150B) 4,_....  
. 4 X
MOV 1NI120B 0,75 MOV INI!21A (052B) 4 X
4MOV 1N136B 8
MOV 1NI147B_
2 X
Page 4
)" l30], ()
:1.
Page 19 of 36


CNC-1 206.03-00-0203 Rev 0 Attachment 1A Page 20 of 36 TABLE 2 -                                         ~Ji   C1~
CNC-1 206.03-00-0203 Rev 0 A Page 20 of 36 TABLE 2 -
__M______ULine                                             Included in       "Press.bndry.
~Ji C1~
NI SYSTEM COMPONENTS (cont.)           Size (in.)       Seismic PiRA       It--grIty only OV       -1N173A(IB)8 78B)
__M______ULine Included in "Press. bndry.
MOV lN1183B                                       12                           1 MOV ]N1185A (184B)                     __10                                             __        ..
NI SYSTEM COMPONENTS (cont.)
MOV 1N1332A                                       6       _                                  _
Size (in.)
MOV 1NI333B'                                     6 MOV 1N1334B (136B)                               6 Ni PUMP IA (1B)
Seismic PiRA It--grIty only OV  
MOV 1NI438A (NIIROGEN BACKUP TO PZR PORV)         1                 X MOV 1NW4398 (NITROGEN BACKUP TO PZR PORV)         1                 X Une             Included In -- Press. bndry.
-1N173A (IB)8 78B)
NV SYSTEM COMPONENTS               Size (in.)       Seismic PRA       Integrity only AOV 1NV52A                                       2                                     x AOV 1NV63B                                       2                                     X AOV INV74A                                       2                                     X AOV 1NV85B                                       2                                     X AOV INV101A                                     0.75                                     x AOV 1NV294                                        3                                     X AOV 1NV309                                       3                                     X MOV   1NV44A                                     2                                     X MOV   1NV55A                             :      2                                     X MOV   INV66A                                     2                                     x MOV   1NV77A .                                   2                                     X MOV   1NVB9A (918)                               4                                     x MOV   INVI88A (1898)                             4                                     x MOV   1NV203A (20213)                           2                                     x MOV   1NV252A (253B)                             8 MOV   1NV312A (3148)                             3 CENTRIFUGAL CHARGING PUMP IA (1 B)
MOV lN1183B 12 1
MOV ]N1185A (184B)
__10 MOV 1N1332A 6
MOV 1NI333B' 6
MOV 1N1334B (136B) 6 Ni PUMP IA (1B)
MOV 1NI438A (NIIROGEN BACKUP TO PZR PORV) 1 X
MOV 1NW4398 (NITROGEN BACKUP TO PZR PORV) 1 X
Une Included In  
-- Press. bndry.
NV SYSTEM COMPONENTS Size (in.)
Seismic PRA Integrity only AOV 1NV52A 2
x AOV 1NV63B 2
X AOV INV74A 2
X AOV 1NV85B 2
X AOV INV101A 0.75 x
AOV 1 NV294 3
X AOV 1NV309 3
X MOV 1NV44A 2
X MOV 1NV55A 2
X MOV INV66A 2
x MOV 1NV77A.
2 X
MOV 1NVB9A (918) 4 x
MOV INVI88A (1898) 4 x
MOV 1 NV203A (20213) 2 x
MOV 1NV252A (253B) 8 MOV 1NV312A (3148) 3 CENTRIFUGAL CHARGING PUMP IA (1 B)
SEAL WATER INJECTION FILTER IA (1B)
SEAL WATER INJECTION FILTER IA (1B)
Une           Included In       Press. bndry.,
Une Included In Press. bndry.,
RN SYSTEM COMPONENTS               Size (In.)       Seismic PRA       lntegrity only AOV 1RN291 (351)                                 12 MOV IRNIA (5A)                                   48         _
RN SYSTEM COMPONENTS Size (In.)
AOOV IRN2B (6B)                                   48                           !
Seismic PRA lntegrity only AOV 1RN291 (351) 12 MOV IRNIA (5A) 48 AOOV IRN2B (6B) 48 OV 1RN30A (408) 4 i
OV 1RN30A (408)                               4       i                                       "-_
Page5 C&#xfd; D 1" I"!
Page5 C&#xfd; D 1"I"!       .J:
.J:
                                          .                                                              Attachment 1 Page 20 of 36
Page 20 of 36


CNC-1 206.03-00-0203 Rev 0 Attachment 1A Page 21 of 36 TABLE 2 -                                                 U      CiGG Line       _      Included In         Press. bndry_.
CNC-1 206.03-00-0203 Rev 0 A Page 21 of 36 U Ci GG TABLE 2 -
RN SYSTEM COMPONENTS (cont.)                         Size (in.)           Seismic PRA           integrity only MOV IRN36A (3713)                                               4 MOV IRN48B (47A)                           _    -.-          20       ......
)
MOV 1RN49A (501)                                               20 MOV IRN5IA (528)                                               20                           __                  _
Line Included In Press. bndry_.
MOV I RN54A (53B)                                             42                                 ....
RN SYSTEM COMPONENTS (cont.)
MOV 1RN63A (58B)           .        __42 MOV 1RN144A (2258)                                             18                                             X MOV 1RN148A (2298)                                     !      18                               ....          X MOV IRN232A (2928)                                             10 MOV IRN287A (347B)                                             20                                             X MOV IRN843B (57A)                                             42 MOV 1RN846A (848B)                                             10 MOV   1RNB47A (849B)                                         10 RN STRAINER 1A   (1B)                                                                         _                      ....
Size (in.)
Seismic PRA integrity only MOV IRN36A (3713) 4 MOV IRN48B (47A) 20 MOV 1RN49A (501) 20 MOV IRN5IA (528) 20 MOV I RN54A (53B) 42 MOV 1RN63A (58B)
__42 MOV 1RN144A (2258) 18 X
MOV 1RN148A (2298) 18 X
MOV IRN232A (2928) 10 MOV IRN287A (347B) 20 X
MOV IRN843B (57A) 42 MOV 1RN846A (848B) 10 MOV 1RNB47A (849B) 10 RN STRAINER 1A (1B)
RN PUMP IA (IB) UPPER BEARING HX RN PUMP LUBE INJECTION SIMPLEX STRAINER A (B)
RN PUMP IA (IB) UPPER BEARING HX RN PUMP LUBE INJECTION SIMPLEX STRAINER A (B)
SNSWP INTAKE (video available)                   II The following Unit I components and structures were included on the Unit 2 walkdown:
SNSWP INTAKE (video available)
MOV IRN3A                                                                     [                             _            ---
II The following Unit I components and structures were included on the Unit 2 walkdown:
) MOV 1RN4B MOV IRN11A
MOV IRN3A
                                                                            '                    -                  ___        i MOV 1RN20B                                                        ____
[
MOV I RN28A                                               _
MOV 1RN4B i
MOV IRN38B MOV 1RN67A MOV IRN69B MOV 1RN250A [train B' valve (ORN310B)NOT reviewed]
MOV IRN11A MOV 1 RN20B MOV I RN28A MOV IRN38B MOV 1 RN67A MOV IRN69B MOV 1RN250A [train B' valve (ORN310B) NOT reviewed]
ELECTROHYDRAULIC VLV 1RN244A                             ___,
ELECTROHYDRAULIC VLV 1RN244A ELECTROHYDRAULIC VLV IRN304B RN PUMP IA RN PUMP IB.Bi RN PUMP INTAKE PIT A BARS, DEBRIS SCREEN, & STRUCTURE R4j PUMP INTAKE PIT B BARS, DEBRIS SCREEN, & STRUCTURE STANDBY NUCLEAR SERVICE WATER POND Une Included in Press. bndry.
ELECTROHYDRAULIC VLV IRN304B RN PUMP IA                                                             -.--              _
SA, SM, SV SYSTEM COMPONENTS Size (In.)
RN PUMP IB .Bi RN PUMP INTAKE PIT A BARS, DEBRIS SCREEN, & STRUCTURE R4j PUMP INTAKE PIT B BARS, DEBRIS SCREEN, & STRUCTURE STANDBY NUCLEAR SERVICE WATER POND                     ___
Seismic PRA Integrlty only AOV I SA2 (5) 4 AOV 1SM86 2
Une                 Included in         Press. bndry.
X AOV 1SM87
SA, SM, SV SYSTEM COMPONENTS                       Size (In.)     __      Seismic PRA   _      Integrlty only AOV ISA2 (5)                                                   4       __
__2_
AOV   1SM86                                                   2       _                                    X AOV 1SM87                                               __2_                                               X Page 6
X Page 6
                                      ':i*t*!; 1 :   ;*I; :.                                                                  Attachment 1 Page 21 of 36
.... t*!;
':i*
1 :
I; Page 21 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 22 of 36 TABLE 2 -                                             CI?
CNC-1206.03-00-0203 Rev 0 A Page 22 of 36 CI?
_  __  _ Une             Included In     Press. bndry.
TABLE 2 -
SA, SM, SV SYSTEM COMPONENTS (cont.)                     Size (in.)         Seismic PRA     Integrity only AOV 1SM88                                                       2                         :          X AOV ISM89                                                      2                                   X MOV 1SM74B                                                     2                                   X MOV 1SM75A                                                     2                                   x MOV 1SM76B                                                     2                                   X MOV 1SM77A                                                     2                                   X MSIV ISM i                                                   34 MSIV 1SM3                                                     34         _.
_ Une Included In Press. bndry.
MSIV   ISM5                                                   34       _                    _
SA, SM, SV SYSTEM COMPONENTS (cont.)
MSIV   1SM7                                                   34     ....
Size (in.)
MSI BYPASS VLV 1SM9                                            3                                     x MSI BYPASS VLV 1SM1O                                           3                                     x MSI BYPASS VLV ISMI 1                                         3                                     X MSI BYPASS VLV 1SMJ12                                         3
Seismic PRA Integrity only AOV 1SM88 2
* _x SG PORV ISV]                                                   6                   X SG PORV     ISV7                                               6                   X SG PORV ISV13                                                   6                   X SG PORV ISVM9                                                 6                   X
X AOV I SM89 2
) SG SRV 1SV2 SG SRV 1SV3 6x 10 6 x 10
X MOV 1SM74B 2
_X X
X MOV 1SM75A 2
SG SRV 1SV4                                                 6x 10                                   X SG SRV 1SV5                                                 6x 10                                   X SG SRV 1SV6                                                 6x 10                                   X SG SRV ISV8                                                 6x 10                                   X SG SRV ]SV9                                                 6x 10                                   X SG   SRV 1SVIO                                             6x   10                                 X SG   SRV ISVI I                                             6x   10                                 X SG   SRV 1SV12                                             6x   10                                 X SG   SRV 1SV14                                             6x   10                                 x SG S1V ISV15                                               6x 10                                   X SG SRV 1SV16                                               6x 10 ..                                           __X SG SRV 1SV17                                               6x 10                                   X SG SRV SV18                                                 6x   10                                 X SG SRV 1SV20                                               6x   10                                 X
x MOV 1SM76B 2
* SG SRV ISV21                                               6x  10                                 X SG SRV 1SV22                                               6x   10                                 x SG SRV 1SV23                                               6x10                                   X SG SRV 1SV24                                               6x 10                                   X 6                                __  xX MOV 1SV25B MOV 1SV26B                                                     6                                   X MOV 1SV27A                                                   6                                     x MOV ISV28A                                           T,     6                                     x Page 7
X MOV 1SM77A 2
                              .;!&#xfd;
X MSIV ISM i 34 MSIV 1SM3 34 MSIV ISM5 34 MSIV 1SM7 34 MSI BYPASS VLV 1 SM9 3
                                !..-.;;,:-, .1. ; -, &#xfd;, -:
x MSI BYPASS VLV 1SM1O 3
Attachment 1 Page 22 of 36
x MSI BYPASS VLV ISMI 1 3
X MSI BYPASS VLV 1SMJ12 3
_x SG PORV ISV]
6 X
SG PORV ISV7 6
X SG PORV ISV13 6
X SG PORV ISVM9 6
X SG SRV 1SV2 6x 10
_X SG SRV 1SV3 6 x 10 X
SG SRV 1SV4 6x 10 X
SG SRV 1SV5 6x 10 X
SG SRV 1SV6 6x 10 X
SG SRV ISV8 6x 10 X
SG SRV ]SV9 6x 10 X
SG SRV 1SVIO 6x 10 X
SG SRV ISVI I 6x 10 X
SG SRV 1SV12 6x 10 X
SG SRV 1SV14 6x 10 x
SG S1V ISV15 6x 10 X
SG SRV 1SV16 6x 10..
__X SG SRV 1SV17 6x 10 X
SG SRV SV18 6x 10 X
SG SRV 1SV20 6x 10 X
SG SRV ISV21 6 x 10 X
SG SRV 1SV22 6x 10 x
SG SRV 1SV23 6x10 X
SG SRV 1SV24 6x 10 X
MOV 1SV25B 6
X x
MOV 1SV26B 6
X MOV 1SV27A 6
x MOV ISV28A T,
6 x
)
Page 7
.;!&#xfd;  
.1. ; -, &#xfd;, -:
Page 22 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 23 of 36 TABLE 2 -                                   bi .018 Une             Included In   Press. bndn&#xfd;.
CNC-1206.03-00-0203 Rev 0 A Page 23 of 36 bi.018 TABLE 2 -
            ,VA* SYSTEM COMPONENTS                       Size ((n.)       Seismic PRA   integrity onjy MOV IVA28B(31A)                                             6                                 X MOV 1VA29A (30B)                                           6                                 X AIR-OPERATED       DAMPER IABF-D- 10 (3)
)
AIR-OPERATED       DAMPER 1ABF-D- 12 (5)
9 Une Included In Press. bndn&#xfd;.
,VA* SYSTEM COMPONENTS Size ((n.)
Seismic PRA integrity onjy MOV IVA28B(31A) 6 X
MOV 1VA29A (30B) 6 X
AIR-OPERATED DAMPER IABF-D-10 (3)
AIR-OPERATED DAMPER 1ABF-D-12 (5)
C._.
C._.
AIR-OPERATED       DAMPER 1ABF-D-14 (7)
AIR-OPERATED DAMPER 1ABF-D-14 (7)
AIR-OPERATED       DAMPER 1AB&.D- 1 (3)
AIR-OPERATED DAMPER 1AB&.D-1 (3)
ELECTRO-HYDRAUUC           DAMPER IABF-D-4 ELECTRO-HYDRAULIC         DAMPER 1ABF-D-6 ELECTRO-HYDRAULIC         DAMPER 1ABF-D- 1                                               -
ELECTRO-HYDRAUUC DAMPER IABF-D-4 ELECTRO-HYDRAULIC DAMPER 1ABF-D-6 ELECTRO-HYDRAULIC DAMPER 1ABF-D-1 ELECTRO-HYDRAULIC DAMPER IABF-D-13 ELECTRO-HYDRAUUC DAMPER IABF-D-16 ELECTRO-HYDRAUUC DAMPER IABF-D-18 MOISTURE EUMINATOR PRHDS-1A (1B)
ELECTRO-HYDRAULIC         DAMPER IABF-D-13 ELECTRO-HYDRAUUC           DAMPER IABF-D-16       __
AUX. BLDG. FILTER UNIT ABFU-1A (I B)
ELECTRO-HYDRAUUC           DAMPER IABF-D- 18       _
MOISTURE EUMINATOR PRHDS-1A (1B)
AUX. BLDG. FILTER UNIT ABFU-1A (I B)                 _,                                                  .
AUX. BLDG. FAN ABFXF-1A (IB)..
AUX. BLDG. FAN ABFXF-1A (IB)..
AUX. BLDG, FAN SUPPLY UNIT ABSU-IA (i8)
AUX. BLDG, FAN SUPPLY UNIT ABSU-IA (i8)
)          VC SYSTEM COMPONENTS Line Size (In.)
Line Included in Press. bndry.
Included in Seismic PRA Press. bndry.
VC SYSTEM COMPONENTS Size (In.)
Jntegrty only   _"
Seismic PRA Jntegrty only MOV IVC5B 24 MOV IVC6A 24 MOV 1VC7B.
MOV IVC5B                                                 24       _,-_                                      -.,,
4 MOV I VC8A 4
MOV IVC6A                                                 24 MOV 1VC7B.                                                 4           __......
ELECTRO-HYDRAULIC DAMPER ICR-D-2 X
MOV I VC8A                                                 4 ELECTRO-HYDRAULIC DAMPER ICR-D-2                                                             X ELECTRO-HYDRAULIC DAMPER tCRA-D-5 ELECTRO-HYDRAULIC DAMPER 1CRA-D-7 CONTROL ROOM AHU 1CR-AHU-1 ............
ELECTRO-HYDRAULIC DAMPER tCRA-D-5 ELECTRO-HYDRAULIC DAMPER 1CRA-D-7 CONTROL ROOM AHU 1CR-AHU-1............
PRESSURIZiNG FILTER ICRA-PFT- I.....
PRESSURIZiNG FILTER I CRA-PFT-I.....
PRESSURIZING FILTER FAN 1CRA-PFTF- I       .......
PRESSURIZING FILTER FAN 1CRA-PFTF-I CONTROL ROOM AREA AHU 1CRA-AHU-1 SWITCHGEAR ROOM AHU ISGR-AHU-1 (2),
CONTROL ROOM AREA AHU 1CRA-AHU-1 SWITCHGEAR ROOM AHU ISGR-AHU-1 (2),
SWITCHGEAR ROOM AHU 1 SGR-AHU-3 (4)
SWITCHGEAR ROOM AHU 1SGR-AHU-3 (4)
HEATER UNIT ICR-H-I x
HEATER   UNIT   ICR-H-I                                                                     x HEATER   UNIT   1CRA-H-1                                                                     x HEATER   UNIT   ICRA-H-2                                                                     X HEATER   UNIT   1CRA-H-3                                                                     x 9 HEATER HEATER UNIT UNIT 1CRA-H-4 1CRA-H-5 x
HEATER UNIT 1CRA-H-1 x
x HEATER   UNIT   1CRA-H-7                                                         =___       x Page 8
HEATER UNIT ICRA-H-2 X
                ,.:I IJ IJ I.) ... .....                                                                      Attachment 1 Page 23 of 36
HEATER UNIT 1CRA-H-3 x
HEATER UNIT 1CRA-H-4 x
HEATER UNIT 1CRA-H-5 x
HEATER UNIT 1CRA-H-7  
=___
x Page 8
,.:I IJ IJ I.)
Page 23 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 24 of 36 TABLE 2 -                             &1       o iX/(c VZ SYSTEM COMPONENTS rj__Included j
CNC-1206.03-00-0203 Rev 0 A Page 24 of 36 TABLE 2 -
in Seismic PRA Press. bndry.
&1 o iX/(c rj__Included in Press. bndry.
flntegrit only NUCLEAR SERVICE WATER PUMPHOUSE FAN IA. 2A (1B, 21)
VZ SYSTEM COMPONENTS j
Seismic PRA flntegrit only NUCLEAR SERVICE WATER PUMPHOUSE FAN IA. 2A (1B, 21)
ELECTRO-HYDRAULIC DAMPERS A3A, A4A (A3B, A4B)
ELECTRO-HYDRAULIC DAMPERS A3A, A4A (A3B, A4B)
ELECTRO-HYDRAULIC DAMPERS B3A, B4A (B3B, 848)
ELECTRO-HYDRAULIC DAMPERS B3A, B4A (B3B, 848)
Une     Included In   Pres. bndry.v         -
Une Included In Pres. bndry.v YC SYSTEM COMPONENTS Stzo (in.)
YC SYSTEM COMPONENTS                 Stzo (in.) Seismic PRA   Integrity only     __
Seismic PRA Integrity only MOV 1YC77A.(121B)  
MOV 1YC77A .(121B)                                 -2                           X ELECTRO-HYDRAUUC           VLV 1YC26 (100)         2.5 ELECTRO-HYDRAULIC           VLV IYC58 (15D)           4 ELECTRO-HYDRAULIC           VLV 1YC 196 (208)         3                                           --  -_
-2 X
ELECTRO-HYDRAUUC           VLV 1YC203 (214)         3 ELECTRO-HYDRAUUC           VLV 1YC264 (274)         3 ELECTRO-HYDRAUUC VLV           1YC270 (281)         3 CONTROL ROOM AREA CHILLED WATER PUMP 1CRA-CHWP-1             ...                        _-
ELECTRO-HYDRAUUC VLV 1YC26 (100) 2.5 ELECTRO-HYDRAULIC VLV IYC58 (15D) 4 ELECTRO-HYDRAULIC VLV 1YC 196 (208) 3 ELECTRO-HYDRAUUC VLV 1YC203 (214) 3 ELECTRO-HYDRAUUC VLV 1YC264 (274) 3 ELECTRO-HYDRAUUC VLV 1YC270 (281) 3 CONTROL ROOM AREA CHILLED WATER PUMP 1CRA-CHWP-1 YC CHILLER ICRA-C-1.
YC CHILLER ICRA-C-1.
YC COMPRESSION TANK ICRA-CT MISC. CIVIL STRUCTURES INSIDE DOGHOUSE x
YC COMPRESSION TANK ICRA-CT                                                                     -
D/G BUILDING X
)          MISC. CIVIL STRUCTURES INSIDE DOGHOUSE                         .                        x       __        ,_ .....
REACTOR COOLANT PUMP SUPPORTS X
D/G BUILDING                                                     X REACTOR COOLANT PUMP SUPPORTS                                     X CONTAINMENT INTERNAL STRUCTURE                                   X CONTROL ROD DRIVE MECHANISM                                       X REACTOR BUILDING                                                 X AUXILIARY BUILDING SHEAR WALLS                                   X                 "_ _
CONTAINMENT INTERNAL STRUCTURE X
9 Page 9 Attachment 1 Page 24 of 36
CONTROL ROD DRIVE MECHANISM X
REACTOR BUILDING X
AUXILIARY BUILDING SHEAR WALLS X  
)
9 Page 9 Page 24 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 25 of 36 TABLE 3 -                                             020 ELECTRICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN
CNC-1206.03-00-0203 Rev 0 A Page 25 of 36 TABLE 3 -
    -.        -            -.              -            I CB' train components are shown In parentheses. A detailed walkdown of these components ISnot il necessary if the 'B' train configuration Is similar to the 'A' train.)
020 ELECTRICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN I
___Included                                       In SUPPORT FOR CA SYSTEM                                                           Seismic PRA 4160V AC SWITCHGEAR IETA (OEMB)                                                                   x 600V AC MCC )EMXC                                                                                 x 600VAC MCC IEMXI (IEMXB)                                                                         x.._
il CB' train components are shown In parentheses. A detailed walkdown of these components IS not necessary if the 'B' train configuration Is similar to the 'A' train.)
600VAC MCC IEMXK (IEMXB)                                                                         X         -
)
600V AC MCC IEMXL                                         _    __x 600V AC LOAD CENTER 1ELXA                                                                         X_
9
600V AC LOAD CENTER IELXC                                             -          _              x 600V AC LOAD CENTER 1ELXD                                                                        X 125V DC PANELBOARD ]EPA (OEPM)                                                                   x 125V DC DISTRIBUTION CENTER IEDA                           _  _            __"                X 125V DC DISiTRIUTION CENTER IEDE (QEDF)                                                           x 12V AC PANELBOARD IERPA (I ERPD)_                                                                 X 125V DC VITAL I&C BATTERY CHARGER IEBA                     _      -                                    _
___Included In SUPPORT FOR CA SYSTEM Seismic PRA 4160V AC SWITCHGEAR IETA (OEMB) x 600V AC MCC )EMXC x
125V DC VITAL I&C BATTERY CHARGER IECA                   i               ,                          _
600VAC MCC IEMXI (IEMXB) x.._
600VAC MCC IEMXK (IEMXB)
X 600V AC MCC IEMXL
__x 600V AC LOAD CENTER 1ELXA X_
600V AC LOAD CENTER IELXC x
600V AC LOAD CENTER 1 ELXD X
125V DC PANELBOARD ]EPA (OEPM) x 125V DC DISTRIBUTION CENTER IEDA X
125V DC DISiTRIUTION CENTER IEDE (QEDF) x 12V AC PANELBOARD I ERPA (I ERPD)_
X 125V DC VITAL I&C BATTERY CHARGER IEBA 125V DC VITAL I&C BATTERY CHARGER IECA i
126V DC VITAL &C BATTERY CHARGER IECS---
126V DC VITAL &C BATTERY CHARGER IECS---
125V DC VITAL I&C BATTERY CHARGER 1EDS 48V DC ESFAS TRAIN A (B)SUPPLY POWER                                                   ,_,
125V DC VITAL I&C BATTERY CHARGER 1EDS 48V DC ESFAS TRAIN A (B) SUPPLY POWER INSTR. LOOP CONTAINING 1CALL/SV/EP0560 (0400)
)  INSTR. LOOP CONTAINING 1CALL/SV/EP0560 (0400)
INSTR. LOOP CONTAINING 1CALL/SV/EP0600 (0440)
INSTR. LOOP CONTAINING 1CALL/SV/EP0600 (0440)                               -
INSTR. LOOP CONTAINING 1CAFE/FT/P 5100 INSIT. LOOP CONTAINING 1 CAFE/FT/P 5110 INSTR. LOOP CONTAINING )CAFE/FT/P 5120
INSTR. LOOP CONTAINING 1CAFE/FT/P 5100 INSIT. LOOP CONTAINING 1CAFE/FT/P 5110                 .....                        __
__}__-
INSTR. LOOP CONTAINING       )CAFE/FT/P 5120                               __}__-         __
INSTR, LOOP CONTAINING 1CAPS5220, 5221, & 5222 (5230, 5231 & 5232)
INSTR, LOOP CONTAINING       1CAPS5220, 5221, & 5222 (5230, 5231 & 5232)
!NSTR. LOOP CONTAINING 1CFLT/P 5490 (5560)  
  !NSTR. LOOP CONTAINING       1CFLT/P 5490 (5560)           __          '"_'l           --
'"_'l INSTR. LOOP CONTAINING CFLT/P (5550)
INSTR. LOOP CONTAINING         CFLT/P       (5550)                                         _
INSTR. LOOP CONTAINING 1CFLT/P 5501 (5551)
INSTR. LOOP CONTAINING         1CFLT/P 5501 (5551)
INSTR. LOOP CONTAINING ICFLT/P 5510 & P 5511 (5570)
INSTR. LOOP CONTAINING       ICFLT/P 5510 & P 5511 (5570) ....
INSTR. LOOP CONTAINING ICFLT/P 5520 & 1 CAP 5521 (5590 & 5591)
INSTR. LOOP CONTAINING         ICFLT/P 5520 & 1CAP 5521 (5590 & 5591)
INSTR. LOOP CONTAINING ]CFLT/P5530 (5580)
INSTR. LOOP CONTAINING         ]CFLT/P5530 (5580)
INSTR. LOOP CONTAINING ICFLT/P 5540 (5600)
INSTR. LOOP CONTAINING         ICFLT/P 5540 (5600)                                       -
INSTR. LOOP CONTAINING 1 CFLT56 10 &P 5612 (5630 & 5632) i INSTR. LOOP CONTAINING ICFLT5620 & P 5622 (5640 & 5642)
INSTR. LOOP CONTAINING         1CFLT56 10 &P 5612 (5630 & 5632)                             i INSTR. LOOP CONTAINING         ICFLT5620 & P 5622 (5640 & 5642)
POST-ACC(DENT MONITORING INSTRUMENTAT70N Page I D ID ID)")
POST-ACC(DENT MONITORING INSTRUMENTAT70N                                     _
Page 25 of 36
9 Page I D IDID)")                                                                                   Attachment 1 Page 25 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 26 of 36 TABLE 3 -                                           w1       021 I__         _  _ !Included
CNC-1206.03-00-0203 Rev 0 A Page 26 of 36 TABLE 3 -
__                                    in SUPPORT FOR DIESEL GENERATORS______                                                               Seismic PRA..
w1 021
125V DC BATTERY/ PRACK                       _          --              1           _X                                 --
)
INVERTERS                                                                                                   X BATTERY 1DGBA (1 DGBB) AND CHARGERS                     __            __                                    X         _.
9 I__  
D/G CONTROL PANEL                                             __                        _                    X DIESEL ENGINE CONTROL PANEL                                                                                   X D/G NEUTRAL GROUND PANEL                                                                                     x AUCTIONEERING DIODE ASSEMBLY EVDA (EVDB)                                   -        _    __x LOAD SEQUENCER                                               ____    _            _X INbTR. LOOP CONTAINING 1FDFT5O00; 1FDLT5003; & 1FDPS5001 thru 5004 (5~5163;       & 5160- -.. *)j)                                fl-                         __5 INSTR, LOOP CONTAINING I FDFT6010; 1FDLT5013; & iFDPS5011 i*hru 5014 (5170;5173; &6170- 5174)                     .[                 iIL__-.
!Included in SUPPORT FOR DIESEL GENERATORS______
Seismic PRA..
125V DC BATTERY/ PRACK 1
_X INVERTERS X
BATTERY 1 DGBA (1 DGBB) AND CHARGERS X
D/G CONTROL PANEL X
DIESEL ENGINE CONTROL PANEL X
D/G NEUTRAL GROUND PANEL x
AUCTIONEERING DIODE ASSEMBLY EVDA (EVDB)
__x LOAD SEQUENCER
_X INbTR. LOOP CONTAINING 1 FDFT5O00; 1 FDLT5003; & 1 FDPS5001 thru 5004 (5~5163;  
& 5160-  
*)j fl-
__5  
)
INSTR, LOOP CONTAINING I FDFT6010; 1FDLT5013; & iFDPS5011 i*hru 5014 (5170;5173; &6170- 5174)  
.[
iIL__-.
INSTR. LOOP CONTAINING IFDLT5060; 1FDPG5061, 5062 (5200; 5201,520'2)
INSTR. LOOP CONTAINING IFDLT5060; 1FDPG5061, 5062 (5200; 5201,520'2)
INSTR. LOOP CONTAINING I1LDPT/PG5 140; ILDPS5141; ILDPS/PT5I42; ILDPT5143;                 & I.LDPT5144 .
INSTR. LOOP CONTAINING I1LDPT/PG5 140; ILDPS5141; ILDPS/PT5I42; ILDPT5143;  
(5170;5171; 5172, 5173;&5174)                       ..... l                         ___
& I.LDPT5144.
INSTR. LOOP CONTAINING LDPG/PS5160 & ILDPS5300 (5190 & 5310)
(5170;5171; 5172, 5173;&5174) l INSTR. LOOP CONTAINING LDPG/PS5160 & ILDPS5300 (5190 & 5310)
INSM. LOOP CONTAINING 1LDIT/P200                                         1 1--
INSM. LOOP CONTAINING 1 LDIT/P200 1 1--
INSTR, LOOP CONTAINING 1LOPT/PS/PG5220: 1LDPT/PS5230; & 1LDPS5500 (5240, 5250. -)                                       ___      I_____
INSTR, LOOP CONTAINING 1 LOPT/PS/PG5220: 1 LDPT/PS5230; & 1 LDPS5500 (5240, 5250. -)
INSTR. LOOP CONTAINING         1LDTT/PS5270.
I_____
INSTR. LOOP CONTAINING         1LDPT/PS5400 (5420)                                                                     -
INSTR. LOOP CONTAINING 1 LDTT/PS5270.
INSTR. LOOP CONTAINING         1LDPG5410 (5430) 1 I
INSTR. LOOP CONTAINING 1LDPT/PS5400 (5420)
) INSTR. LOOP CONTAINING INSTR. LOOP CONTAINING 1VGPS/PG5-500 & 1VGPS5101, 5102 (5250 & 525).5252)
INSTR. LOOP CONTAINING 1LDPG5410 (5430) 1 I
IVGPS/PG5120 & 1VGPS5121, 5122 (5270 & 5271. 5272)
INSTR. LOOP CONTAINING 1VGPS/PG5-500 & 1VGPS5101, 5102 (5250 & 525).5252)
Included in SUPPORT FOR FW SYSTEM                                                                 i   Seismic PRA 600V AC MCC 1EMXA (1EMXB)
INSTR. LOOP CONTAINING IVGPS/PG5120 & 1 VGPS5121, 5122 (5270 & 5271. 5272)
INSTR. LOOP CONTAINING 1FWLT/P 5000                         !
Included in SUPPORT FOR FW SYSTEM i
INSTR. LOOP CONTAINING IFWLT/P 5010i INSTR, LOOP CONTAINING 1FWLT/P 5020 INSTR. LOOP CONTAINING IFWLT/P 5130                   .......
Seismic PRA 600V AC MCC 1EMXA (1EMXB)
___        FOR_ KC SYSTEMIncluded In SUPPORT FOR KC SYSTEM                     --                                              Seismic PRA 4160V AC SWITCHGEAR 1ETA (1ETB)                             I                                                 x 600V AC MCC iEMXA (1EMXJ)                                                                                     x*
INSTR. LOOP CONTAINING 1FWLT/P 5000 INSTR. LOOP CONTAINING IFWLT/P 5010i INSTR, LOOP CONTAINING 1 FWLT/P 5020 INSTR. LOOP CONTAINING IFWLT/P 5130 FOR KC SYSTEMIncluded In SUPPORT FOR KC SYSTEM Seismic PRA 4160V AC SWITCHGEAR 1ETA (1ETB)
:00V AC MCC 1EMXI (IEMXJ)                     ___x__X 9 600V AC LOAD         CONTROL 125V DC PANELBOARD ]EPA (1EPB)
I x
CENTER  1ELXA    (1ELXB)
600V AC MCC iEMXA (1EMXJ) x*
_x
:00V AC MCC 1EMXI (IEMXJ)
                                                                              --                              X 125V DC DISTRIBUTION CENTER 1EDE                  +                         -X Page 2 Attachment 1 Page 26 of 36
___x__X 600V AC LOAD CONTROL CENTER 1ELXA (1ELXB)
X 125V DC PANELBOARD ]EPA (1EPB)
_x 125V DC DISTRIBUTION CENTER 1 EDE
+  
-X Page 2 Page 26 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 27 of 36
CNC-1206.03-00-0203 Rev 0 A Page 27 of 36
                      /
/
TABLE 3 -                                           N1    022
TABLE 3 -
_Included                               In SUPPORT FOR KC SYSTEM (CONT.)                                 _Seism.c                         PRA INSTR LOOP CONTAINING 1KCFE/Fr/PS/P 5530 (5540)
N 1 022
_Included In SUPPORT FOR KC SYSTEM (CONT.)
_Seism.c PRA INSTR LOOP CONTAINING 1KCFE/Fr/PS/P 5530 (5540)
INSTR. LOOP CONTAINING 1KCLS/LT/P 5630 (5640)
INSTR. LOOP CONTAINING 1KCLS/LT/P 5630 (5640)
Included In SUPPORT FOR NC SYSTEM                                                           Seismic PRA 6900V AC SWITCHGEAR 1TD 4160V AC SWITCHGEAR 1ETB                             _x MAIN TRANSFORMED 1B AND BUS                         __        ....
Included In SUPPORT FOR NC SYSTEM Seismic PRA 6900V AC SWITCHGEAR 1TD 4160V AC SWITCHGEAR 1ETB
TRANSFORMER 1ATD TRANSFORMER 1ETXB AUXILIARY POWER TRANSFORMER IT1A AUXILIARY POWER TRANSFORMER IT1B 6WV AC MCC IEMXC                                                                                  x 600V AC MCC 1EMXD                                                                                  x 600V AC LOAD CENTER 1ELXB                                                                         X 120V AC PANELBOARD 1ERPA                                                                   -_x 120V AC PANELBOARD IERPD                                                                         X 120V AC VITAL POWER INVERTER tEID 125V DC VITAL I&C SPARE BATTERY CHARGER IEBD 125V DC VITAL I&C SPARE BATTERY CHARGER 1ECD
_x MAIN TRANSFORMED 1 B AND BUS TRANSFORMER 1ATD TRANSFORMER 1 ETXB AUXILIARY POWER TRANSFORMER IT1A AUXILIARY POWER TRANSFORMER IT1B 6WV AC MCC I EMXC x
)  125V DC VITAL I&C SPARE BATTERY CHARGER IECS 125V DC DISTRIBUTION CENTER 1EDD             II INSTR. LOOP   CONTAINING   1NCSV/LL0320, 1NCSV0321,     & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0340, INCSVO341, & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0360, 1NCSV0361, & RCPS INSTR. LOOP CONTAINING 1NCLT/PT/P 5150   ]   [. "L                             _..
600V AC MCC 1 EMXD x
INSTR. LOOP CONTAINING 1NCLT/PT/SS.5160 & 1NCP 5161               [....
600V AC LOAD CENTER 1ELXB X
INSTR. LOOP CONTAINING INCLT/PT/P 5170; 1NCLT/PT/P 517 1NCP 5173; & INCP 5174 INSTR. LOOP CONTAINING I NCRD/P 5940             I __....
120V AC PANELBOARD 1ERPA  
INSTR. LOOP   CONTAINING     INCRD/P 5970     9               -
-_x 120V AC PANELBOARD IERPD X
INSTR. LOOP CONTAINING 1NCRD/P 5960                                   _
120V AC VITAL POWER INVERTER tEID 125V DC VITAL I&C SPARE BATTERY CHARGER IEBD 125V DC VITAL I&C SPARE BATTERY CHARGER 1ECD 125V DC VITAL I&C SPARE BATTERY CHARGER IECS 125V DC DISTRIBUTION CENTER 1EDD II INSTR. LOOP CONTAINING 1NCSV/LL0320, 1NCSV0321, & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0340, INCSVO341, & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0360, 1NCSV0361, & RCPS INSTR. LOOP CONTAINING 1NCLT/PT/P 5150  
INADEQUATE CORE COOLING MONITOR
]
_Included                                           in SUPPORT FOR ND SYSTEM                 i.__Seismic                                       PRA 4160V AC SWITCHGEAR IETA (1ETB)                     ____X 600V AC MCC 1EMXA (1EMXJ)__x 600V AC MCC 1EMXC                                                                                 X 600V AC MCC 1EMXD                                                                                 X 9 600V AC MCC IEMXS (IEMXL) 125V DC DISTRIBUTION CENTER )EDE (1EDF)           ___                        __    ..
[. "L INSTR. LOOP CONTAINING 1NCLT/PT/SS.5160 & 1NCP 5161
x x
[....
INSTR. LOOP CONTAINING 1NDFE/PG5040 & 1NDPG5041 (5050,5051)                           .. ,I Page 3 Attachment I Page 27 of 36
INSTR. LOOP CONTAINING I NCLT/PT/P 5170; 1 NCLT/PT/P 517 1 NCP 5173; & INCP 5174 INSTR. LOOP CONTAINING I NCRD/P 5940 I __....
INSTR. LOOP CONTAINING INCRD/P 5970 9
INSTR. LOOP CONTAINING 1 NCRD/P 5960 INADEQUATE CORE COOLING MONITOR
_Included in SUPPORT FOR ND SYSTEM i.__Seismic PRA 4160V AC SWITCHGEAR IETA (1ETB)
____X 600V AC MCC 1EMXA (1EMXJ)__x 600V AC MCC 1EMXC X
600V AC MCC 1EMXD X
600V AC MCC IEMXS (IEMXL) x 125V DC DISTRIBUTION CENTER )EDE (1EDF) x INSTR. LOOP CONTAINING 1NDFE/PG5040 & 1NDPG5041 (5050,5051)  
..,I
)
9 Page 3 Attachment I Page 27 of 36


CNC- 1206.03-00-0203 Rev 0 Attachment 1A Page 28 of 36 TABLE 3 -                                         N           023 SUPPORT FOR NI SYSTEM                 __ __-
CNC-1206.03-00-0203 Rev 0 A Page 28 of 36 TABLE 3 -
                                                                    --                  -Included Seismic PRA In 4160V AC SWITCHGEAR         1ETA (1ETB)           __      1                     .--
N 023
600V AC MCC 1EMXA (1EMXB) (1EMXJ)                                                               xijX 125V DC DISTRIBUTION CENTER IEDE (1EDF)                                                       X INSTR. LOOP CONTAINING INILT/P 5260 INSTR. LOOP CONTAINING INILT/P 5270
-Included In SUPPORT FOR NI SYSTEM Seismic PRA 4160V AC SWITCHGEAR 1ETA (1ETB) 1 600V AC MCC 1EMXA (1EMXB) (1EMXJ) xijX 125V DC DISTRIBUTION CENTER IEDE (1EDF)
_      _  _____Included                               in SUPPORT FOR NV SYSTEM                                                           Seismic PRA 4160V AC SW1TCHGEAR IETA (1ETB)                                                                 x 600V AC MCC 1EMXA                                                                               x 600V AC MCC 1EMXJ                                                                               x 600V AC MCC 1EMXL                                                                               x                 .
X INSTR. LOOP CONTAINING INILT/P 5260 INSTR. LOOP CONTAINING INILT/P 5270
125V DC DISTRIBUTION CENTER ]EDE (OEDF)                                                       X 120V DC PANELBOARD I ERPC                                                                     X INSTR. LOOP CONTAINING 1NVFE/Fr/CR5120 & INVFT/CR5121 INSMTR LOOP CONTAINING 1NVFE/FT5130 & 1NVFT5131I INSTR. LOOP CONTAINING 1NVFE/FT/CR5140 & INVFT/CR5141 INSTR. LOOP CONTAINING 1NVFE/FT5150 & 1NVFT5W11 INST. LOOP CONTAINING INVFE/FT/P 5300 & INVP5301                   __
_____Included in SUPPORT FOR NV SYSTEM Seismic PRA 4160V AC SW1TCHGEAR IETA (1ETB) x 600V AC MCC 1EMXA x
INSHTR. LOOP CONTAINING INVFE/FT/P 5310 & INVP 5311                                 -            _.
600V AC MCC 1EMXJ x
INSTR. LOOP CONTAINING 1NVFE/FT/P 5320 & INVP 5321 INSTR. LOOP CONTAINING INVFE/FT/P 5330 & 1NVP 5331                                                               I INSTR. LOOP CONTAINING 1NVPT/P 5620 & INVP 5621 INSTR. LOOP CONTAINING 1NVFE/FT/P 6080 Included In SUPPORT FOR RN SYSTEM                                                         Seismic PRA 4160V AC SWITCHGEAR IETA (IETB)                                                                 x 600V AC MCC 1EMXA                                                                         _          _X 600V AC MCC IEMXE (IEMXF)                                             _      _x 600V AC MCC IEMXG                                                                               x 600V AC MCC 1EMXJ                                                                               x 600V AC MCC IEMXO                                                                               x 600V AC MCC IEMXQ (1EMXR)                             _                                          X           I 600V AC MCC 2EMXH                                     _                                          x 600V AC MCC 2EMXP_                                                             _  _            x 600V AC LOAD CENTER IELXA x             --
600V AC MCC 1EMXL x
125V DC DISTRIBUTION CENTER IEDE (IEDF)         _                                              X 120V DC PANELBOARD IERPA                                         "      ___                    xi_
125V DC DISTRIBUTION CENTER ]EDE (OEDF)
9 INSTR. LOOP CONTAINING ORNLT/P 7350 INSTR. LOOP CONTAINING ORNLT/P 7380 INSTR. LOOP CONTAINING ORNTT/P 8130         , .,          __
X 120V DC PANELBOARD I ERPC X
Page 4 Attachment 1 Page 28 of 36
INSTR. LOOP CONTAINING 1NVFE/Fr/CR5120 & I NVFT/CR5121 INSMTR LOOP CONTAINING 1NVFE/FT5130 & 1NVFT5131I INSTR. LOOP CONTAINING 1NVFE/FT/CR5140 & INVFT/CR5141 INSTR. LOOP CONTAINING 1NVFE/FT5150 & 1NVFT5W11 INST.
LOOP CONTAINING INVFE/FT/P 5300 & INVP5301 INSHTR. LOOP CONTAINING INVFE/FT/P 5310 & INVP 5311 INSTR. LOOP CONTAINING 1NVFE/FT/P 5320 & INVP 5321 INSTR. LOOP CONTAINING INVFE/FT/P 5330 & 1NVP 5331 I
INSTR. LOOP CONTAINING 1 NVPT/P 5620 & I NVP 5621 INSTR. LOOP CONTAINING 1 NVFE/FT/P 6080 Included In SUPPORT FOR RN SYSTEM Seismic PRA 4160V AC SWITCHGEAR IETA (IETB) x 600V AC MCC 1EMXA
_X 600V AC MCC IEMXE (IEMXF)
_x 600V AC MCC IEMXG x
600V AC MCC 1EMXJ x
600V AC MCC IEMXO x
600V AC MCC IEMXQ (1EMXR)
X I
600V AC MCC 2EMXH x
600V AC MCC 2EMXP_
x 600V AC LOAD CENTER IELXA x
125V DC DISTRIBUTION CENTER IEDE (IEDF)
X 120V DC PANELBOARD IERPA xi_
INSTR. LOOP CONTAINING ORNLT/P 7350 9 INSTR. LOOP CONTAINING ORNLT/P 7380 INSTR. LOOP CONTAINING ORNTT/P 8130 Page 4 Page 28 of 36


CNC-1 206.03-00-0203 Rev 0 Attachment 1A Page 29 of 36 TABLE 3 -                                               U     024
CNC-1 206.03-00-0203 Rev 0 A Page 29 of 36 TABLE 3 -
_____....            ... . . ............ __      Included In ,
U 024
SUPPORT FOR RN SYSTEM (CONT,)_                                                               Seismic PRA
,J
,J    INSTR. LOOP CONTAINING INSTR. LOOP CONTAINING 1RNTE/IT/P 5000 1RNPT/PS/P 5020 (5010)
)
(5030)
Included In,
INSTR. LOOP CONTAINING     1RNFE/FT/P 5800 (5850)
SUPPORT FOR RN SYSTEM (CONT,)_
INSTR. LOOP CONTAINING       1RNFE/FT/P 5930 (5980)
Seismic PRA INSTR. LOOP CONTAINING 1RNTE/IT/P 5000 (5010)
INSTR. LOOP CONTAINING     1RNFE/FT/P 6290 (6340)
INSTR. LOOP CONTAINING 1 RNPT/PS/P 5020 (5030)
INSTR. LOOP CONTAINING       IRNLT/P 7400 (7370)                                                               -  -
INSTR. LOOP CONTAINING 1RNFE/FT/P 5800 (5850)
INSTR. LOOP CONTAINING       1PNTE/T/..P 7460 (7430)             .....
INSTR. LOOP CONTAINING 1RNFE/FT/P 5930 (5980)
INSTR. LOOP CONTAINING       I RNPT/PS/P 7480 (7470)                                       ......
INSTR. LOOP CONTAINING 1RNFE/FT/P 6290 (6340)
INSTR. LOOP CONTAINING       IRNFE/FT/P 7520 (75 1O) iNSTR. LOOP CONTAINING       2RNLT/P 7400 (7370 Included In REACTOR PROTECTION SYSTEM                                                                 Seismic PRA REACTOR TRIP BREAKER A (B)
INSTR. LOOP CONTAINING IRNLT/P 7400 (7370)
INSTR. LOOP CONTAINING 1 PNTE/T/..P 7460 (7430)
INSTR. LOOP CONTAINING I RNPT/PS/P 7480 (7470)
INSTR. LOOP CONTAINING IRNFE/FT/P 7520 (75 1O) iNSTR. LOOP CONTAINING 2RNLT/P 7400 (7370 Included In REACTOR PROTECTION SYSTEM Seismic PRA REACTOR TRIP BREAKER A (B)
REACTOR TRIP BYPASS BREAKER A (B)
REACTOR TRIP BYPASS BREAKER A (B)
Included In
Included In SUPPORT FOR SA, SM. SV SYSTEMS Seismfc PRA 600V AC MCC IEMXC x
)          SUPPORT FOR SA, SM. SV SYSTEMS                                                               Seismfc PRA 600V AC MCC IEMXC                                                                                         x 600V AC MCC IEMXD                                                                                         x 600V AC MCC IEMXK                                                                                         x 600V AC MCC IEMXL                                                                                         X 125V DC PANELBOARD 1EPA                                                                                   X 125V DC PANELBOARD IEPD                                                                                   x 120V AC PANELBOARD IERPA                                                       __._                      x 120V AC PANELBOARD IERPD                                       ,                                        x INSTR. LOOP CONTAINING ISALL/SVX02O & ISALL/SVOO2i INSTR. LOOP CONTAINING ISMLLOO)0 thru 0015 & ISMSV00lOOfhru 0013 INSTR. LOOP CONTAINING ISMLL0030 Ihnu 0035 & ISMSVOO30 fhru 0033 INSTR. LOOP CONTAINING ISMLLOU5O thru 0055 & ISMSVO050 thru 0053 tNSTR. LOOP CONTAINING ISMLL0070 thru 0075 & 1SMSVO070 thru 0073 iNSTR. LOOP CONTAINING ISMLL/SV/MLOO90 & ISVLL/SVOO91 INSTR. LOOP CONTAINING ISMLL/SV/MLO0O0 & ISVLL/SVO110 1 INSTR. LOOP CONTAINING ISMLL/SV/ML0O1 & ISVLL/SVO 111 INSTR. LOOP CONTAINING 1SMLL/SV/ML0120 & I.SVLL/SV0121                         _
600V AC MCC IEMXD x
INSTR. LOOP CONTAINING ISMFE/FT/P 5000 & 1SMFT/P 5010 INSTR. LOOP CONTAINING ISMFE/FT/P 5020 & ISMFT/P 5030 INSTR. LOOP CONTAINING 1SMFE/FT/P 5040 & 1SMFT/P 5050 INSTR. LOOP CONTAINING ISMPT/CR/P 6080 INSTR. LOOP CONTAINING.ISMPT/P 5090      M_
600V AC MCC IEMXK x
1 INSTR. LOOP CONTAINING I SMFE/FT/P 5060 & I SMFT/P 5070
600V AC MCC IEMXL X
_  I INSTR, LOOP CONTAINING 1SMPT/P 5T00                   _... _                                                  -
125V DC PANELBOARD 1EPA X
Page 5 Attachment 1 Page 29 of 36
125V DC PANELBOARD IEPD x
120V AC PANELBOARD IERPA x
120V AC PANELBOARD IERPD x
INSTR. LOOP CONTAINING ISALL/SVX02O & ISALL/SVOO2i INSTR. LOOP CONTAINING ISMLLOO)0 thru 0015 & ISMSV00lOOfhru 0013 INSTR. LOOP CONTAINING ISMLL0030 Ihnu 0035 & ISMSVOO30 fhru 0033 INSTR. LOOP CONTAINING ISMLLOU5O thru 0055 & ISMSVO050 thru 0053 tNSTR. LOOP CONTAINING ISMLL0070 thru 0075 & 1SMSVO070 thru 0073 iNSTR. LOOP CONTAINING ISMLL/SV/MLOO90 & ISVLL/SVOO91 INSTR. LOOP CONTAINING ISMLL/SV/MLO0O0  
& ISVLL/SVO110 1 INSTR. LOOP CONTAINING ISMLL/SV/ML0O1  
& ISVLL/SVO 111 INSTR. LOOP CONTAINING 1SMLL/SV/ML0120 & I.SVLL/SV0121 INSTR. LOOP CONTAINING ISMFE/FT/P 5000 & 1SMFT/P 5010 INSTR. LOOP CONTAINING ISMFE/FT/P 5020 & ISMFT/P 5030 INSTR. LOOP CONTAINING 1SMFE/FT/P 5040 & 1SMFT/P 5050 INSTR. LOOP CONTAINING I SMFE/FT/P 5060 & I SMFT/P 5070 INSTR. LOOP CONTAINING ISMPT/CR/P 6080 1 INSTR. LOOP CONTAINING.ISMPT/P 5090 M_
I INSTR, LOOP CONTAINING 1SMPT/P 5T00 Page 5 Page 29 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 30 of 36 TABLE 3 -                                                 1   025
CNC-1206.03-00-0203 Rev 0 A Page 30 of 36 TABLE 3 -
                                            ! -Included
1 025
_ _ _........            _                            In SUPPORT FOR SA, SM, SV SYSTEMS (cont.)         -,                                        Seismic PRA   _
-Included In SUPPORT FOR SA, SM, SV SYSTEMS (cont.)
INSTR. LOOP CONTAINING ISMPT/P 5110 INSTR. LOOP CONTAINING 1SMPT/P 5120 & ISMCR5800     D_
Seismic PRA INSTR. LOOP CONTAINING ISMPT/P 5110 INSTR. LOOP CONTAINING 1SMPT/P 5120 & ISMCR5800 D_
INSTR. LOOP CONTAINING 1SMPT/P 5130                             ......
INSTR. LOOP CONTAINING 1SMPT/P 5130 INSTR. LOOP CONTAINING 1SMPT/P 5140 INSTR. LOOP CONTAINING ISMPT/P 5150 INSTR. LOOP CONTAINING 1SMPT/P 5160 i
INSTR. LOOP CONTAINING 1SMPT/P 5140                                                 ....
INSTR. LOOP CONTAINING ISMPT/P 5170 INSTR, LOOP CONTAINING ISMPT/P 5180 INSTR. LOOP CONTAINING 1SMP1/P 5190 INSTR. LOOP CONTAINING ISVEP/MLO010; & 1SVSVOOI 1 thru 0017 INSTR. LOOP CONTAINING ISVEP/MLOO70; & ISVSV071 thru 0077 INSTR. LOOP CONTAINING 1ISVEP/MLO 130; & ISVSVOI31 thru 0137 INSTR. LOOP CONTAINING 1SVEP/ML0190; & 1SVSVO191 thru 0197 Included In
INSTR. LOOP CONTAINING ISMPT/P 5150                           ......
___Seismic PRA SOLID STATE PROTECTION SYSTEM
INSTR. LOOP CONTAINING 1SMPT/P 5160                               i         _    .
_x Included In SUPPORT FOR VA SYSTEM Seismic PRA POWER SUPPLY FOR VA SYSTEM INSTR. LOOP CONTAINING 1VAPT/P 5000 (5020)
INSTR. LOOP CONTAINING ISMPT/P 5170                                             _ ..
X INSTR. LOOP CONTAINING 1 VAFE/P 5280 Included in SUPPORT FOR VC SYSTEM Seismic PRA 4160V AC SWIWCHGEAR IETA (2ETB) 60DV AC MCC 1EMXG (2EMXH) 120V AC PANELBOARD IEKPG (2EKPH) 600/120V AC TRANSFORMER IEKTG INSTR, LOOP CONTAINING IVCPT/P 5160 x
INSTR, LOOP CONTAINING ISMPT/P 5180                                                           _      __
/_
INSTR. LOOP CONTAINING 1SMP1/P 5190                   ____          ______
Included in SUPPORT FOR YC SYSTEM Seismic PRA 600V AC MCC 1EMXG INSTR. LOOP CONTAINING 0YCFE/ff/P 5000 (5010)
INSTR. LOOP CONTAINING ISVEP/MLO010; & 1SVSVOOI 1thru 0017 INSTR. LOOP CONTAINING ISVEP/MLOO70; & ISVSV071 thru 0077 INSTR. LOOP CONTAINING 1ISVEP/MLO 130; & ISVSVOI31 thru 0137 INSTR. LOOP CONTAINING 1SVEP/ML0190; & 1SVSVO191 thru 0197                         -
Page 6 Page 30 of 36
Included In
___Seismic                           PRA SOLID STATE PROTECTION SYSTEM             _x Included In SUPPORT FOR VA SYSTEM                                                           Seismic PRA POWER SUPPLY FOR VA SYSTEM INSTR. LOOP CONTAINING 1VAPT/P 5000 (5020)                                                       X INSTR. LOOP CONTAINING 1VAFE/P 5280                     ,,,                _,,
Included in SUPPORT FOR VC SYSTEM                                                           Seismic PRA 4160V AC SWIWCHGEAR IETA (2ETB) 60DV AC MCC 1EMXG (2EMXH)                   ,__
120V AC PANELBOARD IEKPG (2EKPH)                             -
600/120V AC TRANSFORMER IEKTG               .,___
INSTR, LOOP CONTAINING IVCPT/P 5160           .,      ___                                        x
                                              /_                                           Included in SUPPORT FOR YC SYSTEM                                 '                        Seismic PRA 600V AC MCC 1EMXG                                 ___
INSTR. LOOP CONTAINING 0YCFE/ff/P 5000 (5010)
Page 6 Attachment 1 Page 30 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 31 of 36 TABLE 4 -
CNC-1206.03-00-0203 Rev 0 A Page 31 of 36 TABLE 4 -
N       026 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNITI IPEEE WALKDOWN                     ___'"..
N 026 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNITI IPEEE WALKDOWN CONTAINMENT ISOLATION VALVES Penetr.
CONTAINMENT ISOLATION VALVES           Penetr.                     l               _Valve             Position AND PENETRATIONS                   No.         Valve No.         Line Size (in.) Norm       Fall I Shut. Post UPPER COMPARTMENr PURGE INLET                 M456             1VPIB                   24         C     C       C     C UPPER COMPARTMENT PURGE INLET                 M456             1VP2A'                 24         CC             C     C UPPER COMPARTMENT PURGE INLET           --    WM432           1VP3B                   24           C     C       C     C UPPER COMPARTMENT PURGE INLET                 M432             I VP4A                 24         C     C       C     C LOWER COMPARTMENT PURGE INLET                 M357             1VP6B                  24           C I._     C       C     C LOWER COMPARTMENT PURGE INLET                 M357             lVPTA                   24         C     C       C     C LOWER COMPARTMENT PURGE INLET                 M434             IVP8B                   24         LC     C       C     C LOWER COMPARTMENT PURGE INLET                 M434             I VP9A                 24         C     C       C     C CONT. PURGE EXHAUST                           M368           IVP10A                   24         C     C     C       C CONT. PURGE EXHAUST                           M368           1VP11B                   24         C     C       C     C CONT. PURGE EXHAUST                           M433           1VP12A                   24         C     C     C       C CONT. PURGE EXHAUST                           M433           IVP13B                   24         C     C       C       C CONT. PURGE EXHAUST                           M119           1VPISA                   24         C     C     C       C CONT. PURGE EXHAUST                           MI 19           1VP16B                   24         LC     C       C       C INCORE INSTR. ROOM PURGE IN                   M213           IVP17A                   12         C     C       C       C INCORE INSTR. ROOM PURGE IN                   M213           1VP18B                   12         LC     C       C     C
l
  )WRE   INSTR. ROOM PURGE OUT RE INSTR. ROOM PURGE OUT M140 M140 IVP19A 1VP20B 12 12 1C LC C
_Valve Position AND PENETRATIONS No.
Valve No.
Line Size (in.) Norm Fall I Shut.
Post UPPER COMPARTMENr PURGE INLET M456 1VPIB 24 C
C C
C UPPER COMPARTMENT PURGE INLET M456 1VP2A' 24 CC C
C UPPER COMPARTMENT PURGE INLET WM432 1VP3B 24 C
C C
C UPPER COMPARTMENT PURGE INLET M432 I VP4A 24 C
C C
C LOWER COMPARTMENT PURGE INLET M357 1 VP6B 24 I._
C C
C C
LOWER COMPARTMENT PURGE INLET M357 lVPTA 24 C
C C
C LOWER COMPARTMENT PURGE INLET M434 IVP8B 24 LC C
C C
LOWER COMPARTMENT PURGE INLET M434 I VP9A 24 C
C C
C CONT. PURGE EXHAUST M368 IVP10A 24 C
C C
C CONT. PURGE EXHAUST M368 1VP11B 24 C
C C
C CONT. PURGE EXHAUST M433 1VP12A 24 C
C C
C CONT. PURGE EXHAUST M433 IVP13B 24 C
C C
C CONT. PURGE EXHAUST M119 1VPISA 24 C
C C
C CONT. PURGE EXHAUST MI 19 1VP16B 24 LC C
C C
INCORE INSTR. ROOM PURGE IN M213 IVP17A 12 C
C C
C INCORE INSTR. ROOM PURGE IN M213 1VP18B 12 LC C
C C
)WRE INSTR. ROOM PURGE OUT M140 IVP19A 12 1C C
C C
RE INSTR. ROOM PURGE OUT M140 1VP20B 12 LC C
C C
CONT. AIR RELEASE M386 1VQ2A 4
C C
C C
CONT. AIR RELEASE M386 1VQ3B 4
C Al C
C CONT. AIR ADDITION M204 1VQ]5B 4
C At C
C CONT. AIR ADDITION M204 1VQ16A 4
C C
C C
C C
C C
C CONT. AIR RELEASE                              M386            1VQ2A                    4        C      C      C      C CONT. AIR RELEASE                              M386            1VQ3B                    4          C      Al      C      C CONT. AIR ADDITION                            M204          1VQ]5B                    4          C      At      C      C CONT. AIR ADDITION                            M204          1VQ16A                    4          C      C      C      C CONT. HYDROGEN PURGE OUTLET LINE               M346           1VY17A                   4         C     Al     C     C CONT. HYDROGEN PURGE OUTLET LINE             M346             WV18B                   4         C     Al     C     C VENT. UNIT CONDENSATE DRAIN HDR.               M221         IWL867A                   4         0     Al     0     C VENT. UNIT CONDENSATE DRAIN HDR.             M221           1WL869B                   4         0     A-Ad   0     C EQUIPMENT HATCH                                                                       240         C
CONT. HYDROGEN PURGE OUTLET LINE M346 1VY17A 4
* _C   C PERSONNEL HATCH                               .... ___115                                         C_**_C               C LOWER PERSONNEL AIR LOCK                     C100               ........                        ..    ..      ..    ..
C Al C
UPPER PERSONNEL AIR LOCK                       C300......
C CONT. HYDROGEN PURGE OUTLET LINE M346 WV18B 4
C Al C
C VENT. UNIT CONDENSATE DRAIN HDR.
M221 IWL867A 4
0 Al 0
C VENT. UNIT CONDENSATE DRAIN HDR.
M221 1WL869B 4
0 A-Ad 0
C EQUIPMENT HATCH 240 C
_C C
PERSONNEL HATCH  
.... ___115 C_**_C C
LOWER PERSONNEL AIR LOCK C100 UPPER PERSONNEL AIR LOCK C300......
PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)
PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)
PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 6XOV AC MCC I EMXC: (I EMXD)_______
PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 6XOV AC MCC I EMXC: (I EMXD)_______
600V AC MCC 1EMXK (I1EMXB)____
600V AC MCC 1 EMXK (I1EMXB)____
60XV AC MCC I MXM____                                                                                 __
60XV AC MCC I MXM____
600V AC MCC IMXO p
600V AC MCC IMXO 600V AC MCC 1MXR p
600V AC MCC 1MXR I!-
I!-
Page 1 j2 Attachment 1 Page 31 of 36
Page 1 j2 Page 31 of 36


CNC- 1206.03-00-0203 Rev 0 Attachment 1A Page 32 of 36 TABLE 4 -
CNC-1206.03-00-0203 Rev 0 A Page 32 of 36 TABLE 4 -
EI         0     I?
EI 0
                                              ,..  .Una..       Included In   Press. bndry.
I?
U&   HYDROGEN MITIGATION SYSTEM                 bize (In.)   Seismic PRA   integrry only GLOW PLUG IGNITERS                                             _                                            .....
.Una..
600V AC MCC IEMXI (QEMXB)                                                                                   __.______
Included In Press. bndry.
600/V20V ACTRANSFORMER         XFMR0013 (14)                               !......                                        ......
U&
HYDROGEN MITIGATION SYSTEM bize (In.)
Seismic PRA integrry only GLOW PLUG IGNITERS 600V AC MCC IEMXI (QEMXB) 600/V20V ACTRANSFORMER XFMR0013 (14)
ICE BASKETS & DOORS__
ICE BASKETS & DOORS__
Une       Included in   Press. bndry. _.__
Une Included in Press. bndry.
NS SYSTEM                       Size (in.)   Seismic PRA   Integrity only_..                                .
NS SYSTEM Size (in.)
Seismic PRA Integrity only_..
NS PUMP 1A (1B)
NS PUMP 1A (1B)
NS HX IA (18),!                                   _                                                  .......
NS HX IA (18),!
MOV 1NS18A                                           12 MOV 1NS29A (32A)                                     8 4160V AC SWITCHGEAR 1ETA (0ETB)                                                                   -
MOV 1NS18A 12 MOV 1NS29A (32A) 8 4160V AC SWITCHGEAR 1ETA (0ETB)
  "    AC MCC IEMXA
AC MCC IEMXA
  .I"DCPANELBOARD )EIDE (IEDF]
.I"DCPANELBOARD )EIDE (IEDF]
Une       Included in   Press, bndry,               .    ............    .
Une Included in Press, bndry, VX SYSTEM Size (in.)
VX SYSTEM                       Size (in.)   Seismic PRA   Integrity only                   ..
Seismic PRA Integrity only AIR-OP. DAMPER 1ARF-D-5 (-8)
AIR-OP. DAMPER 1ARF-D-5 (-8)
AIR-OP. DAMPER 1ARF-D-6 (-9)
AIR-OP. DAMPER 1ARF-D-6 (-9)
AIR-OP. DAMPER 1ARF-D-7 (-10)                                                                                     _      !        .
AIR-OP. DAMPER 1ARF-D-7 (-10)
MOTOR-OP. DAMPER IARF-D-2 (-4)                                                                                           I CONTAINMENT AIR RETURN FAN I A ()IB--                                                                   -
MOTOR-OP. DAMPER IARF-D-2 (-4)
600V AC MCC I EMXK ( EMXL) 120V AC PANELBOARD 1EKPI (IEKPB)                             -
I CONTAINMENT AIR RETURN FAN I A ()I B--
9 Page 2 Attachment 1 Page 32 of 36
600V AC MCC I EMXK ( EMXL) 120V AC PANELBOARD 1EKPI (IEKPB) 9 Page 2 Page 32 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 33 of 36 TABLE 5 -
CNC-1206.03-00-0203 Rev 0 A Page 33 of 36 TABLE 5 -
                                                                                                                  ~I   02s CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2 IPEEE WALKDOWN CONTAINMENT ISOLATION VALVES                     Penetr,                                               Valve Posliiorn AND PENETRATIONS                           No.             Volve No. Une Size (in.) Norm     Foil Shut. Post UPPER   COMPARTMENT PURGE INLET                           M     -4           2VPIB                     C       C     C         c-UPPER COMPARTMENT PURGE INLET                           M456
~I 02s CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2 IPEEE WALKDOWN CONTAINMENT ISOLATION VALVES
                                                                      .24 2VP2A       24           c       C     C         C UPPER COMPARTMENT PURGE INLET                           M432                 2VP3B       24           C       C     C         C UPPER COMPARTMENT PURGE INLET                           M432         -      2VP4A       24           C   -- C     C__       C LOWER COMPARTMENT PURGE INLET                           M357                 2VP6B       24           LC       C     C         C LOWER COMPARTMENT PURGE INLET                           M357                 2VP7A       24           LC       C     C         C LOWER COMPARTMENT PURGE INLET                           M434                 2VP8B       24         -LC       6     C         C LOWER COMPARTMENT PURGE INLET                           M434                 2VPgA       24           IC       C     C       C CONT. PURGE EXHAUST                             ._      M434               2VP10A O       24           C       C     C         C CONT. PURGE EXHAUST                                     M368               2VPIOB       24           C       C     C         C CONT. PURGE EXHAUST                                     M433               2VP) 2A       24           C       C     C         C CONT. PURGE EXHAUST                                     M433               2VP13B       24           C       CC               C
: Penetr, Valve Posliiorn AND PENETRATIONS No.
-CONT. PURGE EXHAUST                                     Ml19                 2VPI5A       24           C       C     C         C CONT. PURGE EXHAUST                                     M1 19               2VP16B       24           LC       C     C         C INCORE INSTR. ROOM PURGE IN                             M213               2VPI7A         12           C       C     C         C INCORE INSTR. ROOM PURGE IN                             M213                 2VP18B       12           LC       C     C         C INSTR. ROOM PURGE OUT
Volve No.
      -1IRE                                              M14D               2VPI9A         12           C       C   *C         C RE INSTR. ROOM PURGE OUT                         M140                 2VP20B       12           LC     C     C-         C CONT. AIR RELEASE                                       M386                 2VQ2A         4           C       C   C           C CONT. AIR RELEASE                                       M386                 2VQ3B   1     4           C       Al   C           C CONT. AIR ADDMON                                         M204               2VQ 158       4           C       Al     C C           -
Une Size (in.) Norm Foil Shut.
CONT. AIR ADDmON                                         M204         I 2VQ16A             4           C       C     C           C CONT. HYDROGEN PURGE OUTLET LINE                         M346               2w17A         4           C       Al   C           C CONT. HYDROGEN PURGE OUTLET LINE                         M346               2VY18B         4           C       Al   C           C VENT. UNIT CONDENSATE DRAIN HDR.                         M221               2WL867A         4           0       Al   0           C VENrT. UNIT CONDENSATE DRAIN HDR.                       M221               2WL869B         4           0       Al   0           C EQUIPMENT HATCH                   _........                              _-                240                         C _C-PERSONNEL HATCH                                       ........                            115           C             C           C LOWER PERSONNEL AIR LOCK                         j       C 10       -                                      '
Post UPPER COMPARTMENT PURGE INLET M  
UPPER PERSONNEL AIR LOCK PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)                                       ____
-4 2VPIB  
PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC (2EMXD)                       ,- .                                                                      .......
.24 C
60OV AC MCC 2EMXK (2EMXB) 600 VAC MCC 2MXM                                                         ___
C C
600 VAC MCC 2MXO                           ___
c-UPPER COMPARTMENT PURGE INLET M456 2VP2A 24 c
600 VAC MCC 2MXR                                                                                         .    .
C C
9 Page 1 D:                                                                                   Attachment 1 Page 33 of 36
C UPPER COMPARTMENT PURGE INLET M432 2VP3B 24 C
C C
C UPPER COMPARTMENT PURGE INLET M432 2VP4A 24 C  
-- C C__
C LOWER COMPARTMENT PURGE INLET M357 2VP6B 24 LC C
C C
LOWER COMPARTMENT PURGE INLET M357 2VP7A 24 LC C
C C
LOWER COMPARTMENT PURGE INLET M434 2VP8B 24  
-LC 6
C C
LOWER COMPARTMENT PURGE INLET M434 2VPgA 24 IC C
C C
CONT. PURGE EXHAUST M434 2VP10A O
24 C
C C
C CONT. PURGE EXHAUST M368 2VPIOB 24 C
C C
C CONT. PURGE EXHAUST M433 2VP) 2A 24 C
C C
C CONT. PURGE EXHAUST M433 2VP13B 24 C
CC C
-CONT. PURGE EXHAUST Ml19 2VPI5A 24 C
C C
C CONT. PURGE EXHAUST M1 19 2VP16B 24 LC C
C C
INCORE INSTR. ROOM PURGE IN M213 2VPI7A 12 C
C C
C INCORE INSTR. ROOM PURGE IN M213 2VP18B 12 LC C
C C
-1IRE INSTR. ROOM PURGE OUT M14D 2VPI9A 12 C
C  
*C C
RE INSTR. ROOM PURGE OUT M140 2VP20B 12 LC C
C-C CONT. AIR RELEASE M386 2VQ2A 4
C C
C C
CONT. AIR RELEASE M386 2VQ3B 1
4 C
Al C
C CONT. AIR ADDMON M204 2VQ 158 4
C Al C C CONT. AIR ADDmON M204 I
2VQ16A 4
C C
C C
CONT. HYDROGEN PURGE OUTLET LINE M346 2w17A 4
C Al C
C CONT. HYDROGEN PURGE OUTLET LINE M346 2VY18B 4
C Al C
C VENT. UNIT CONDENSATE DRAIN HDR.
M221 2WL867A 4
0 Al 0
C VENrT. UNIT CONDENSATE DRAIN HDR.
M221 2WL869B 4
0 Al 0
C EQUIPMENT HATCH 240 C
_C-PERSONNEL HATCH 115 C
C C
LOWER PERSONNEL AIR LOCK j C 10 UPPER PERSONNEL AIR LOCK PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)
PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC (2EMXD) 60OV AC MCC 2EMXK (2EMXB) 600 VAC MCC 2MXM 600 VAC MCC 2MXO 600 VAC MCC 2MXR 9
Page 1 D:
Page 33 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 34 of 36 TAgLE 5 -
CNC-1206.03-00-0203 Rev 0 A Page 34 of 36 TAgLE 5 -
O29 line         Included In   Press. bndry.
O 29 line Included In Press. bndry.
_,*" HYDROGEN MITIGATION SYSEM                 Size (In.)   Seismic PRA   integrity only_
_,*" HYDROGEN MITIGATION SYSEM Size (In.)
Seismic PRA integrity only_
GLOW PLUG IGNITERS 600V AC MCC 2EMXI (2EMXB) 600/120V AC TRANSFORMER 2XFMROO] 3 (14)
GLOW PLUG IGNITERS 600V AC MCC 2EMXI (2EMXB) 600/120V AC TRANSFORMER 2XFMROO] 3 (14)
ICE BASKETS       & DOORS Une         Included In   Press. bndry,         -,
ICE BASKETS & DOORS Une Included In Press. bndry, NS SYSTEM Size (in,)
NS SYSTEM                     Size (in,)     Seismic PRA   Integrity only" NS PUMP 2A (28)     .......
Seismic PRA Integrity only" NS PUMP 2A (28)
NS HX 2A (2B)
NS HX 2A (2B)
MOV 2NS18A                                           12 MOV 2NS29A (32A)                                     8 4160V AC SWlTCHGEAR 2ETA (2ETB)
MOV 2NS18A 12 MOV 2NS29A (32A) 8 4160V AC SWlTCHGEAR 2ETA (2ETB)
  "N,' AC MCC 2EMXA DC PANELBOARD 2EDE         (2EDF)
"N,' AC MCC 2EMXA DC PANELBOARD 2EDE (2EDF)
Une         Included In   Press. bndry. :
Une Included In Press. bndry. :
VX SYSTEM         ".          Size (in.)     Seismic PRA   integrity only_
VX SYSTEM Size (in.)
Seismic PRA integrity only_
AIR-OP. DAMPER 2ARF-D-5 (-8)
AIR-OP. DAMPER 2ARF-D-5 (-8)
AIR-OP. DAMPER 2ARF-D-6 (-9).
AIR-OP. DAMPER 2ARF-D-6 (-9).
AIR-OP. DAMPER 2ARF-D-7 (-10)
AIR-OP. DAMPER 2ARF-D-7 (-10)
MOTOR-OP. DAMPER 2ARF-D-2 (-4)
MOTOR-OP. DAMPER 2ARF-D-2 (-4)
CONTAINMENT AIR RETURN FAN 2A (28)           '.I
CONTAINMENT AIR RETURN FAN 2A (28)  
,600V AC MCIC 2EMXK (2EMXL)-                                                   ____
'.I
1-20V AC PANELBOARD 2EKPI (2EKPB)                             ,                        _
,600V AC MCIC 2EMXK (2EMXL)-
Page 2 D IDID 1-     :11                                                     Attachment 1 Page 34 of 36
1-20V AC PANELBOARD 2EKPI (2EKPB)
Page 2 D ID 1-ID
:11 Page 34 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 35 of 36 TABLE 5 -
CNC-1206.03-00-0203 Rev 0 A Page 35 of 36 TABLE 5 -
9     030 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2 A-                               101D       WAII YnfNfWMi7
9 030 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2 A-101D WAII YnfNfWMi7 U I ~ ~ ~ V.
      ....                                              U I ~~~ V.
CONTAINMENT ISOLATION VALVES Penelt.
CONTAINMENT ISOLATION VALVES           Penelt.                                           Valve Position_
Valve Position_
AND PENETRATIONS                 No.         Valve No. Line Size (In.) Norm     Fall Shut. Post UPPER COMPARTMENT PURGE INLET                 M456           2VP1B   -        24         -        C     CC--
AND PENETRATIONS No.
UPPER COMPARTMENT PURGE INLET                 M456           2VP2A             24           C _C        C       C UPPER COMPARTMENT PURGE INLET                 M432           2VP38             24           C     C     C       C UPPER COMPARTMENT PURGE INLET                 M432           2VP4A             24           C     C     C       C LOWER COMPARTMENT PURGE INLET               M357             2VP6B             24           IC     C     C -C LOWER COMPARTMENT PURGE INLET               M357             2VP7A.           24       _C       C     C       C LOWER COMPARTMENT PURGE INLET               M434             2VP8..           24           LC     C     C       C LOWER COMPARTMENT PURGE INLET               M434           2VP9A             24             C     C     C       C CONT. PURGE EXHAUST                           M368           2VP1OA           24             C     C     C       C CONT. PURGE EXHAUST                         M368           2VP1 1B           24             C     _            C CONT. PURGE EXHAUST                         M433       ._2VP12A               24           C   C     C       C CONT. PURGE EXHAUST                         M433           2VP 13B     _          _      -C -(       C       C CONT. PURGE EXHAUST                           M 119           2VP 15A           24             C   C     C       C CONT. PURGE EXHAUST                           Ml 19           2VP168           24           LC   C     C       C INCORE INSTR. ROOM PURGE IN                   M213           2VP17A             12           C     C     C       C INCORE INSTR. ROOM PURGE IN                   M213           2VPI88            12           LC   C     C       C INrr'"INSTR. ROOM PURGE OUT                   M140           2VP19A             12           C     C     C     C
Valve No.
* *INSTR. ROOM PURGEOUT                   -MM140             2VP20B           12           LC   C     C       C CuNI' AIR RELEASE                             M386           2VQ2A.             4           C     C     C       C CONT. AIR RELEASE                             M386           2VQ38             4           C -W               C CONT. AIR ADDITION                           M204           2VQ15B             4           C     Al   C       C CONT. AIR ADDITION                           M204           2VQ16A             4           C     C     C       C CONT. HYDROGEN PURGE OUTLET LINE             M346           2_ 7A               4           C   Al       C CONT. HYDROGEN PURGE OUTLET LINE             M346           2VY8B               4           C         I   C VENT. UNIT CONDENSATE DRAIN HDR.             M221         2WL867A               4           0   Al     0       C VENT. UNIT CONDENSATE DRAIN HDR.             M221         2WL8698     1     4             0   Al     0       C EQUIPMENT HATCH                               to..                           240           c             C c PERSONNEL HATCH .......                                                       116           C           G       C LOWER PERSONNEL AIR LOCK                     C_100                           so*...._...                     __
Line Size (In.) Norm Fall Shut.
C300                             too.
Post UPPER COMPARTMENT PURGE INLET M456 2VP1B 24 C
UPPER PERSONNEL AIR LOCK PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)--
CC--
UPPER COMPARTMENT PURGE INLET M456 2VP2A 24 C
C C
C UPPER COMPARTMENT PURGE INLET M432 2VP38 24 C
C C
C UPPER COMPARTMENT PURGE INLET M432 2VP4A 24 C
C C
C LOWER COMPARTMENT PURGE INLET M357 2VP6B 24 IC C
C  
-C LOWER COMPARTMENT PURGE INLET M357 2VP7A.
24
_C C
C C
LOWER COMPARTMENT PURGE INLET M434 2VP8..
24 LC C
C C
LOWER COMPARTMENT PURGE INLET M434 2VP9A 24 C
C C
C CONT. PURGE EXHAUST M368 2VP1OA 24 C
C C
C CONT. PURGE EXHAUST M368 2VP1 1B 24 C
C CONT. PURGE EXHAUST M433  
._2VP12A 24 C
C C
C CONT. PURGE EXHAUST M433 2VP 13B  
-C  
-(
C C
CONT. PURGE EXHAUST M 119 2VP 15A 24 C
C C
C CONT. PURGE EXHAUST Ml 19 2VP168 24 LC C
C C
INCORE INSTR. ROOM PURGE IN M213 2VP17A 12 C
C C
C INCORE INSTR. ROOM PURGE IN M213 2VPI8 8 12 LC C
C C
INrr'"INSTR. ROOM PURGE OUT M140 2VP19A 12 C
C C
C
*INSTR. ROOM PURGEOUT  
-MM140 2VP20B 12 LC C
C C
CuNI' AIR RELEASE M386 2VQ2A.
4 C
C C
C CONT. AIR RELEASE M386 2VQ38 4
C  
-W C
CONT. AIR ADDITION M204 2VQ15B 4
C Al C
C CONT. AIR ADDITION M204 2VQ16A 4
C C
C C
CONT. HYDROGEN PURGE OUTLET LINE M346 2_
7A 4
C Al C
CONT. HYDROGEN PURGE OUTLET LINE M346 2VY8B 4
C I
C VENT. UNIT CONDENSATE DRAIN HDR.
M221 2WL867A 4
0 Al 0
C VENT. UNIT CONDENSATE DRAIN HDR.
M221 2WL8698 1
4 0
Al 0
C EQUIPMENT HATCH to..
240 c
C c PERSONNEL HATCH.......
116 C
G C
LOWER PERSONNEL AIR LOCK C_100 so*...._...
UPPER PERSONNEL AIR LOCK C300 too.
PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)--
PERSONNEL AIR LOCK 208 V LINEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC (2EMXD) 600V AC MCC 2EMXI< C2EMXB)-
PERSONNEL AIR LOCK 208 V LINEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC (2EMXD) 600V AC MCC 2EMXI< C2EMXB)-
600 VAC MCC 2MXM                                                         _____
600 VAC MCC 2MXM 600 VAC MCC 2MXO 600 VAC MCC 2MXR Y
600 VAC MCC 2MXO 600 VAC MCC 2MXR                           _______                                                                _
Page )
Y Page )
ii If
ii If               1.                                                               Attachment 1 Page 35 of 36
: 1.
Page 35 of 36


CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 36 of 36 TABLE 5 -
CNC-1206.03-00-0203 Rev 0 A Page 36 of 36 TABLE 5 -
11   031
11 031
                                                    -t.     Line         Includedin                   bndrj.
-t.
MPress.
Line Includedin MPress.
kDROGEN MITIGATION SYSTEM                       Size(in.)       Seismic PRA         integil*l   O ...
bndrj.
kDROGEN MITIGATION SYSTEM Size(in.)
Seismic PRA i ntegil*l O
GLOW PLUG IGNITERS 600V AC MCC 2EMXI (2EMXB) 50/120V AC TRANSFORMER 2XFMR0013 (14)
GLOW PLUG IGNITERS 600V AC MCC 2EMXI (2EMXB) 50/120V AC TRANSFORMER 2XFMR0013 (14)
ICE BASKETS & DOORS iUne         Included in       -Press. bndy.                  ..
ICE BASKETS & DOORS iUne Included in  
NS SYSTEM                         Size (in.)     Seismic PRA         Integrity only.
-Press. bndy.
NIS PUMP2A (2B).                                                                                 -        -
NS SYSTEM Size (in.)
\JS HX 2A   (.2_
Seismic PRA Integrity only.
8) vlOV 2NS18A 8-                                             12 OV 2NS29A       ..A)                                     8 160V AC SWITCHGEAR 2ETA (2ETB)
NIS PUMP2A (2B).  
  &#xfd;&#xfd;- ).
\\JS HX 2A (.2_
JOV AC MCC 2EMXA PANELBOARD 2EDE (2EDF) iUne         Included in         Press. bndy.                         .,
8) vlOV 2NS18A 8-12 OV 2NS29A  
VX SYSTEM                         Size (in.)       Seismic PRA         integrity only.
..A) 8 160V AC SWITCHGEAR 2ETA (2ETB)
AI R-OP. DAMPER 2ARF-D-5 (-8) aIR-OP. DAM           2ARF-D-6 (-9)                                                                                   -_,
JOV AC MCC 2EMXA
AIR-OP. DAMW.... 2ARF-D-7 (-10)                                                                                 .....
&#xfd;&#xfd;- ).
PANELBOARD 2EDE (2EDF) iUne Included in Press. bndy.
VX SYSTEM Size (in.)
Seismic PRA integrity only.
AI R-OP. DAMPER 2ARF-D-5 (-8) aIR-OP. DAM 2ARF-D-6 (-9)
AIR-OP. DAMW.... 2ARF-D-7 (-10)
MOTOP-OP. DAMPER 2ARi-D-2 (-4)
MOTOP-OP. DAMPER 2ARi-D-2 (-4)
CONTAINMENT AIR RETURN FAN 2A           (2B)I                                                                                 ]
CONTAINMENT AIR RETURN FAN 2A (2B)I  
600V AC MCC 2EMXK (2EMXL)                               _        _.__
]
120V AC PANELBOARD 2E(PI (2EKPB)                                 .... _        _                                        ,__
600V AC MCC 2EMXK (2EMXL) 120V AC PANELBOARD 2E(PI (2EKPB) 9 Page 2 Page 36 of 36
9 Page 2 Attachment 1 Page 36 of 36


Sheet I of 4 Status: Y[D No U0 Area Walk-By Checklist (AWC)
Sheet I of 4 Status: Y[D No U0 Area Walk-By Checklist (AWC)
Location: Bldg. CVI             Floor El. 557             Room, Area, DEG 58 RIAD 40 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. CVI Floor El. 557 Room, Area, DEG 58 RIAD 40 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column Line or Other Location Info INV52A              IA NC Pump Seal Return                  El 557, 58 deg. Radius 40 ft.
Components: Equipment ID INV52A Description IA NC Pump Seal Return Column Line or Other Location Info El 557, 58 deg. Radius 40 ft.
Does anchorage of equipment in the area appear to be free of                       Y0 NO UO N/A[]
Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Y0 NO UO N/A[]
: 2. Does anchorage of equipment in the area appear to be free of significant YZ No U0 N/AD]
: 2. Does anchorage of equipment in the area appear to be free of significant YZ No U0 N/AD]
degraded conditions?
degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YE* NO U[        N/ALl raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YE* NO U[
N/ALl
'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC. INV52A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 11 of 105
AWC. INV52A.DOC CNC-1206.03-00-0203 Rev 1 A Page 11 of 105


Sheet 2 of 4 Status: YR NF-I UZ' Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: YR NF-I UZ' Area Walk-By Checklist (AWC)
Location: Bldg. CV]             Floor El. 557         . Room, Area, DEG 58 RAD 40
Location: Bldg. CV]
: 4. Does it appear that the area is free of potentially adverse seismic spatial YZ NO UO N/Al]
Floor El. 557  
interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
. Room, Area, DEG 58 RAD 40
: 5. Does it appear that the area is firee of potentially adverse seismic       YZ ND U1I N/AD interactions that could cause flooding or spray in the area?
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 6. Does it appear that the area is free of potentially adverse seismic       YZ ND UO N/AD interactions that could cause a fire in the area?
: 5. Does it appear that the area is firee of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 7. Does it appear that the area is free of potentially adverse seismic       YE* ND UD: N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 8. Have you looked for and found no other seismic conditions that could       Y0 ND UD1 adversely affect the safety functions of the equipment in the area?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
Near Azimuth 63, radius30, elevation 563, there is a empty piece of 4" electray hanging almost vertically with very few attachments. This component does not appearto be a seismic threat currently due to its low mass, and lack of sensitive targets below, but it does not appearto be serving any purpose, and it would be a good practice to remove it.
YZ NO UO N/Al]
YZ ND U1I N/AD YZ ND UO N/AD YE* ND UD: N/AD
: 8. Have you looked for and found no other seismic conditions that could Y0 ND UD1 adversely affect the safety functions of the equipment in the area?
Near Azimuth 63, radius 30, elevation 563, there is a empty piece of 4" electray hanging almost vertically with very few attachments. This component does not appear to be a seismic threat currently due to its low mass, and lack of sensitive targets below, but it does not appear to be serving any purpose, and it would be a good practice to remove it.
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
AWC - uNV52A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 12 of 105
AWC - uNV52A.DOC CNC-1206.03-00-0203 Rev 1 A Page 12 of 105


Sheet 3 of 4 Status: YZ NEI U-Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: YZ NEI U-Area Walk-By Checklist (AWC)
Location: Bldg. CVI         Floor El. 557   Room, Area, DEG 58 R_4D 40 Evaluated by: Thomas R Leich ,         ?--/'  "<'
Location: Bldg. CVI Floor El. 557 Room, Area, DEG 58 R_4D 40 Evaluated by: Thomas R Leich,  
* Date:           2       ,. r2,3 Ralp11017( F-11MI?~~~A>_&#x17d;_                             Date:     2__2 (2 AWC - INV52A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 13 of 105
?--/'
Date:
2  
,..r2,3 Ralp11017( F-11MI?~~~A>_&#x17d;_
Date:
2__2 (2 AWC - INV52A.DOC CNC-1206.03-00-0203 Rev 1 A Page 13 of 105


Sheet 4 of 4 Status: YZ N-' UD Area Walk-By Checklist (AWC)
Sheet 4 of 4 Status: YZ N-' UD Area Walk-By Checklist (AWC)
Location: Bldg. CV1           Floor El. 557       Room, Area, DEG 58 RAD 40 71 npty hanging piece of electray.(see 8)     Note:
Location: Bldg. CV1 Floor El. 557 Room, Area, DEG 58 RAD 40 71 npty hanging piece of electray. (see 8)
Note:                                               Note:
Note:
AWC-I NV52A. DOC CNC-1206.03-00-0203 Rev I Attachment 7A Page 14 of 105             _j.
Note:
Note:
AWC-I NV52A. DOC CNC-1206.03-00-0203 Rev I A Page 14 of 105
_j.
I
I


Sheet I of 3 Status: YE NI-         U-]
Sheet I of 3 Status: YE NI-U-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INV52A                               Equip. Class, 7 (AOV)
Equipment ID No. INV52A Equip. Class, 7 (AOV)
Equipment Description 1A NC Puma Seal Return Location: Bldg. CV1                     Floor El. 557           Room, Area DEG 58 RAD 40 Manufacturer, Model, Etc. (optional but recommended)                 Kerotest Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description 1A NC Puma Seal Return Location: Bldg. CV1 Floor El. 557 Room, Area DEG 58 RAD 40 Manufacturer, Model, Etc. (optional but recommended)
Kerotest Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one YO NED of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?           YE] NE UOE N/AZ
YO NED
: 3. Is the anchorage free of corrosion that is more than mild surface           YE NE UD- N/AZ oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?   YE NE UE N/AE
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?         YE NE UE N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of           YED NEI UE potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
I ntc)r the equipment class 11nac fromt Appendix 13:Classcs of Equipment.
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 15 of 105
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YE] NE UOE N/AZ YE NE UD-N/AZ YE NE UE N/AE YE NE UE N/AZ YED NEI UE I ntc)r the equipment class 11nac fromt Appendix 13: Classcs of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 15 of 105


Sheet 2 of 3 Status: YZ NE]         U]-
Sheet 2 of 3 Status: YZ NE] U]-
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No.       INV52A                     Equip. Class' 7 (AOV)
Equipment ID No.
INV52A Equip. Class' 7 (AOV)
Equipment Description IA NC Pump Seal Return Interaction Effects
Equipment Description IA NC Pump Seal Return Interaction Effects
: 7. Are soft targets fiee from impact by nearby equipment or structures?           YZ NEI UD N/AO
: 7. Are soft targets fiee from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ' NEI UI- N/AI]
YZ NEI UD N/AO
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ' NEI UI-N/AI]
and masonry block walls not likely to collapse onto the equipment?
and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?                   Y[l NI UDI N/AUI
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free           YN NO UO of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could           YZ NO] UF-adversely affect the safety functions of the equipment?
Y[l NI UDI N/AUI YN NO UO Other Adverse Conditions 1I.
Have you looked for and found no other seismic conditions that could YZ NO] UF-adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
There is a 2" line that will interact with the supporl steel for 1NV52A, But it is not massive enough to cause any damage. The support steel (Rigid) was originally cut to make room for the 2" line, so this condition was considered in the original design. The 2" line is a VB (BreathingAir) system line, and the interaction point is nol vety far from valve IVB1O. - See photo.
There is a 2" line that will interact with the supporl steel for 1NV52A, But it is not massive enough to cause any damage. The support steel (Rigid) was originally cut to make room for the 2" line, so this condition was considered in the original design. The 2" line is a VB (Breathing Air) system line, and the interaction point is nol vety far from valve IVB1O. - See photo.
Evaluated by:                                ;&#xfd;,     e,. Z               ., RZe-,'1cXDate:       /             / -P, (2-   ~- ~o IZ.
; &#xfd;,
J CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 16 of 105
e,. Z Evaluated by:
., RZe-,'1cXDate:  
/  
/ -P, (2- ~-  
~o IZ.
J CNC-1206.03-00-0203 Rev 1 A Page 16 of 105


Sheet 3 of 3 Status: YZ N[-       UE-Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: YZ N[-
Equipment ID No. 1NV52A                     Equip. Class1 Equipment Description 1A NC Pump Seal Return Photographs Note: 2" VB line close to steel for 1NV52A.               Note:
UE-Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NV52A Equip. Class1 Equipment Description 1A NC Pump Seal Return Photographs Note: 2" VB line close to steel for 1NV52A.
Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 17 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 17 of 105


Sheet 1 of 4 Status: YER NM UD Area Walk-By Checklist (AWC)
Sheet 1 of 4 Status: YER NM UD Area Walk-By Checklist (AWC)
Location: Bldg. CVJ                 Floor El. 560           Room, Area' DEG 46 RAD 47 PCHA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. CVJ Floor El. 560 Room, Area' DEG 46 RAD 47 PCHA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID               Description                     Column Line or Other Location Info IN154A            C-Leg Accum A Dischg. Isol 46 Deg, Rad 47 Elev 560 I. Does anchorage of equipment in the area appear to be free of                       Y(E ND-- U[D N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Components: Equipment ID IN154A Description Column Line or Other Location Info C-Leg Accum A Dischg. Isol 46 Deg, Rad 47 Elev 560 I. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Y(E ND--
U[D N/AD
: 2. Does anchorage of equipment in the area appear to be free of significant YO NO UD N/AD degraded conditions?
: 2. Does anchorage of equipment in the area appear to be free of significant YO NO UD N/AD degraded conditions?
: 3. Based on a visual inspection fiorn the floor, do the cable/conduit                   YZ ND UD N/AD]
: 3. Based on a visual inspection fiorn the floor, do the cable/conduit raceways and 1-VAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
raceways and 1-VAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YZ ND UD N/AD]
I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC - INI0054A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 18 of 105
AWC - INI0054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 18 of 105


Sheet 2 of 4 Status: YN NO U7 Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: YN NO U7 Area Walk-By Checklist (AWC)
Location: Bldg. CVI               Floor UL. 560           Room, Area' DEG 46 RAD 47 PCH-IA
Location: Bldg. CVI Floor UL. 560 Room, Area' DEG 46 RAD 47 PCH-IA
: 4. Does it appear that the area is free of potentially adverse seismic spatial         YO ND UD N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 5. Does it appear that the area is free of potentially adverse seismic                 YN ND UD N/AD interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic                 YC      ND UD N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic                 YZ ND U[-D N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could                 YO NZ UD adversely affect the safety functions of the equipment in the area?
YO ND UD N/AD YN ND UD N/AD YC ND UD N/AD YZ ND U[-D N/AD
Found loose locknut on pipe support for 1WL820. If not corrected, this had potential to allow support to work loose during operation, See comments section.
: 8. Have you looked for and found no other seismic conditions that could YO NZ UD adversely affect the safety functions of the equipment in the area?
Found loose locknut on pipe support for 1 WL820. If not corrected, this had potential to allow support to work loose during operation, See comments section.
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Some cable trays in area are full but acceptable. Noticed loose locknut on rod supporting IWL820. Wrote Work Request to get it fixed. One small 6" electray has an empty section that is very flexible, but it is not close or heavy enough to interact seismically with other components, AWC- IN10054A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 19 of 105
Some cable trays in area are full but acceptable. Noticed loose locknut on rod supporting I WL820. Wrote Work Request to get it fixed. One small 6" electray has an empty section that is very flexible, but it is not close or heavy enough to interact seismically with other components, AWC-I N10054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 19 of 105


Sheet 3 of 4 Status: Y[* NF U-Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: Y[* NF U-Area Walk-By Checklist (AWC)
Location: Bldg. CV]             Floor El. 560   Room, Area1 DEG 46 RAD 47PCHA Evaluated by: Thomas R Leitch     -          .Date:                           __/__________--_
Location: Bldg. CV]
Ravniond C Fung
Floor El. 560 Room, Area1 DEG 46 RAD 47PCHA Evaluated by: Thomas R Leitch  
                              ,7                                       Date:   2 7             2112I3 AWC - I NI0054A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 20 of 105
.Date:
__/__________--_
Ravniond C Fung  
,7 Date:
2 7 211 2I3 AWC - I NI0054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 20 of 105


Sheet 4 of 4 Status: YZ NF' U[']
Sheet 4 of 4 Status: YZ NF' U[']
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CV1             Floor El. 560   Room, Area, DEG 46 RAD 47 PCHA Note: Full tray with well restrained cables. See   Note:
Location: Bldg. CV1 Floor El. 560 Room, Area, DEG 46 RAD 47 PCHA Note: Full tray with well restrained cables. See Comments.
Comments.
Note:
LI~Uo: LUUOOLU*nIUL Uin ra     supporting I VVL     Note:
Note:
See Comments.
LI~Uo: LUUOO LU*nIUL Uin ra supporting I VVL See Comments.
AWC - I N10054A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 21 of 105
AWC - I N10054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 21 of 105


Sheet i of 3 Status: Y[     Nn U-Seismic Walkdown Checklist (SWC)
Sheet i of 3 Status: Y[
Equipment ID No. INIOO54A                         Equip. Class, 8 (MOV/SOV)
Nn U-Seismic Walkdown Checklist (SWC)
Equipment ID No. INIOO54A Equip. Class, 8 (MOV/SOV)
Equipment Description C-Lee Accum A Discharge Isol.
Equipment Description C-Lee Accum A Discharge Isol.
Location: Bldg. CVI                 Floor El. 560           Room, Area DEG 46     RAD 47 PCHA Manufacturer, Model, Etc. (optional but recommended)               Westinghouse 09J-2-09 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Location: Bldg. CVI Floor El. 560 Room, Area DEG 46 RAD 47 PCHA Manufacturer, Model, Etc. (optional but recommended)
Anchorage I. Is the anchorage configuration verification required (i.e., is the item one     YO NO of the 50% of SWEL items requiring such verification)?
Westinghouse 09J-2-09 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?               YOi NEI UE N/AM
Anchorage I. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 3. Is the anchorage free of corrosion that is more than mild surface               YED N[E UL N/AZ oxidation?
YO NO
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?       YE NEI     U-   N/AO
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 5. Is the anchorage configuration consistent with plant documentation?             YO- NEI UO- N/AN!
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
YOi NEI UE N/AM YED N[E UL N/AZ
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
YE NEI U-N/AO
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
YE NE UE
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
IE nter the equipment class name from Appendix B: Classes of E.quipment.
YO-NEI UO-N/AN!
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 22 of 105
YE NE UE IE nter the equipment class name from Appendix B: Classes of E.quipment.
CNC-1206.03-00-0203 Rev 1 A Page 22 of 105


Sheet 2 of 3 Status: YE NEI       ULI Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: YE NEI ULI Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NIO054A               Equip. Class, 8 (MOV/SOV)
Equipment ID No.
1NIO054A Equip. Class, 8 (MOV/SOV)
Equipment Description C-Leg Accum A Discharqe Isol.
Equipment Description C-Leg Accum A Discharqe Isol.
Interaction Effects
Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     YZ ND UD N/AD
: 7. Are soft targets free from impact by nearby equipment or structures?
YZ ND UD N/AD
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD and masonry block walls not likely to collapse onto the equipment?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YN ND UD N/AD
: 9. Do attached lines have adequate flexibility to avoid damage?
YN ND UD N/AD
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions
Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could     YE NDI UD adversely affect the safety functions of the equipment?
: 11. Have you looked for and found no other seismic conditions that could YE NDI UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
No problems observed, See drawing CN-1041-02 for plan view. Also, see CN-1491-NI.O0-043.
No problems observed, See drawing CN-1041-02 for plan view. Also, see CN-1491-NI.O0-043.
Evaluated by: 7-I-amy     s     4?d,,'YcA   .t-hez                             Date:   o Z*z       o/3.
Evaluated by:
                                                              -1~~'
7-I-amy s
2.;   ct3
4?
                                            .___j CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 23 of 105
d,,'YcA  
.t-hez Date:
o Z* z o/3.
-1~~'
2.;
ct3
.___j CNC-1206.03-00-0203 Rev 1 A Page 23 of 105


Sheet 3 of 3 Status: Y       S[] CRU-Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: Y S[] CRU-Seismic Walkdown Checklist (SWC)
Equipment ID No. 1N0054A               Equip. Class' 8 (MOV/SOV)
Equipment ID No. 1N0054A Equip. Class' 8 (MOV/SOV)
Equipment Description C-Leg Accum A Discharge Isol.
Equipment Description C-Leg Accum A Discharge Isol.
INOte: WV104A.                                       Note:
INOte:
Note:                                               Note:
WV104A.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 24 of 105
Note:
Note:
Note:
CNC-1206.03-00-0203 Rev 1 A Page 24 of 105


Sheet I of 4 Status: YZ ND-1 UQ1 Area Walk-By Checklist (AWC)
Sheet I of 4 Status: YZ ND-1 UQ1 Area Walk-By Checklist (AWC)
Location: Bldg. CVI             Floor El. 562             Room, Area' DEG 40 RAD 55 ACLA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. CVI Floor El. 562 Room, Area' DEG 40 RAD 55 ACLA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column Line or Other Location Info IN1438A          Emer N2 From CLA A to INC-34A                 Deg 40 Rad 55 ACLA
Components: Equipment ID IN1438A Description Column Line or Other Location Info Emer N2 From CLA A to INC-34A Deg 40 Rad 55 ACLA
: 1. Does anchorage of equipment in the area appear to be free of                       YZ NO U[] N/All]
: 1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
YZ NO U[] N/All]
: 2. Does anchorage of equipment in the area appear to be free of significant           YN Nil Ut] N/At degraded conditions?
: 2. Does anchorage of equipment in the area appear to be free of significant YN Nil Ut] N/At degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YN NEI Ut        N/AL raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
All cables appearadequately anchored and supported.
All cables appear adequately anchored and supported.
YN NEI Ut N/AL
'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC - IN)438A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 25 of 105
AWC - IN)438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 25 of 105


Sheet 2 of 4 Status: YZI N---] U-Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: YZI N---] U-Area Walk-By Checklist (AWC)
Location: Bldg. CVI             Floor El. 562             Room, Area, DEG 40 RAD 55 ACLA
Location: Bldg. CVI Floor El. 562 Room, Area, DEG 40 RAD 55 ACLA
: 4. Does it appear that the area is free of potentially adverse seismic spatial YNJ NE] U[        N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 5. Does it appear that the area is free of potentially adverse seismic         YZ NEI      U-    N/AD:1 interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic         Y[3 ND UD N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic         YN ND UM N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could         YN ND U adversely affect the safety functions of the equipment in the area?
YNJ NE] U[
Comments (Additional pages may be added as necessary)
N/AD YZ NEI U-N/AD:1 Y[3 ND UD N/AD YN ND UM N/AD
: 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?
YN ND U Comments (Additional pages may be added as necessary)
Some boron deposits were noted on tubing connected to INIPT5050, about 10' above floor, near an elbow. Not a seismic issue, but wrote work request to clean / repair as needed.
Some boron deposits were noted on tubing connected to INIPT5050, about 10' above floor, near an elbow. Not a seismic issue, but wrote work request to clean / repair as needed.
AWC - IN1438A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 26 of 105
AWC - IN1438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 26 of 105


Sheet 3 of 4 Status: YN NF U-Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: YN NF U-Area Walk-By Checklist (AWC)
Location: Bldg. CV]           Floor El. 562   Room, Area, DEG 40 ]?AD 55 ACLA Evaluated by: Thoas R Leitch           4227- ,   Z6                   Date:           /;___n/_,
Location: Bldg. CV]
7__
Floor El. 562 Room, Area, DEG 40 ]?AD 55 ACLA Evaluated by: Thoas R Leitch 4227-,
Ravinond Fzung                                         Date:   Z/z7/- 13 AWC - I N1438A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 27 of 105
Z6 Date:
7__
/;___ n/_,
Ravinond Fzung Date:
Z/z7/- 13 AWC - I N1438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 27 of 105


Sheet 4 of 4 Status: YM N-- U[-
Sheet 4 of 4 Status: YM N-- U[-
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CV]         Floor El. 562 Room, Area, DEG 40 RAD 55 ACLA P
Location: Bldg. CV]
Floor El. 562 Room, Area, DEG 40 RAD 55 ACLA P
Note: Boron deposits on tube attached to 1N!PT5050, See Comments.
Note: Boron deposits on tube attached to 1N!PT5050, See Comments.
Note:                                         Note:
Note:
AWC- IN1438A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 28 of 105
Note:
AWC-IN1438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 28 of 105


Sheet I of 3 Status: YZ Nf-- U[-]
Sheet I of 3 Status: YZ Nf-- U[-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1N1438A                         Equip. Class' 8 (MOV/SOV)
Equipment ID No. 1N1438A Equip. Class' 8 (MOV/SOV)
Equipment Description Emer N2 From CLA A to 1NC-34A Location: Bldg. CV1               Floor El. 562           Room, Area DEG 40 RAD 55 ACLA Manufacturer, Model, Etc. (optional but recommended)             Kerotest 09J-510 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description Emer N2 From CLA A to 1NC-34A Location: Bldg. CV1 Floor El. 562 Room, Area DEG 40 RAD 55 ACLA Manufacturer, Model, Etc. (optional but recommended)
Anchorage I. Is the anchorage configuration verification required (i.e., is the item one YE- NO of the 50% of SWEL items requiring such verification)?
Kerotest 09J-510 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?           YD NE UED N/A0
Anchorage I. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 3. Is the anchorage free of corrosion that is more than mild surface           YD NEI UEI N/AS oxidation?
YE-NO
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?   YE] NEi   U[3 N/AZ
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 5. Is the anchorage configuration consistent with plant documentation?         YEJ NEK UV1 N/AO (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 6. Based on the above anchorage evaluations, is the anchorage free of           YZ NEI U-potentially adverse seismic conditions?
YD NE UED N/A0 YD NEI UEI N/AS
IEnter the equipment class name from Appendix B: Classes of Equipment.
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 29 of 105
YE] NEi U[3 N/AZ
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YEJ NEK UV1 N/AO YZ NEI U-I Enter the equipment class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 29 of 105


Sheet 2 of 3 Status: YZ N-- UEZ Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: YZ N-- UEZ Seismic Walkdown Checklist (SWC)
Equipment ID No. 1N1438A                 Equip. Class' 8 (MOV/SOV)
Equipment ID No.
1N1438A Equip. Class' 8 (MOV/SOV)
Equipment Description Emer N2 From CLA A to INC-34A Interaction Effects
Equipment Description Emer N2 From CLA A to INC-34A Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     YIZ NEI UD N/ADI
: 7. Are soft targets free from impact by nearby equipment or structures?
YIZ NEI UD N/ADI
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UD N/AD and masonry block walls not likely to collapse onto the equipment?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UD N/AD and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YE NDI UD N/ADl
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     YZ NEI UE-of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions
YE NDI UD N/ADl YZ NEI UE-Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could     YED NDI     UDJ adversely affect the safety functions of the equipment?
: 11. Have you looked for and found no other seismic conditions that could YED NDI UDJ adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Reference CN-149"1-NI102 Evaluated by: 7-Xomnao. 9 LeYe~A           7/-,i~.~                             Date:   /2//1/3*/ Z N
Reference CN-149"1-NI102 Evaluated by: 7-Xomnao. 9 LeYe~A 7/-,i~.~
1ZAY'4('6 (Ii.b   f"_-/_j r-[               /y 2 ~
Date:  
C)//; 4 ~
/2//1/3*/ Z N
                                                                                                            / ~
1ZAY'4('6 (Ii.b f"_- /_j r-[
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 30 of 105
/ y 2 ~ C)//;
4 ~ / ~
CNC-1206.03-00-0203 Rev 1 A Page 30 of 105


Sheet 3 of 3 Status: YZ NR-1 Uf']
Sheet 3 of 3 Status: YZ NR-1 Uf']
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1N1438A             Equip. Class' 8 (MOV/SOV)
Equipment ID No. 1N1438A Equip. Class' 8 (MOV/SOV)
Equipment Description ErnerN2 From CLA A to 1NC-34A Photographs Note:
Equipment Description Erner N2 From CLA A to 1NC-34A Photographs Note:
Note:                                               Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 31 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 31 of 105


Sheet I of 4 Status: YS ND UD Area Walk-By Checklist (AWC)
Sheet I of 4 Status: YS ND UD Area Walk-By Checklist (AWC)
Location: Bldg. CV]               Floor El. 567               Room, Areal DEG 176 RAD 50 -Room FA'BC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. CV]
Floor El. 567 Room, Areal DEG 176 RAD 50 -Room FA'BC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID               Description                       Column Line or Other Location Info IND2A          ND Pump 1A Suction From LOOP B                   Deg 176 Rad 50 I. Does anchorage of equipment in the area appear to be fiee of                         Y2 ND UD N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Components: Equipment ID IND2A Description Column Line or Other Location Info ND Pump 1 A Suction From LOOP B Deg 176 Rad 50 I. Does anchorage of equipment in the area appear to be fiee of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 2. Does anchorage of equipment in the area appear to be free of significant               YZ ND UD- N/AD]
Y2 ND UD N/AD
: 2. Does anchorage of equipment in the area appear to be free of significant YZ ND UD-N/AD]
degraded conditions?
degraded conditions?
: 3. Based on a visual inspection friom the floor, do the cable/conduit                     YD N[        UD N/AD raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 3. Based on a visual inspection friom the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
There are two cables that run from 1ND37A and go thru an electray marked 440722. This electray has missing or loose fasteners that need resecurement to existing unistrut to restore compliance with the electrical mounting spec. Also the cables in the tray need inspection and reattachmentof tray tie wires in a few locations. The condition as found is capable of performing its design function, because the cable connections are still intact and not currently in a position that will cause their integrity to be compromised. A work request has been generated requesting repairto install/replacethe fasteneras necessary to restore compliance with the spec.
There are two cables that run from 1ND37A and go thru an electray marked 440722. This electray has missing or loose fasteners that need resecurement to existing unistrut to restore compliance with the electrical mounting spec. Also the cables in the tray need inspection and reattachment of tray tie wires in a few locations. The condition as found is capable of performing its design function, because the cable connections are still intact and not currently in a position that will cause their integrity to be compromised. A work request has been generated requesting repair to install/replace the fastener as necessary to restore compliance with the spec.
IIf the room in which the SWEL item   is located is very large (e.g., Turbine Hall), the area selected should be described.
YD N[
UD N/AD I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC- IND2A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 32 of 105
AWC-IND2A.DOC CNC-1206.03-00-0203 Rev 1 A Page 32 of 105


Sheet 2 of 4 Status: YZ N[D UD Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: YZ N[D UD Area Walk-By Checklist (AWC)
Location: Bldg. CV]               Floor El. 567         Room, Area, DEG 176 RAD 50 -Room FNBC
Location: Bldg. CV]
: 4. Does it appear that the area is free of potentially adverse seismic spatial YN NI Ui-I N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
Floor El. 567 Room, Area, DEG 176 RAD 50 -Room FNBC
: 5. Does it appear that the area is fiee of potentially adverse seismic           YZ ND U[D N/AD]
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic           YZ ND UO N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic           YZ ND UO N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could           YZ NDI Un adversely affect the safety functions of the equipment in the area?
YN NI Ui-I N/AD YZ ND U[D N/AD]
Comments (Additional pages may be added as necessary)
YZ ND UO N/AD YZ ND UO N/AD
: 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?
YZ NDI Un Comments (Additional pages may be added as necessary)
See item 3 above. Similar condition found on valve IND2A is described in SWC for that component.
See item 3 above. Similar condition found on valve IND2A is described in SWC for that component.
Repair called for in item 3 above was completed on 12/11/2012 per work order 02070453.
Repair called for in item 3 above was completed on 12/11/2012 per work order 02070453.
AWC- IND2A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 33 of 105
AWC-I ND2A.DOC CNC-1206.03-00-0203 Rev 1 A Page 33 of 105


Sheet 3 of 4 Status: YZ NE] U[]l Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: YZ NE] U[]l Area Walk-By Checklist (AWC)
Location: Bldg. CV]         Floor El. 567 Room, Area' DEG 176 R4D 50 -Room FNBC Evaluated by: Thomas R Leilch               _    _    _    _    Date:             2e'/- 3 Tl V            cn6   }
Location: Bldg. CV]
AWC- I ND2A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 34 of 105
Floor El. 567 Room, Area' DEG 176 R4D 50 -Room FNBC Evaluated by: Thomas R Leilch Date:
2e'/- 3 Tl cn6 }
V AWC-I ND2A.DOC CNC-1206.03-00-0203 Rev 1 A Page 34 of 105


Sheet 4 of 4 Status: YZ NM U[-I Area Walk-By Checklist (AWC)
Sheet 4 of 4 Status: YZ NM U[-I Area Walk-By Checklist (AWC)
Location: Bldg. CV]     Floor El. 567 Room, Area' DEG 176 RAID 50 -Room FNBC Phol Note:
Location: Bldg. CV]
Note:                                     Note:
Floor El. 567 Room, Area' DEG 176 RAID 50 -Room FNBC Phol Note:
AWC- I ND2A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A PFa2ge35 of 105
Note:
Note:
AWC-I ND2A.DOC CNC-1206.03-00-0203 Rev 1 A PFa2ge35 of 105


Sheet I of 4 Status: Y&#xa5;   N--   U-Seismic Walkdown Checklist (SWC)
Sheet I of 4 Status: Y&#xa5; N-- U-Seismic Walkdown Checklist (SWC)
Equipment ID No. IND2A                           Equip. Class' 8 (MOV/SOV)
Equipment ID No. IND2A Equip. Class' 8 (MOV/SOV)
Equipment Description ND Pump 1A Suction from LOOP B Location: Bldg. CVI                 Floor El. 567           Room, Area DEG 176 RAD 50 -RM FNBC Manufacturer, Model, Etc. (optional but recommended)             Borg Warner 09J-201 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description ND Pump 1A Suction from LOOP B Location: Bldg. CVI Floor El. 567 Room, Area DEG 176 RAD 50 -RM FNBC Manufacturer, Model, Etc. (optional but recommended)
Borg Warner 09J-201 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchora2e
Anchora2e
: 1. Is the anchorage configuration verification required (i.e., is the item one   YO NZ of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?             YE NEI U[      N/AZ
YO NZ
: 3. Is the anchorage free of corrosion that is more than mild surface             YE NE-) U-      N/AZ oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?     YO N-      UEi N/AZ
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?           YE NEI UE N/AN (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of           Y9 NO Un potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
I Enter the equipment class name from Appendix B: Classes of Equipment.
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 36 of 105
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YE NEI U[
N/AZ YE NE-) U-N/AZ YO N-UEi N/AZ YE NEI UE N/AN Y9 NO Un I Enter the equipment class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 36 of 105


Sheet 2 of 4 Status: Y[D ND UD Seismic Walkdown Checklist (SWC)
Sheet 2 of 4 Status: Y[D ND UD Seismic Walkdown Checklist (SWC)
Equipment ID No. 1ND2A                         Equip. Class, 8 (MOV/SOVJ Equipment Description ND Pump IA Suction from LOOP B Interaction Effects
Equipment ID No. 1ND2A Equip. Class, 8 (MOV/SOVJ Equipment Description ND Pump IA Suction from LOOP B Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?       YE NED UI         N/ADI
: 7. Are soft targets free from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID ND UD-I N/ADI and masonry block walls not like]y to collapse onto the equipment?
YE NED UI N/ADI
: 9. Do attached lines have adequate flexibility to avoid damage?               Y[l NDI UD[ N/A[D
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID ND UD-I N/ADI and masonry block walls not like]y to collapse onto the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment free       YZ NEI UEI of potentially adverse seismic interaction effects?
: 9. Do attached lines have adequate flexibility to avoid damage?
Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could       YNI   ND UD adversely affect the safety functions of the equipment?
1 0. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
There are Nuclear Safety Related cables that run from the valve operatorthen thru an electray and into a junction box. The box was originallyfastened to a piece of unistrut that goes to an embedment in the wall. These fasteners have come loose. As a result the electray is also loose, and the cables would be the support for the box if it tried to fall off the unistrut.
Y[l NDI UD[ N/A[D YZ NEI UEI Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YNI ND UD adversely affect the safety functions of the equipment?
There are Nuclear Safety Related cables that run from the valve operator then thru an electray and into a junction box. The box was originally fastened to a piece of unistrut that goes to an embedment in the wall. These fasteners have come loose. As a result the electray is also loose, and the cables would be the support for the box if it tried to fall off the unistrut.
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
See item 11. The box weighs less than 20# and the cables all have metal jackets that are robust and undamaged. A work request was written to repairthese items before the end of the outage, but the condition as found was judged capable of performing its design function. (supply of power to the valve operator). Repair was completed on 12/11/2012 per work order 02070468.
See item 11. The box weighs less than 20# and the cables all have metal jackets that are robust and undamaged. A work request was written to repair these items before the end of the outage, but the condition as found was judged capable of performing its design function. (supply of power to the valve operator). Repair was completed on 12/11/2012 per work order 02070468.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 37 of 105
CNC-1206.03-00-0203 Rev 1 A Page 37 of 105


Sheet 3 of 4 Status: YZ N[-] UD-Seismic Walkdown Checklist (SWC)
Sheet 3 of 4 Status: YZ N[-] UD-Seismic Walkdown Checklist (SWC)
Equipment ID No. IND2A                 Equip. Class' 8 (MOV/SOV)
Equipment ID No. IND2A Equip. Class' 8 (MOV/SOV)
Equipment Description ND Pump IA Suction from LOOP B Evaluated by:         -s       &,            .                Date:   i/27/,z/z       z.
Equipment Description ND Pump IA Suction from LOOP B Evaluated by:  
                *.Jb     r0                                               '    '-,2,&/3 CNC-1206.03-00-0203 Rev I Attachment 7A Page 38 of 105
-s Date:
i/27/,z/z z.
*.Jb r0  
'-,2,&/3 CNC-1206.03-00-0203 Rev I A Page 38 of 105


Sheet 4 of 4 Status: Y[   NE]   UD-Seismic Walkdown Checklist (SWC)
Sheet 4 of 4 Status: Y[
Equipment ID No. IND2A                   Equip. Class, 8 (MOV/SOV)
NE] UD-Seismic Walkdown Checklist (SWC)
Equipment Description ND Putmp 1A Suction from LOOP B Note: Box needing reattachmentto unistrut.             Note:
Equipment ID No. IND2A Equip. Class, 8 (MOV/SOV)
Note:                                                 Note:
Equipment Description ND Putmp 1A Suction from LOOP B Note: Box needing reattachment to unistrut.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 39 of 105
Note:
Note:
Note:
CNC-1206.03-00-0203 Rev 1 A Page 39 of 105


Sheet I of 4 Status: YZ N[] U0 Area Walk-By Checklist (AWC)
Sheet I of 4 Status: YZ N[] U0 Area Walk-By Checklist (AWC)
Location: Bldg. CVI                 Floor El. 568           Room, Area, DEG 176 RAD 25 -Room LC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. CVI Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID               Description                     Column Line or Other Location Info INDIB     ND Pump IA Suction from Lp B                 DEG 176 Rad 25 El 568 I. Does anchorage of equipment in the area appear to be free of                       Y0 NE        UD N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Components: Equipment ID Description INDIB ND Pump IA Suction from Lp B Column Line or Other Location Info DEG 176 Rad 25 El 568 I. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 2. Does anchorage of equipment in the area appear to be free of significant YN ND U- N/AD degraded conditions?
Y0 NE UD N/AD
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YE NO UO N/AD raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 2. Does anchorage of equipment in the area appear to be free of significant YN ND U-N/AD degraded conditions?
I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YE NO UO N/AD I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC- INDIB.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 40 of 105
AWC-INDIB.DOC CNC-1206.03-00-0203 Rev 1 A Page 40 of 105


Sheet 2 of 4 Status: YN NEI     U]
Sheet 2 of 4 Status: YN NEI U]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CV]             Floor El. 568             Room, Area, DEG 176 RAD 25 -Room LC
Location: Bldg. CV]
: 4. Does it appear that the area is free of potentially adverse seismic spatial YZ N[     UD N/A[
Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC
: 4. Does it appear that the area is free of potentially adverse seismic spatial YZ N[
UD N/A[
interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 5. Does it appear that the area is free of potentially adverse seismic         YZ Ni7 U[I- N/AD interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic         YZ NO UI N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic         Y[    NED UJ[    N/AD1 interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could       Y[D N[D UDM adversely affect the safety functions of the equipment in the area?
YZ Ni7 U[I-N/AD YZ NO UI N/AD Y[
NED UJ[
N/AD1
: 8. Have you looked for and found no other seismic conditions that could Y[D N[D UDM adversely affect the safety functions of the equipment in the area?
Noted some small tubing that may have been disturbed from original position. Condition is fine, no kinks or tight bends noted, seismic function is maintained.
Noted some small tubing that may have been disturbed from original position. Condition is fine, no kinks or tight bends noted, seismic function is maintained.
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Temporary lead shielding appears to be well secured in place.
Temporary lead shielding appears to be well secured in place.
AWC- IND]B.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 41 of 105
AWC-IND]B.DOC CNC-1206.03-00-0203 Rev 1 A Page 41 of 105


Sheet 3 of 4 Status: YZ NM UD Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: YZ NM UD Area Walk-By Checklist (AWC)
Location: Bldg. CV]         Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Evaluated by: Thomas R Leitch                                     Date:   Z12 7/z/--
Location: Bldg. CV]
Rciwvnond Funs                                     Date:     *      -7' AWC- I NDIB.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 42 of 105 44
Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Evaluated by: Thomas R Leitch Date:
Z12 7/z/--
Rciwvnond Funs Date:  
-7 AWC-I NDIB.DOC CNC-1206.03-00-0203 Rev 1 A Page 42 of 105 44


Sheet 4 of 4 Status- YZ ND]U     tJ-Area Walk-By Checklist (AWC)
Sheet 4 of 4 Status-YZ ND]U tJ-Area Walk-By Checklist (AWC)
Location: Bldg. CV1     Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Pho Note:
Location: Bldg. CV1 Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Pho Note:
Note:                                     Note:
Note:
AWC- INDIB.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 43 of 105
Note:
AWC-INDIB.DOC CNC-1206.03-00-0203 Rev 1 A Page 43 of 105


Sheet I of 3 Status: YN NEI U-]
Sheet I of 3 Status: YN NEI U-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NDIB                           Equip. Class, 8 (MOVISOV)
Equipment ID No. 1NDIB Equip. Class, 8 (MOVISOV)
Equipment Description ND Pump 1A Suction from LOOP B Location: Bldg. CV1                 Floor El. 568           Room, Area DEG 176 RAD 25       -Room LC Manufacturer, Model, Etc. (optional but recommended)             Borg Warner 09J-201 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description ND Pump 1A Suction from LOOP B Location: Bldg. CV1 Floor El. 568 Room, Area DEG 176 RAD 25  
-Room LC Manufacturer, Model, Etc. (optional but recommended)
Borg Warner 09J-201 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorae I. Is the anchorage configuration verification required (i.e., is the item one YE No of the 50% of SWEL items requiring such verification)?
Anchorae I. Is the anchorage configuration verification required (i.e., is the item one YE No of the 50% of SWEL items requiring such verification)?
: 2. .sthe anchorage free of bent, broken, missing or loose hardware?             YEI NE UlE N/AZ
: 2..s the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surface             YE[ NE UD N/AZ oxidation?
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?     YE NEI UE- N/A[D
YEI NE UlE N/AZ YE[ NE UD N/AZ
: 5. Is the anchorage configuration consistent with plant documentation?           YE NEI UE[      NWAN (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage fiee of             YN NE U-E potentially adverse seismic conditions?
YE NEI UE-N/A[D
Enter the cquipmenl class name from Appendix B: Classes of Equipment.
: 5. Is the anchorage configuration consistent with plant documentation?
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 44 of 105
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage fiee of potentially adverse seismic conditions?
YE NEI UE[
NWAN YN NE U-E Enter the cquipmenl class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 44 of 105


Sheet 2 of 3 Status: Y[N Nn-] Ul-]
Sheet 2 of 3 Status: Y[N Nn-] Ul-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INDIB                         Equip. Class' 8 (MOV/SOV)
Equipment ID No. INDIB Equip. Class' 8 (MOV/SOV)
Equipment Description ND Pump 1A Suction from LOOP B Interaction Effects
Equipment Description ND Pump 1A Suction from LOOP B Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     YU NO UL-] N/AD
: 7. Are soft targets free from impact by nearby equipment or structures?
YU NO UL-] N/AD
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ N[D UEL N/AEl and masonry block walls not likely to collapse onto the equipment?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ N[D UEL N/AEl and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?               Y[E N[-I U0 N/A[D
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     Y19 NE UE3 of lpotentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of lpotentially adverse seismic interaction effects?
Other Adverse Conditions
Y[E N[-I U0 N/A[D Y19 NE UE3 Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could     YZ NW UD adversely affect the safety functions of the equipment?
: 11. Have you looked for and found no other seismic conditions that could YZ NW UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Congested area. Radiation Shielding blocked direct view of piping. All items going to the valve looked secure. Ref CN-1491-ND.O0-003.
Congested area. Radiation Shielding blocked direct view of piping. All items going to the valve looked secure. Ref CN-1491-ND.O0-003.
Evaluated by: Thomas R Leitch               -                                    Date:   /,2Z/,,,2-/Z..
Evaluated by: Thomas R Leitch ID Date:  
ID                                &'
/,2Z/,,,2-/Z..
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 45 of 105
CNC-1206.03-00-0203 Rev 1 A Page 45 of 105
                                                                                                              --- 4
--- 4


Sheet 3 of 3 Status: Y[ NF- U-]
Sheet 3 of 3 Status: Y[
NF-U-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. tNDIB               Equip. Class, 8 (MOV/SOV)
Equipment ID No. tNDIB Equip. Class, 8 (MOV/SOV)
Equipment Description ND Pump IA Suction from LOOP B Note:
Equipment Description ND Pump IA Suction from LOOP B Note:
Note:                                               Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 46 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 46 of 105


Sheet I of 4 Status: YN NF U[.
Sheet I of 4 Status: YN NF U[.
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CVI               Floor El. 635           Room, AreaI DEG 105 RAD R37 - Top Of PZR Cavit, Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. CVI Floor El. 635 Room, AreaI DEG 105 RAD R37 - Top Of PZR Cavit, Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column   Line or Other Location Info INC34A        PZRPORV                          Deg 105     Rad37 El 635 INC32B        PZR PORV                          Deg 107   Rad 38 El 635 INC36B        PZR PORV                          Deg 101     Rad37 El 635
Components: Equipment ID INC34A INC32B INC36B Description PZRPORV PZR PORV PZR PORV Column Line or Other Location Info Deg 105 Rad37 El 635 Deg 107 Rad 38 El 635 Deg 101 Rad37 El 635
: 1. Does anchorage of equipment in the area appear to be free of                       Y9 N(: U(:] N/AEZ) potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 2. Does anchorage of equipment in the area appear to be fiee of significant           Y,     NZ) UDI N/Ac.
Y9 N(: U(:] N/AEZ)
: 2. Does anchorage of equipment in the area appear to be fiee of significant Y,
NZ) UDI N/Ac.
degraded conditions?
degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YO N-- UED N/A[Z raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
IIf the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
YO N-- UED N/A[Z I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC - I NC4A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 47 of 105
AWC - I NC4A.DOC CNC-1206.03-00-0203 Rev 1 A Page 47 of 105


Sheet 2 of 4 Status: YZ NM UD Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: YZ NM UD Area Walk-By Checklist (AWC)
Location: Bldg. CVI               Floor El. 635           Room, Area' DEG 105 RAD R37- Ton of PZR Cavity
Location: Bldg. CVI Floor El. 635 Room, Area' DEG 105 RAD R37-Ton of PZR Cavity
: 4. Does it appear that the area is free of potentially adverse seismic spatial       YO NO U-         N/A[9 interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 4. Does it appear that the area is free of potentially adverse seismic spatial YO NO U-N/A[9 interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
No Tiles or lighting
No Tiles or lighting
: 5. Does it appear that the area is free of potentially adverse seismic               YZ ND UD NJAO interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic               YZ ND UD N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is fl'ee of potentially adverse seismic               YO NO UD N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is fl'ee of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could               YZ No UD adversely affect the safety functions of the equipment in the area?
YZ ND UD NJAO YZ ND UD N/AD YO NO UD N/AD
Comments (Additional pages may be added as necessary)
: 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?
YZ No UD Comments (Additional pages may be added as necessary)
Area is very congested, but system clearances are maintained, and all anchorage, cabling, and tubing appears in good condition and properly supported.
Area is very congested, but system clearances are maintained, and all anchorage, cabling, and tubing appears in good condition and properly supported.
AWC - INC34A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 48 of 105
AWC - INC34A.DOC CNC-1206.03-00-0203 Rev 1 A Page 48 of 105


Sheet 3 of 4 Status: YM ND-- U[D Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: YM ND--
Location: Bldg. CV1         Floor El. 635 - Room, AreaI DEG 105 RAD R37- Top of PZR Ca'ity Evaluated by: Thomas R Leitch     "7/           <.                Date:   '/2     "b/-
U[D Area Walk-By Checklist (AWC)
Ravmond Fvn~       i&#xfd;W                             Date:2 j AWC - I NC34A.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 49 of 105
Location: Bldg. CV1 Floor El. 635 Room, AreaI DEG 105 RAD R37-Top of PZR Ca'ity Evaluated by: Thomas R Leitch "7/
Date:  
'/2 "b/-
Ravmond Fvn~
i&#xfd;W Date:2 j AWC - I NC34A.DOC CNC-1206.03-00-0203 Rev 1 A Page 49 of 105


Sheet 4 of 4 Status: YE N-] UM-]
Sheet 4 of 4 Status: YE N-] UM-]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CVI     Floor El. 635 Room, Area, DEG 105 RAD R37 - Top of PZR Cavity Photographs Note:
Location: Bldg. CVI Floor El. 635 Room, Area, DEG 105 RAD R37 - Top of PZR Cavity Photographs Note:
AWC- INC34ADOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 50 of 105
AWC-INC34ADOC CNC-1206.03-00-0203 Rev 1 A Page 50 of 105


Sheet I of 3 Status: YZ ND- UD--
Sheet I of 3 Status: YZ ND-UD--
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INC34A                           Equip. Class, Equipment Description PZR PORV Location: Bldg. CV1                 Floor El. 635             Room, Area DEG 105 RAD R37-Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)               CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment ID No. INC34A Equip. Class, Equipment Description PZR PORV Location: Bldg. CV1 Floor El. 635 Room, Area DEG 105 RAD R37-Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)
CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one YED NZ of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage fiee of bent, broken, missing or loose hardware?           YE] NED UE] N/A[]
YED NZ
: 3. Is the anchorage fiee of corrosion that is more than mild surface           Y0 NE] UD N/AZ oxidation?
: 2. Is the anchorage fiee of bent, broken, missing or loose hardware?
: 4. ]s the anchorage free of visible cracks in the concrete near the anchors?   YE] NEI UtD N/AZ
: 3. Is the anchorage fiee of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?         YE] NED UE] N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. ]s the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of           YM NE] UE potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
Enler the equipment class name from Appendix 13: Classes of Equipment.
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 51 of 105
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YE] NED UE] N/A[]
Y0 NE] UD N/AZ YE] NEI UtD N/AZ YE] NED UE] N/AZ YM NE] UE Enler the equipment class name from Appendix 13: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 51 of 105


Sheet 2 of 3 Status: Y[     NEI U-]
Sheet 2 of 3 Status: Y[
NEI U-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INC34A                       Equip. Class' Equipment Description PZR PORV Interaction Effects
Equipment ID No. INC34A Equip. Class' Equipment Description PZR PORV Interaction Effects
: 7. Are sofi targets free from impact by nearby equipment or structures?     YZ NDI U0 N/A[]
: 7. Are sofi targets free from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN ND- UD] N/AD and masonry block walls not likely to collapse onto the equipment?
YZ NDI U0 N/A[]
: 9. Do attached lines have adequate flexibility to avoid damage?               Y0 NDI UD- N/AD
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN ND-UD] N/AD and masonry block walls not likely to collapse onto the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment free     YZ NED Un of potentially adverse seismic interaction effects?
: 9. Do attached lines have adequate flexibility to avoid damage?
Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could       YE NEIUn adversely affect the safety functions of the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Comments.(Additional pages may be added as necessary)
Y0 NDI UD-N/AD YZ NED Un Other Adverse Conditions 1I.
This component is removed/rebuilton a regularschedule. Also, ref drawing CN-1491-07.00-30.
Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?
Evaluated by: ;     -7"* -     ,/ , l                                           Date:   / L&#x17d;3     Z7kZ/ .
YE NEIUn Comments.(Additional pages may be added as necessary)
2   3 2o(Z-~
This component is removed/rebuilt on a regular schedule. Also, ref drawing CN-1491-07.00-30.
fj CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 52 of 105
Evaluated by: ;  
-7"* -
, /, l Date:  
/ L&#x17d;3 Z7kZ/.
fj 2 3 2o(Z-~
CNC-1206.03-00-0203 Rev 1 A Page 52 of 105


Sheet 3 of 3 Status: YV     N[- Ul-I Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: YV N[- Ul-I Seismic Walkdown Checklist (SWC)
Equipment ED No. 1NC34A         Equip. Class' 7 (AOV)
Equipment ED No. 1NC34A Equip. Class' 7 (AOV)
Equipment Description PZR PORV Photo ra hA Note: INC34A                                   Note:
Equipment Description PZR PORV Photo ra hA Note: INC34A Note:
Note:                                         Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 53 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 53 of 105


Sheet 3 of 3 Status: YN NDI       U[-D Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: YN NDI U[-D Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NC32B                           Equip. Class, 7 (AOV)
Equipment ID No. 1NC32B Equip. Class, 7 (AOV)
Equipment Description PZR PORV Location: Bldg. CV1                 Floor El. 635           Room, Area DEG 107 RAD R38 - Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)             CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description PZR PORV Location: Bldg. CV1 Floor El. 635 Room, Area DEG 107 RAD R38 - Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)
CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage I. Is the anchorage configuration verification required (i.e., is the item one YO No of the 50% of SWEL items requiring such verification)?
Anchorage I. Is the anchorage configuration verification required (i.e., is the item one YO No of the 50% of SWEL items requiring such verification)?
Line mounted item.
Line mounted item.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?           YE] NE UE N/AZ
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free ofcorrosion that is more than mild surface             YE NO U[       N/AlZ oxidation?
: 3. Is the anchorage free ofcorrosion that is more than mild surface oxidation?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?   YE NEI UD N/A12
YE] NE UE N/AZ YE NO U[
: 5. Is the anchorage configuration consistent with plant documentation?         YEI NEI UD3 N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
N/AlZ
: 6. Based on the above anchorage evaluations, is the anchorage free of           YZ NO U-potentially adverse seismic conditions?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
SEnter the equipmeni class name from Appendix B: Classes of Equipment.
YE NEI UD N/A12
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 54 of 105
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YEI NEI UD3 N/AZ YZ NO U-SEnter the equipmeni class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 54 of 105


Sheet 2 of 3 Status: YF ND U[
Sheet 2 of 3 Status: YF ND U[
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
INC32B Equipment ID No. sEquip                             Class Equipment Description PZR PORV Interaction Effects
Equipment ID No.
: 7. Are soft targets free from impact by nearby equipment or structures?     YlZ NEI Ut] N/AEl
INC32B sEquip Class Equipment Description PZR PORV Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?
YlZ NEI Ut] N/AEl
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NE] Ut1 N/AtI and masonry block walls not likely to collapse onto the equipment?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NE] Ut1 N/AtI and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YN[    NE] Ut] N/At]
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     YE NE] UE of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions
YN[
: 11. Have you looked for and found no other seismic conditions that could     YZ NEI Ut]
NE] Ut] N/At]
YE NE] UE Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could YZ NEI Ut]
adversely affect the safety functions of the equipment?
adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Evaluated by: 7-IOna-s-       Al --k&/4*         ~4:9       A?~<             Date:       .. ,3~~
Evaluated by: 7-IOna-s-Al -- k&/4*
2 CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 55 of 105           I
~4:9 A?~<
Date:  
,3~~
2 CNC-1206.03-00-0203 Rev 1 A Page 55 of 105 I


Sheet 3 of 3 Status: Y[     NF- U[-]
Sheet 3 of 3 Status: Y[
NF-U[-]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NC32B         Equip. Class, 7 (AOV)
Equipment ID No. 1NC32B Equip. Class, 7 (AOV)
Equipment Description PZR PORV Photo2raphs Note:
Equipment Description PZR PORV Photo2raphs Note:
Note:                                         Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 56 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 56 of 105


Sheet i of 3 Status: YM N[-- U-Seismic Walkdown Checklist (SWC)
Sheet i of 3 Status: YM N[-- U-Seismic Walkdown Checklist (SWC)
Equipment IDNo. 1NC36B                             Equip. Class' 7 (AOV)
Equipment IDNo. 1NC36B Equip. Class' 7 (AOV)
Equipment Description PZR PORV Location: Bldg. CVI                 Floor El. 635           Room, Area DEG 101 RAD R37 - Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)               CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description PZR PORV Location: Bldg. CVI Floor El. 635 Room, Area DEG 101 RAD R37 - Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)
CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one YO NO of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
Line mounted item.
Line mounted item.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?           YE- NO UE      N/AO Studs and nuts attaching valve assembly to line mounted portion of valve are all there and in excellent condition.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surface           YE NEI UE NIAZ oxidation?
Studs and nuts attaching valve assembly to line mounted portion of valve are all there and in excellent condition.
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?   YE NE      JIE N/AZ
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?         YE NE UE N/As (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of           YN NE UE&#xfd; potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
Enter the equipmenl class name fromn Appendix B: Classes of Equipment.
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 57 of 105
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YO NO YE-NO UE N/AO YE NEI UE NIAZ YE NE JIE N/AZ YE NE UE N/As YN NE UE&#xfd; Enter the equipmenl class name fromn Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 57 of 105


Sheet 2 of 3 Status: Y1Z ND UM Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: Y1Z ND UM Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NC36B                     Equip. Class, Equipment Description PZR PORV Interaction Effects
Equipment ID No. 1NC36B Equip. Class, Equipment Description PZR PORV Interaction Effects
: 7. Are soft targets free fiom impact by nearby equipment or structures?     YZ ND UD N/AD
: 7. Are soft targets free fiom impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD) and masonry block walls not likely to collapse onto the equipment?
YZ ND UD N/AD
: 9. Do attached lines have adequate flexibility to avoid damage?               YER ND UD1 N/AD
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD) and masonry block walls not likely to collapse onto the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment flee     YZ NO UO of potentially adverse seismic interaction effects?
: 9. Do attached lines have adequate flexibility to avoid damage?
Other Adverse Conditions
: 10. Based on the above seismic interaction evaluations, is equipment flee of potentially adverse seismic interaction effects?
: 1. Have you looked for and found no other seismic conditions that could     YZ ND UED adversely affect the safety functions of the equipment?
YER ND UD1 N/AD YZ NO UO Other Adverse Conditions
Comments (Additional pages may be added as necessary)
: 1. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?
YZ ND UED Comments (Additional pages may be added as necessary)
Congested area. All items in good condition and installed correctly. This component is worked on/rebuilt regularly.
Congested area. All items in good condition and installed correctly. This component is worked on/rebuilt regularly.
Evaluated by: 7-/oi,. .                                   , A                   Date:    /
Evaluated by: 7-/oi,..
rL/{6'p                       7, CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 58 of 105
, A rL/{6'p 7,
Date:
/
CNC-1206.03-00-0203 Rev 1 A Page 58 of 105


Sheet 3 of 3 Status: Y[     NE- UE]
Sheet 3 of 3 Status: Y[
NE-UE]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INC36B         Equip. Class' Equipment Description PZR PORV Note:
Equipment ID No. INC36B Equip. Class' Equipment Description PZR PORV Note:
Note:                                         Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 59 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 59 of 105


Sheet I o14 Status: YN N7 UM Area Walk-By Checklist (AWC)
Sheet I o14 Status: YN N7 UM Area Walk-By Checklist (AWC)
Location: Bldg. CV1               Floor El. 568             Room, Area, DEG 244 RAD 47 - Room PCHA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Location: Bldg. CV1 Floor El. 568 Room, Area, DEG 244 RAD 47 - Room PCHA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column Line or Other Location Info IFW8        Refueling Cavity Drain                Deg 244 Rad 47 El 568 I. Does anchorage of equipment in the area appear to be fiee of                       YZ NE UD N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Components: Equipment ID Description I FW8 Refueling Cavity Drain Column Line or Other Location Info Deg 244 Rad 47 El 568 I. Does anchorage of equipment in the area appear to be fiee of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 2. Does anchorage of equipment in the area appear to be free of significant             YN ND] UD N/AD-degraded conditions?
YZ NE UD N/AD
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YZ ND UD N/AO raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 2. Does anchorage of equipment in the area appear to be free of significant YN ND] UD N/AD-degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YZ ND UD N/AO
' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC-     -FW8.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 60 of 105
AWC-  
-FW8.DOC CNC-1206.03-00-0203 Rev 1 A Page 60 of 105


Sheet 2 of 4 Status: Y[   N[] UD Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: Y[
Location: Bldg. CVI             Floor El. 568           Room, Area1 DLG' 244 RIAD 47 - .Room PCHA
N[] UD Area Walk-By Checklist (AWC)
Location: Bldg. CVI Floor El. 568 Room, Area1 DLG' 244 RIAD 47 -.Room PCHA
: 4. Does it appear that the area is free of potentially adverse seismic spatial YZ NDI UD N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 4. Does it appear that the area is free of potentially adverse seismic spatial YZ NDI UD N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 5. Does it appear that the area is free of potentially adverse seismic       YZ ND UD N/AD interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic       YN NDI      U0 N/AD]
YZ ND UD N/AD
interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic       YE, ND UDI N/ADl interactions associated with housekeeping practices, storage of poltable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of poltable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could       YZ ND U0 adversely affect the safety functions of the equipment in the area?
YN NDI U0 N/AD]
AWC- I FWS.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 61 of 105
YE, ND UDI N/ADl
: 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?
YZ ND U0 AWC-I FWS.DOC CNC-1206.03-00-0203 Rev 1 A Page 61 of 105


Sheet 3 of 4 Status: YZ NE-* UD)
Sheet 3 of 4 Status: YZ NE-* UD)
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CVI               Floor El. 568             Room, Area' DEG 244 RID 47 - Room PCHA Conirnents (Additional pages may be added as necessary)
Location: Bldg. CVI Floor El. 568 Room, Area' DEG 244 RID 47 - Room PCHA Conirnents (Additional pages may be added as necessary)
Noted I VP7A -- First tubing clamp off operator is loose- see pictures. This is a VI tubing clamp on the line attached to 1V13690. Tubing is still supported by clamp. Wrote work request #01075428 to tighten/repair.
Noted I VP7A -- First tubing clamp off operator is loose-see pictures. This is a VI tubing clamp on the line attached to 1V13690. Tubing is still supported by clamp. Wrote work request #01075428 to tighten/repair.
1VYI 7A - 4 inch VY (H2 sample and purge) pipe elbow is close to a Nuclear Safety Related cable junction box. Pipe seems rigid, and cable junction box could tolerate some contact, as it can flex somewhat. There is approx. 'A"clear currently. There is some slack in the cables, and the junction box is mounted on 4" electray that is mounted on unistrut.
1 VYI 7A - 4 inch VY (H2 sample and purge) pipe elbow is close to a Nuclear Safety Related cable junction box. Pipe seems rigid, and cable junction box could tolerate some contact, as it can flex somewhat. There is approx. 'A" clear currently. There is some slack in the cables, and the junction box is mounted on 4" electray that is mounted on unistrut.
This electric junction box assembly is not very massive, and seismic movement would be minimal due to stiffniess of unistrut support. The piping is restrained in the lateral direction by two supports , I-A-VY-4008 and I -A-VY-4234, so lateral seismic motion of the piping should be negligible. See Photo.
This electric junction box assembly is not very massive, and seismic movement would be minimal due to stiffniess of unistrut support. The piping is restrained in the lateral direction by two supports, I-A-VY-4008 and I -A-VY-4234, so lateral seismic motion of the piping should be negligible. See Photo.
Evaluated by: Thomas R Leitch                                                               Date: 02/18/2013 Y~2J~   ,22         hj                                                              U. -1:3 AWC- IFWS.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 62 of 105
Evaluated by: Thomas R Leitch Date: 02/18/2013 Y~2J~
hj 22 U. -1:3 AWC-IFWS.DOC CNC-1206.03-00-0203 Rev 1 A Page 62 of 105


Sheet 4 of 4 Status: YN N[] Ur-Area Walk-By Checklist (AWC)
Sheet 4 of 4 Status: YN N[] Ur-Area Walk-By Checklist (AWC)
Location: Bldg. CV]             Floor El. 568   Room, Area, DEG 244 RAD 47 - Room PCHA Photographs iNote: inis vaive is near 4 in elDOW ShOWn DelOW   trote: t-irst tuDing ciamp on' ntos operatoris loose.
Location: Bldg. CV]
Floor El. 568 Room, Area, DEG 244 RAD 47 - Room PCHA Photographs iNote: inis vaive is near 4 in elDOW ShOWn DelOW trote: t-irst tuDing ciamp on' ntos operator is loose.
Note: Loose Tubing clamp is attached to support shown on right.
Note: Loose Tubing clamp is attached to support shown on right.
AWC- I FWS.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 63 of 105
AWC-I FWS.DOC CNC-1206.03-00-0203 Rev 1 A Page 63 of 105


Sheet I of 3 Status: YN NR U[]
Sheet I of 3 Status: YN NR U[]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. IFW8                             Equip. Class' 00 (Other)
Equipment ID No. IFW8 Equip. Class' 00 (Other)
Equipment Description Refueling Cavity Drain Location: Bldg. CV1                 Floor El. 568           Room, Area DEG 244 RAD 47 - Room PCHA Manufacturer, Model, Etc. (optional but recommended)             Westinghouse 09D-210 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWt.L. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description Refueling Cavity Drain Location: Bldg. CV1 Floor El. 568 Room, Area DEG 244 RAD 47 - Room PCHA Manufacturer, Model, Etc. (optional but recommended)
Westinghouse 09D-210 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWt.L. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. is the anchorage configuration verification required (i.e., is the item one   YF-1 N9 of the 50% of SWEL items requiring such verification)?
: 1. is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?             YE NE UD N/Az
Y F-1 N 9
: 3. Is the anchorage free of corrosion that is more than mild surface             YE- NE UrI      N/A[D oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 4. ls the anchorage free of visible cracks in the concrete near the anchors?     YE NE UE N/AZ
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?           YE NE UO N/AN (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. ls the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage flee of           YX NO UE-potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
Enter the equipmcnt class name from Appendix B: Classes of Equipment.
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 64 of 105
: 6. Based on the above anchorage evaluations, is the anchorage flee of potentially adverse seismic conditions?
YE NE UD N/Az YE-NE UrI N/A[D YE NE UE N/AZ YE NE UO N/AN YX NO UE-Enter the equipmcnt class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 64 of 105


Sheet 2 of 3 Status: YM ND Ul--
Sheet 2 of 3 Status: YM ND Ul--
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1FW8                         Equip. Class, 00 (Other)
Equipment ID No.
1FW8 Equip. Class, 00 (Other)
Equipment Description Refueling Cavity Drain Interaction Effects
Equipment Description Refueling Cavity Drain Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     YN NI U-i       N/AO
: 7. Are soft targets free from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YEK ND ur- N/AD-and masonry block walls not likely to collapse onto the equipment?
YN NI U-i N/AO
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YEK ND ur-N/AD-and masonry block walls not likely to collapse onto the equipment?
No ceiling tiles
No ceiling tiles
: 9. Do attached lines have adequate flexibility to avoid damage?             YO NO UD N/An No attached lines, this is a manual valve
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     Y[K NO U-of potentially adverse seismic interaction effects?
No attached lines, this is a manual valve 1 0. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions I1. I-lave you looked for and found no other seismic conditions that could   Y E N -1 Ui0 adversely affect the safety functions of the equipment?
YO NO UD N/An Y[K NO U-Other Adverse Conditions I1. I-lave you looked for and found no other seismic conditions that could Y E N -1 Ui0 adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as mecessary)
Comments (Additional pages may be added as mecessary)
See Picture. Also ref CN-1491-FWO07 Evaluated by: 71-//4,ew"     /F   4r'7-a     Z           1         6         Date: 12//3 /40 / Ze-
See Picture. Also ref CN-1491-FWO07 Evaluated by: 71-//4,ew"  
                                                                          -7 J e,                 09     ,                  ,~
/F 4r'7-a Z
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 65 of 105
1 6
Date: 12//3 /40 / Ze-
-7 J e, 09  
,~
CNC-1206.03-00-0203 Rev 1 A Page 65 of 105


Sheet 3 of 3 Status: YZ NM] U[]
Sheet 3 of 3 Status: YZ NM] U[]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1FW8                 Equip. ClassW 00 (Other)
Equipment ID No. 1FW8 Equip. ClassW 00 (Other)
Equipment Description Refueling Cavity Drain Note:
Equipment Description Refueling Cavity Drain Note:
Note:                                                 Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 66 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 66 of 105


Sheet I of 4 Status: YZ N[D U-Area Walk-By Checklist (AWC)
Sheet I of 4 Status: YZ N[D U-Area Walk-By Checklist (AWC)
Location: Bldg. CVI               Floor El. 563           Room, Area' DEG 300 RAD 33 - Room LC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Location: Bldg. CVI Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column Line or Other Location Info IFW46            Refueling Cavity Drain          Deg300 Rad 33 El 563
Components: Equipment ID IFW46 Description Refueling Cavity Drain Column Line or Other Location Info Deg300 Rad 33 El 563
: 1. Does anchorage of equipment in the area appear to be free of                       YZ N: UD- N/AO potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 2. Does anchorage of equipment in the area appear to be free of significant           YN ND UD- N/AF-1 degraded conditions?
YZ N: UD-N/AO
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YZ NED UD N/AD raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 2. Does anchorage of equipment in the area appear to be free of significant YN ND UD-N/AF-1 degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YZ NED UD N/AD
' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC- I FW46.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 67 of 105
AWC-I FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 67 of 105


Sheet 2 of 4 Status: YZ N7 U[]
Sheet 2 of 4 Status: YZ N7 U[]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. CV]             Floor El. 563           Room, Area' DEG 300 RAD 33 - Room LC
Location: Bldg. CV]
: 4. Does it appear that the area is free of potentially adverse seismic spatial       YE    NEI UED N/A-1 interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC
: 5. Does it appear that the area is free of potentially adverse seismic               Y9* NO UD N/AD interactions that could cause flooding or spray in the area?
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 6. Does it appear that the area is free of potentially adverse seismic               Y&* ND U- N/AD interactions that could cause a fire in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 7. Does it appear that the area is free of potentially adverse seismic               YZ NO U-          N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 8. Have you looked for and found no other seismic conditions that could             YE NEIUM adversely affect the safety functions of the equipment in the area?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
Comments (Additional pages may be added as necessary)
YE NEI UED N/A-1 Y9* NO UD N/AD Y&* ND U-N/AD YZ NO U-N/AD
: 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?
YE NEIUM Comments (Additional pages may be added as necessary)
Noted some small flexible VS lines in the area. This is not a problem due to adequate clearance and low mass.
Noted some small flexible VS lines in the area. This is not a problem due to adequate clearance and low mass.
AWC- IFW46.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 68 of 105
AWC-I FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 68 of 105


Sheet 3 of 4 Status: Y[   ND- U-Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: Y[
Location: Bldg. CV]         Floor E[. 563 Room, Area' DEG 300 RAD 33 - Room LC Evaluated by: Thomas]? Leilch                                   Date:     ~   721 Ra 'mond Fun                                     Date:           11 AWC- IFW46.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 69 of 105
ND-U-Area Walk-By Checklist (AWC)
Location: Bldg. CV]
Floor E[. 563 Room, Area' DEG 300 RAD 33 - Room LC Evaluated by: Thomas]? Leilch Date:  
~
721 Ra 'mond Fun Date:
11 AWC-I FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 69 of 105


Sheet 4 of 4 Status: Y:'] ND U[3 Area Walk-By Checklist (AWC)
Sheet 4 of 4 Status: Y:'] ND U[3 Area Walk-By Checklist (AWC)
Location: Bldg. CVI     Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC Photographs Note:                                     Note:
Location: Bldg. CVI Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC Photographs Note:
Note:                                     Note:
Note:
AWC - 1FW46.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 70 of 105
Note:
Note:
AWC - 1FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 70 of 105


Sheet 1of 3 Status: Y[     NEI UW Seismic Walkdown Checklist (SWC)
Sheet 1 of 3 Status: Y[
Equipment ID No. 1FW46                           Equip. Class, 00 (Other)
NEI UW Seismic Walkdown Checklist (SWC)
Equipment Description Refueling Cavity Drain Location: Bldg. CV1                 Floor El. 563             Room, Area DEG 300 RAD 33- Room LC Manufacturer, Model, Etc. (optional but recommended)               Westinghouse 09D-210 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL, The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment ID No. 1FW46 Equip. Class, 00 (Other)
Equipment Description Refueling Cavity Drain Location: Bldg. CV1 Floor El. 563 Room, Area DEG 300 RAD 33-Room LC Manufacturer, Model, Etc. (optional but recommended)
Westinghouse 09D-210 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL, The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one   YE N[9 of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one YE N[9 of the 50% of SWEL items requiring such verification)?
Line mounted item.
Line mounted item.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?             YD NE UE N/AN
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surface             YE NEI UL] N/AH oxidation?
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?     YE NEi     UE N/AZ
YD NE UE N/AN YE NEI UL] N/AH
: 5. Is the anchorage configuration consistent with plant documentation?           YE NE UD N/As (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of             Y9 NEI UE-potentially adverse seismic conditions?
YE NEi UE N/AZ
Enter the equipment class name fIom Appendix B: Classes of Equipment.
: 5. Is the anchorage configuration consistent with plant documentation?
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 71 of 105
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YE NE UD N/As Y9 NEI UE-Enter the equipment class name fIom Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 71 of 105


Sheet 2 of 3 Status: YE ND UR Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: YE ND UR Seismic Walkdown Checklist (SWC)
Equipment ID No. 1FW46                   Equip. Class, 00 (Other)
Equipment ID No.
1FW46 Equip. Class, 00 (Other)
Equipment Description Refueling Cavity Drain Interaction Effects
Equipment Description Refueling Cavity Drain Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     Y 0 ND UD N/AD
: 7. Are soft targets free from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YFJ ND- UD- N/AD and masonry block walls not likely to collapse onto the equipment?
Y 0 ND UD N/AD
: 9. Do attached lines have adequate flexibility to avoid damage?             YD1 NDI U-        N/AN Manual valve. No attached lines
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YFJ ND-UD-N/AD and masonry block walls not likely to collapse onto the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment free     YZ ND) UD of potentially adverse seismic interaction effects?
: 9. Do attached lines have adequate flexibility to avoid damage?
Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could     Y[   ND UD adversely affect the safety functions of the equipment?
Manual valve. No attached lines
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
YD1 NDI U-N/AN YZ ND) UD Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could Y[
ND UD adversely affect the safety functions of the equipment?
Cominents (Additional pages may be added as necessary)
Cominents (Additional pages may be added as necessary)
Ref CN-1491-FW.00-004 Evaluated by: Thomas R Leitch                     -  *,,Iq De/./
Ref CN-1491-FW.00-004 Evaluated by: Thomas R Leitch De/./
I-,                                                 F- A                     (2-.v, 22Z CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 72 of 105
*,,Iq I-,
F-A (2-.v, 22Z CNC-1206.03-00-0203 Rev 1 A Page 72 of 105


Sheet 3 of 3 Status: YN ND UD Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: YN ND UD Seismic Walkdown Checklist (SWC)
Equipment ID No, 1FW46                   Equip. Class, 00 (Other)
Equipment ID No, 1FW46 Equip. Class, 00 (Other)
Equipment Description Refueling Cavity Drain Photo rahs Note: 1FW46                                           Note:
Equipment Description Refueling Cavity Drain Photo rahs Note: 1FW46 Note:
Note:                                                 Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 73 of 105
Note:
CNC-1206.03-00-0203 Rev 1 A Page 73 of 105


Sheet I of 4 Status: YN NEI U[-
Sheet I of 4 Status: YN NEI U[-
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. RXI               Floor El. 557           Room, Areal DEG 280 REG60R Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Location: Bldg. RXI Floor El. 557 Room, Areal DEG 280 REG60R Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equjpment ID             Description                     Column Line or Other Location Info INVPDO042      Stnby M/U Disch Pulsa Damp                     Deg 278 Rad 58 El 558 INV865A        Stnby M/U Pump Suct fi'om XFR Tube Deg 266 Rad 61 El 578 INVPUSB        Standby Makeup Pump                             Deg 280 Rad 64 El 557 I. Does anchorage of equipment in the area appear to be free of                       YZ NEI      UD N/AR potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
Components: Equjpment ID I NVPDO042 INV865A INVPUSB Description Column Line or Other Location Info Stnby M/U Disch Pulsa Damp Deg 278 Rad 58 El 558 Stnby M/U Pump Suct fi'om XFR Tube Deg 266 Rad 61 El 578 Standby Makeup Pump Deg 280 Rad 64 El 557 I. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 2. Does anchorage of equipment in the area appear to be free of significant             Y[D NDI UD N/AD-degraded conditions?
YZ NEI UD N/AR
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YZ NDI UD N/AD raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 2. Does anchorage of equipment in the area appear to be free of significant Y[D NDI UD N/AD-degraded conditions?
If the room in which the SWEL item is located is vei) large (e.g., Turbine Hall), the area selected should be described.
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YZ NDI UD N/AD If the room in which the SWEL item is located is vei) large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC - I NVPUSB.DOC CNC-1206.03-00-0203 Rev I Attachment 7A Page 74 of 105
AWC - I NVPUSB.DOC CNC-1206.03-00-0203 Rev I A Page 74 of 105


Sheet 2 of 4 Status: Y[     NfI- UE]
Sheet 2 of 4 Status: Y[
NfI-UE]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. RXI               Floor El. .5.57_       Room, Area' DEG. 280 REG60R
Location: Bldg. RXI Floor El..5.57_
: 4. Does it appear that the area is free of potentially adverse seismic spatial YZ NDI      U-    N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
Room, Area' DEG. 280 REG60R
: 5. Does it appear that the area is fiee of potentially adverse seismic       YO NO U7 N/AD[
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic       YZ NDI UD N/AD-interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic         Y[    NDI  U[D N/ADI interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could       Y[E   ND1 UD-1 adversely affect the safety functions of the equipment in the area?
YZ NDI U-N/AD YO NO U7 N/AD[
AWC - I NV1)USB.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 75 of 105
YZ NDI UD N/AD-Y[
NDI U[D N/ADI
: 8. Have you looked for and found no other seismic conditions that could Y[E ND1 UD-1 adversely affect the safety functions of the equipment in the area?
AWC - I NV1)USB.DOC CNC-1206.03-00-0203 Rev 1 A Page 75 of 105


Sheet 3 of 4 Status: YZ N[       U[D Area Walk-By Checklist (AWC)
Sheet 3 of 4 Status: YZ N[
Location: Bldg. RXI             Floor El. 557         Room, Area' DEG 280 REG6OR Comments (Additional pages may be added as necessary)
U[D Area Walk-By Checklist (AWC)
Location: Bldg. RXI Floor El. 557 Room, Area' DEG 280 REG6OR Comments (Additional pages may be added as necessary)
Noted lighting on Poles attached to railing on elev. 575. These items are very flexible and not likely to survive a seismic event, however, they are not heavy or massive, and no targets were identified in the area that they would impact, so this is not an issue of concern.
Noted lighting on Poles attached to railing on elev. 575. These items are very flexible and not likely to survive a seismic event, however, they are not heavy or massive, and no targets were identified in the area that they would impact, so this is not an issue of concern.
Also noted that minimum 2" NV system clearance standardbetween 2 inch NV line and unistrut supporting a small electray is not met. The NV line is on CN-1491-NV. 00-117, elev 562'-9", and is almost directly above the pulsation dampener.(Approx Az 277, rad 59'-4"). This is not a QA I line, so this 2" clearanceis a good practice ratherthan a requirement. This clearance can be achieved by removing enough material from the unistrut to achieve the system clearance. See Photo.
Also noted that minimum 2" NV system clearance standard between 2 inch NV line and unistrut supporting a small electray is not met. The NV line is on CN-1491-NV. 00-117, elev 562'-9", and is almost directly above the pulsation dampener. (Approx Az 277, rad 59'-4"). This is not a QA I line, so this 2" clearance is a good practice rather than a requirement. This clearance can be achieved by removing enough material from the unistrut to achieve the system clearance. See Photo.
Evaluated by: Thomas R Leitch :&#xfd;           "        4                             Date:             /     /z-6 YA0A~p F14 -)67                            /20/20       /o1&#x17d;..
Evaluated by: Thomas R Leitch :&#xfd; 4
              ?aAlh~           ~
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AWC. INVPUS[3.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 76 of 105
~
Date:  
/  
/z-
/20/20  
/o1&#x17d;..
6 YA 0 A~p F14 -)67 AWC. INVPUS[3.DOC CNC-1206.03-00-0203 Rev 1 A Page 76 of 105


Sheet 4 of 4 Status: YZ ND- U-]
Sheet 4 of 4 Status: YZ ND-U-]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. RXI           Floor El. 557           Room, Area' DEG 280 REG60R Photographs Note: NV System Clearancenot met. Per                   Note:
Location: Bldg. RXI Floor El. 557 Room, Area' DEG 280 REG60R Photographs Note: NV System Clearance not met. Per Note:
MP/O/A/7650/153, good practice clearance for 250 degree NV line is 2" (Not required, since line is not QA 1, just good practice)
MP/O/A/7650/153, good practice clearance for 250 degree NV line is 2" (Not required, since line is not QA 1, just good practice)
Note:                                                     Note:
Note:
AWC- INVPUSB.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 77 of 105
Note:
AWC-INVPUSB.DOC CNC-1206.03-00-0203 Rev 1 A Page 77 of 105


Sheet I of 4 Status: YN Nn U-Seismic Walkdown Checklist (SWC)
Sheet I of 4 Status: YN Nn U-Seismic Walkdown Checklist (SWC)
Equipment ID No.       1NVPDO042               Equip. Class, 00 (Other)
Equipment ID No.
Equipment Description Standby Makeup Discharge Pulsation Dampener Location: Bldg. RXI               Floor El. 558           Room, Area DEG 278 RAD 58 Manufacturer, Model, Etc. (optional but recommended)             Metal Bellows Div Senior 76016 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
1NVPDO042 Equip. Class, 00 (Other)
Equipment Description Standby Makeup Discharge Pulsation Dampener Location: Bldg. RXI Floor El. 558 Room, Area DEG 278 RAD 58 Manufacturer, Model, Etc. (optional but recommended)
Metal Bellows Div Senior 76016 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one   YO NZ of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?               YE- NEi    UED N/AZ
YO NZ
: 3. Is the anchorage free of corrosion that is more than mild surface               YI[] N.,    UE- N/AZ oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 4. Is the anchorage free of visible cracks in the concrete neatr the anchors?     YE] NED UE] N/AZ
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?             YEO NEI UE] N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete neatr the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of             YR Nn U[1 potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YE-NEi UED N/AZ YI[] N.,
UE-N/AZ YE] NED UE] N/AZ YEO NEI UE] N/AZ YR Nn U[1
' Enter the equipment class name from Appendix B: Classes of Equipment.
' Enter the equipment class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 78 of 105
CNC-1206.03-00-0203 Rev 1 A Page 78 of 105


Sheet 2 of 4 Status: YN ND- U-Seismic Walkdown Checklist (SWC)
Sheet 2 of 4 Status: YN ND-U-Seismic Walkdown Checklist (SWC)
Equipment ID No.     INVPDO042               Equip. Class, 00 (Other)
Equipment ID No.
Equipment Description Standby Makeup Discharoe PulsationDampener Interaction Effects
INVPDO042 Equip. Class, 00 (Other)
: 7. Are soft targets free from impact by nearby equipment or structures?     Y(9 ND U[ N/AD
Equipment Description Standby Makeup Discharoe Pulsation Dampener Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?
Y(9 ND U[ N/AD
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD]
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD]
and masonry block walls not likely to collapse onto the equipment?
and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YZ ND UD1 N/A[]
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     YZ NO UD of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions
YZ ND UD1 N/A[]
: 11. Have you looked for and found no other seismic conditions that could     YN ND UD adversely affect the safety functions of the equipment?
YZ NO UD Other Adverse Conditions
Noted one spring can from vertical trapeze support that is supporting the pulsation dampener is almost touching the metal belt guard on the PD pump. There are two Type A B268 spring cans, and one is only 1/8" clear of the metal belt guard for the PD pump. The can weights no more than 15# and it is a vertical support, so its horizontal seismic motion is limited by rod tension and restraintat the top and bottom of the can. Some limited minor seismic interaction with the belt guard is possible, but the potential unrestrained(no interaction) horizontal motion would not be likely to exceed X" since the seismic driving force involved should be less than one G. This could result in minimal seismic interaction with the metal belt guard, but the guard appears robust enough to withstand the small forces involved without significant damage. Also, the pump is radwaste related (QA2) but it is not designed as seismically supported, and the piping supported by the spring cans is class E and supportedper Construction requirements, which are also non seismic. These items are both part of SWEL 2, not SWEL 1. See photo.
: 11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 79 of 105
Noted one spring can from vertical trapeze support that is supporting the pulsation dampener is almost touching the metal belt guard on the PD pump. There are two Type A B268 spring cans, and one is only 1/8" clear of the metal belt guard for the PD pump. The can weights no more than 15# and it is a vertical support, so its horizontal seismic motion is limited by rod tension and restraint at the top and bottom of the can. Some limited minor seismic interaction with the belt guard is possible, but the potential unrestrained (no interaction) horizontal motion would not be likely to exceed X" since the seismic driving force involved should be less than one G. This could result in minimal seismic interaction with the metal belt guard, but the guard appears robust enough to withstand the small forces involved without significant damage. Also, the pump is radwaste related (QA2) but it is not designed as seismically supported, and the piping supported by the spring cans is class E and supported per Construction requirements, which are also non seismic. These items are both part of SWEL 2, not SWEL 1. See photo.
YN ND UD CNC-1206.03-00-0203 Rev 1 A Page 79 of 105


Sheet 3 of 4 Status: YZ NT-D UWE Seismic Walkdown Checklist (SWC)
Sheet 3 of 4 Status: YZ NT-D UWE Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NVPDO042             Equip. Class2 00 (Other)
Equipment ID No.
Equipment Description Standby Makeup DischarLe PulsationDampener Comments (Additional pages may be added as necessary)
1NVPDO042 Equip. Class2 00 (Other)
Equipment Description Standby Makeup DischarLe Pulsation Dampener Comments (Additional pages may be added as necessary)
Ref Drwgs CNM-1201.04-0174.001 and CN-1491-NV.00-117. Pulsation dampener was recently replaced by mod EC 102855.
Ref Drwgs CNM-1201.04-0174.001 and CN-1491-NV.00-117. Pulsation dampener was recently replaced by mod EC 102855.
Evaluated by: Thomas R Leitch       '*                                  Date:   6 ,//9/A0/3 2 21   ~-~i CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 80 of 105
Evaluated by: Thomas R Leitch Date:
6,//9/A0/3 2 21 ~-~i CNC-1206.03-00-0203 Rev 1 A Page 80 of 105


Sheet 4 of 4 Status: YO ND U-Seismic Walkdown Checklist (SWC)
Sheet 4 of 4 Status: YO ND U-Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NVPDO042             Equip. Class' 00 (Other)
Equipment ID No. 1NVPDO042 Equip. Class' 00 (Other)
Equipment Description Standby Makeup Discharge PulsationDampener P
Equipment Description Standby Makeup Discharge Pulsation Dampener P
Note: PD support and left spring.                   fNote:
Note: PD support and left spring.
L   At Note: Right spring close to belt guard.             Note:
fNote:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 81 of 105
L At Note: Right spring close to belt guard.
Note:
CNC-1206.03-00-0203 Rev 1 A Page 81 of 105


Sheet I of 3 Status: Y19 NEI UD Seismic Walkdown Checklist (SWC)
Sheet I of 3 Status: Y19 NEI UD Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NV865A                         Equip. Class, 8 (MOVI Equipment Description Standby M/U Pump Suction from XFR Tube Location*: Bldg. AN1               Floor El. 578           Room, Area DEG 266 RAD 61 Manufacturer, Model, Etc. (optional but recommended)             Borg Warner 05B-262 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment ID No. 1NV865A Equip. Class, 8 (MOVI Equipment Description Standby M/U Pump Suction from XFR Tube Location*: Bldg. AN1 Floor El. 578 Room, Area DEG 266 RAD 61 Manufacturer, Model, Etc. (optional but recommended)
Anchorape I. Is the anchorage configuration verification required (i.e., is the item one   YD NZ of the 50% of SWEL items requiring such verification)?
Borg Warner 05B-262 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
: 2. Is the anchorage free of bent, broken, missing or loose hardware?             YEI NE] UE- N/AZ
Anchorape I. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 3. Is the anchorage free of corrosion that is more than mild surface             YE] NE] UD N/AED oxidation?
YD NZ
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?     Yn NEI- UiC     N/A9
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 5. Is the anchorage configuration consistent with plant documentation?           YD- N[-I UI-1 N/AZ]
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
YEI NE] UE-N/AZ YE] NE] UD N/AED
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
Yn NEI-UiC N/A9
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
YE] NE    UE]
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
Enter the equipment class name from Appendix 13:Classes of Equipment.
YD-N[-I UI-1 N/AZ]
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 82 of 105
YE] NE UE]
Enter the equipment class name from Appendix 13: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 82 of 105


Sheet 2 of 3 Status: YN ND UM Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: YN ND UM Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NV865A                     Equip. Class, 8 (MOV)
Equipment ID No. 1NV865A Equip. Class, 8 (MOV)
Equipment Description Standby M/U Pump Suction from XFR Tube Interaction Effects
Equipment Description Standby M/U Pump Suction from XFR Tube Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     YZ ND UD N/AL
: 7. Are soft targets free from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 ND UD N/ALl and masonry block walls not likely to collapse onto the equipment?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YN ND UD N/AD
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     YN NEI U-of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions I1. Have you looked for and found no other seismic conditions that could     YZ ND UD adversely affect the safety functions of the equipment?
YZ ND UD N/AL Y0 ND UD N/ALl YN ND UD N/AD YN NEI U-Other Adverse Conditions I 1. Have you looked for and found no other seismic conditions that could YZ ND UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Ref drawing CN-]491-N]     / 16.
Ref drawing CN-]491-N]  
Evaluated by: */o.at'71a.       Z? L& L                                         Date:
/ 16.
(,4~ 6/~         7 J~((J4 ____
Evaluated by: */o.at'71a.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 83 of 105
Z? L& L Date:
(,4~ 6/~
7J~((J4____
CNC-1206.03-00-0203 Rev 1 A Page 83 of 105


I- -
I-Sheet 3 of 3 Status: Y[D NE UF Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: Y[D NE UF Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NV865A Equip. Class1 8 (MOVW Equipment Description Standby M/U Pum" Suction from XFR Tube Photozraphs Note:
Equipment ID No. 1NV865A           Equip. Class1 8 (MOVW Equipment Description Standby M/U Pum" Suction from XFR Tube Photozraphs Note:
Note:
Note:                                               Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 84 of 105
CNC-1206.03-00-0203 Rev 1 A Page 84 of 105


Sheet 1 of 4 Status: YZ' N-1 ULD Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No.       1NVPUSB                   Equip. Class, 5 (Horizontal Pump)
Sheet 1 of 4 Status: YZ' N-1 ULD Equipment ID No.
Equipment Description Standby Makeup Pump                   ,
1NVPUSB Equip. Class, 5 (Horizontal Pump)
Location: Bldg. RXI                 Floor El. 557           Room, Area DEG 280 RAD 064 Manufacturer, Model, Etc. (optional but recommended)             Whealley S/N 5P1510 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description Standby Makeup Pump Location: Bldg. RXI Floor El. 557 Room, Area DEG 280 RAD 064 Manufacturer, Model, Etc. (optional but recommended)
Whealley S/N 5P1510 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is (lte anchorage configuration verification required (i.e., is the item one YE NO of the 50% of SWEL items requiring such verification)?
: 1. Is (lte anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardwaare?           Y[Z NDi U        N/AD--
YE NO
: 3. Is the anchorage free of corrosion that is more than mild surface             YO NED UD N/AEZ oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardwaare?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?     YZ ND U- N/AD
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?           YlZ NI ULD N/AD1 (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of             YZ NEI UD potentially adverse seismic conditions?
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
Y[Z ND i U N/AD--
YO NED UD N/AEZ YZ ND U-N/AD YlZ NI ULD N/AD1 YZ NEI UD
' Enter the equipment class name from Appendix B: Classes of Equipment.
' Enter the equipment class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 85 of 105
CNC-1206.03-00-0203 Rev 1 A Page 85 of 105


Sheet 2 of 4 Status: YZ NF[       UZ-Seismic Walkdown Checklist (SWC)
Sheet 2 of 4 Status: YZ NF[
Equipment ID No. 1NVPUSB                     Equip. Class, 5 (Horizontal Pump)
UZ-Seismic Walkdown Checklist (SWC)
Equipment ID No. 1NVPUSB Equip. Class, 5 (Horizontal Pump)
Equipment Description Standby Makeup Pump Interaction Effects
Equipment Description Standby Makeup Pump Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?     Y Z NO UD N/AM
: 7. Are soft targets free from impact by nearby equipment or structures?
Y Z NO UD N/AM
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ No UD N/AD and masonry block walls not likely to collapse onto the equipment?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ No UD N/AD and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YZ NDI UD N/AD
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free     YE NO UD of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions
YZ NDI UD N/AD YE NO UD Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could     YZ NO UE adversely affect the safety functions of the equipment?
: 11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
YZ NO UE Comments (Additional pages may be added as necessary)
Note that Standby makeup pump support is not safety related, although it is well built and appearsto be quite sturdy. The Standby makeup pump and the piping leading into and out of it are class E, radwaste related, and are not seismic category 1. They were never intended to be seismically designed. This is acceptable due to the system design. These components were selected for walk down as part of the SWEL 2 list, which does not have to be seismic category 1.
Note that Standby makeup pump support is not safety related, although it is well built and appears to be quite sturdy. The Standby makeup pump and the piping leading into and out of it are class E, radwaste related, and are not seismic category 1. They were never intended to be seismically designed. This is acceptable due to the system design. These components were selected for walk down as part of the SWEL 2 list, which does not have to be seismic category 1.
Ref CNM-1203.03-0080, CN-1080-22, CN-1491-07.00-08, CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 86 of 105
Ref CNM-1203.03-0080, CN-1080-22, CN-1491-07.00-08, CNC-1206.03-00-0203 Rev 1 A Page 86 of 105


Sheet 3 of 4 Status: YZ N-I UM Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INVPUSB           Equip. Class, 5 (Horizontal Pump)
Equipment ID No.
Equipment Description Standby Makeup Pump Evaluated by: Thomas R. Leitch "7"-li       le                         Date:   0     /, /*.z,/-3 Raymond C Fung                                                      2       z2o-l, CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 87 of 105
INVPUSB Equip. Class, 5 (Horizontal Pump)
Equipment Description Standby Makeup Pump Sheet 3 of 4 Status: YZ N-I UM Evaluated by: Thomas R. Leitch "7"-li le Raymond C Fung Date:
0  
/,  
/*.z,/-3 2
z2o-l, CNC-1206.03-00-0203 Rev 1 A Page 87 of 105


Sheet 4 of 4 Status: YZ NF U[D]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. INVPUSB           Equip. Class' 5 (Horizontal Pump)
Equipment ID No.
Equipment Description Standby Makeuo Pump Note: Anchorage in good condition.
INVPUSB Equip. Class' 5 (Horizontal Pump)
Equipment Description Standby Makeuo Pump Sheet 4 of 4 Status: YZ NF U[D]
Note: Anchorage in good condition.
Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 88 of 105
CNC-1206.03-00-0203 Rev 1 A Page 88 of 105


Sheet I of 4 Status: YN ND UD Area Walk-By Checklist (AWC)
Sheet I of 4 Status: YN ND UD Area Walk-By Checklist (AWC)
Location: Bldg. A UX             Floor El. 594           Room, Area, CC-55 (Control Room)
Location: Bldg. A UX Floor El. 594 Room, Area, CC-55 (Control Room)
Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column Line oi- Other Location Info I SSPSA Solid State Protection Syst, Train A         CC-56 (Control Room)
Components: Equipment ID Description Column Line oi-Other Location Info I SSPSA Solid State Protection Syst, Train A CC-56 (Control Room)
I Does anchorage of equipment in the area appear to be free of                       YZ ND UD N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
I Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
1SSPSA anchorage was visible when cabinet was opened, and one other cabinet (IELCCO058) had anchorage that was visible when cabinet was closed. No other cabinets in the walk-by area were available to be opened. Anchors that were visible were free of potentially adverse seismic conditions.(see photo)
1SSPSA anchorage was visible when cabinet was opened, and one other cabinet (IELCCO058) had anchorage that was visible when cabinet was closed. No other cabinets in the walk-by area were available to be opened. Anchors that were visible were free of potentially adverse seismic conditions. (see photo)
: 2. Does anchorage of equipment in the area appear to be free of significant           YN ND] UD) N/AD degraded conditions?
YZ ND UD N/AD
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YZ NDI UD N/AD1 raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 2. Does anchorage of equipment in the area appear to be free of significant YN ND] UD) N/AD degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
Initially, these items were not visible from the floor due to lightweight ceiling material. A subsequent walk by was performed to remove a sample of ceiling material to allow visual inspection of the cable conduit raceways and HVAC ducting in the walk by area ceiling. The HVAC Ducting and supports were in excellent condition. There are only a few cable Iconduit raceways, they are not overfilled and are adequately supported.
Initially, these items were not visible from the floor due to lightweight ceiling material. A subsequent walk by was performed to remove a sample of ceiling material to allow visual inspection of the cable conduit raceways and HVAC ducting in the walk by area ceiling. The HVAC Ducting and supports were in excellent condition. There are only a few cable Iconduit raceways, they are not overfilled and are adequately supported.
YZ NDI UD N/AD1
'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC- ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 89 of 105
AWC-I SSPSA.DOC CNC-1206.03-00-0203 Rev 1 A Page 89 of 105


Sheet 2 of 4 Status: Y[* NM U--
Sheet 2 of 4 Status: Y[* NM U--
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. A UX             Floor El. 594           Room, Area3 CC-55 (Control Room)
Location: Bldg. A UX Floor El. 594 Room, Area3 CC-55 (Control Room)
: 4. Does it appear that the area is free of potentially adverse seismic spatial YN ND UD N/ADI interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
Ceiling materialis very light weight and would not adversely interact due to low mass. Lighting appearsto be well secured to prevent failure during a seismic event. The lighting fixtures are also tethered with light chains to prevent them from falling.
Ceiling material is very light weight and would not adversely interact due to low mass. Lighting appears to be well secured to prevent failure during a seismic event. The lighting fixtures are also tethered with light chains to prevent them from falling.
: 5. Does it appear that the area is fiee of potentially adverse seismic         Y1Z NDI UD3 N/ADI interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is fiee of potentially adverse seismic         YS ND UD N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic         Y0 ND UD N/AD1 interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could       YN NDI UDI adversely affect the safety functions of the equipment in the area?
YN ND UD N/ADI Y1Z NDI UD3 N/ADI YS ND UD N/AD Y0 ND UD N/AD1
: 8. Have you looked for and found no other seismic conditions that could YN NDI UDI adversely affect the safety functions of the equipment in the area?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
AWC- ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 90 of 105
AWC-ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 A Page 90 of 105


Sheet 3 of 4 Status: Y[     ND Ui-]
Sheet 3 of 4 Status: Y[
ND Ui-]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. AUX           Floor El. 594   Room, Area' CC-55 LControl Room)
Location: Bldg. AUX Floor El. 594 Room, Area' CC-55 LControl Room)
Evaluated by: Thomas R Leitch               1                         Date: 02/20/2013 Ra 'mond C FII)7g                                               Y22, 1121V 13 AWC- ISSI'SA.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 91 of 105
Evaluated by: Thomas R Leitch 1
Date: 02/20/2013 Ra 'mond C FII)7g Y22, 1121V 13 AWC-ISSI'SA.DOC CNC-1206.03-00-0203 Rev 1 A Page 91 of 105


Sheet 4 of 4 Status: Y[     NO U[-
Sheet 4 of 4 Status: Y[
NO U[-
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. AUX           Floor El. 594 Room, Area, CC-55 (.Control Room)
Location: Bldg. AUX Floor El. 594 Room, Area, CC-55 (.Control Room)
Photo2ravhs INote: ivo aaverse Interacrions.               iNote: lignrweignh ceuiing mareriat i
Photo2ravhs INote: ivo aaverse Interacrions.
iN ote: lignrweignh ceuiing mareriat i
Note: Lighting Fixture chain tether.
Note: Lighting Fixture chain tether.
AWC- ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 92 of 105
AWC-ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 A Page 92 of 105


Seismic Walkdown Checklist (SWC)
Sheet 1 Of 3 Status: YZ No U[
Sheet 1 Of 3 Status: YZ No U[
Seismic Walkdown Checklist (SWC)
Equipment ED No.
Equipment ED No.       ISSPSA                   Equip. Class, 18 (Equipment Rack)
ISSPSA Equip. Class, 18 (Equipment Rack)
Equipment Description Solid State Protection System Train A Location: Bldg. AUX                 Floor El. 594           Room, Area CC-55 Manufacturer, Model, Etc. (optional but recommended)             WestinO05678 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description Solid State Protection System Train A Location: Bldg. AUX Floor El. 594 Room, Area CC-55 Manufacturer, Model, Etc. (optional but recommended)
WestinO05678 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one YZ NEI of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?           YE  NEI UD" N/AD
YZ NEI
: 3. Is the anchorage free of corrosion that is more than mild surface           YZ NED UD) N/AD oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?   YZ NEI U0 N/AD
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?         Y(3 NDl UD N/AD-(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
YE NEI UD" N/AD YZ NED UD) N/AD
: 6. Based on the above anchorage evaluations, is the anchorage free of         YZ NEI U-potentially adverse seismic conditions?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
Enter the equipment class name from Appendix B: Classes of Equipment.
YZ NEI U0 N/AD
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 93 of 105
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
Y(3 NDl UD N/AD-YZ NEI U-Enter the equipment class name from Appendix B: Classes of Equipment.
CNC-1206.03-00-0203 Rev 1 A Page 93 of 105


Sheet 2 of 3 Status: Y[     ND-- U-Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: Y[
Equipment ID No. 1SSPSA                       Equip. Class' 18 (Equipment Rack)
ND-- U-Seismic Walkdown Checklist (SWC)
Equipment ID No. 1SSPSA Equip. Class' 18 (Equipment Rack)
Equipment Description Solid State Protection System Train A Interaction Effects
Equipment Description Solid State Protection System Train A Interaction Effects
: 7. Are soft targets firee from impact by nearby equipment or structures?     Y[9 ND1 iJEI N/AE3
: 7. Are soft targets firee from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y9 N.1     UD3 N/ADl and masonry block walls not likely to collapse onto the equipment?
Y[9 ND1 iJEI N/AE3
Ceiling tiles appearin acceptable condition, and also are very light weight. If any were to fall, they would not have enough mass to cause damage or operate the equipment.
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y9 N.1 UD3 N/ADl and masonry block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?             YZI NDO ULI N/AD Attached lines are cables, and there is enough flexibility to avoid damage. See Photo.
Ceiling tiles appear in acceptable condition, and also are very light weight. If any were to fall, they would not have enough mass to cause damage or operate the equipment.
: 10. Based on the above seismic interaction evaluations, is equipment free     YZ NEI Ur of potentially adverse seismic interaction effects?
: 9. Do attached lines have adequate flexibility to avoid damage?
Other Adverse Conditions
Attached lines are cables, and there is enough flexibility to avoid damage. See Photo.
: 11. Have you looked for and found no other seismic conditions that could     YED NED UD adversely affect the safety functions of the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
YZI NDO ULI N/AD YZ NEI Ur Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could YED NED UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
The cabinet is well anchored, and cables and fasteners are in good condition, with good sealing in floor penetrationarea. Reference CNC-1139.14-19-0001, CN- 1200-10.04, CNM- 1399.08-0039-005, CN-1214-01, CN-1224-05, CN-1227-05.
The cabinet is well anchored, and cables and fasteners are in good condition, with good sealing in floor penetration area. Reference CNC-1139.14-19-0001, CN-1200-10.04, CNM-1399.08-0039-005, CN-1214-01, CN-1224-05, CN-1227-05.
Evaluated by: ThomasRLeitch               ei"r                 I               Date: 12/06/2012 Ravmond C Funo 1--j Q    7-'
Evaluated by: ThomasRLeitch ei"r I
                                                            -  "9 CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 94 of 105
Ravmond C Funo Q
7-' -
"9 Date: 12/06/2012 1--j CNC-1206.03-00-0203 Rev 1 A Page 94 of 105


Sheet 3 of 3 Status: Y[     NEI U-Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. ISSPSA                   Equip. Class' 18 (Equipment Rack)
Sheet 3 of 3 Status: Y[
Equipment Description Solid State Protection System Train A Photographs Photographs r~ote: 7, Note: Cables well sealed with adequate flex.           Note: Load path.
NEI U-Equipment ID No. ISSPSA Equip. Class' 18 (Equipment Rack)
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 95 of 105
Equipment Description Solid State Protection System Train A Photographs Photographs r~ote: 7, Note: Cables well sealed with adequate flex.
Note: Load path.
CNC-1206.03-00-0203 Rev 1 A Page 95 of 105


Sheet I of 4 Status: YE) NR- U-Area Walk-By Checklist (AWC)
Sheet I of 4 Status: YE) NR-U-Area Walk-By Checklist (AWC)
Location: Bldg. Aux               Floor El. 560           Room, Area, Aux 560 Rm 372, AA-51 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Location: Bldg. Aux Floor El. 560 Room, Area, Aux 560 Rm 372, AA-51 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.
Additional space is provided at the end of this checklist for documenting other comments.
Components: Equipment ID             Description                     Column Line or Other Location Info 1ETXB            4160/600 VAC Trans           AA-47 IETXD            4160/600 VAC Trans             AA-46
Components: Equipment ID 1ETXB I ETXD Description 4160/600 VAC Trans 4160/600 VAC Trans Column Line or Other Location Info AA-47 AA-46
: 1. Does anchorage of equipment in the area appear to be free of                       YE    N[    U-I'N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
: 1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?
YE N[
U-I' N/AD
: 2. Does anchorage of equipment in the area appear to be free of significant YZ NE] UD N/An degraded conditions?
: 2. Does anchorage of equipment in the area appear to be free of significant YZ NE] UD N/An degraded conditions?
: 3. Based on a visual inspection from the floor, do the cable/conduit                   YO NDI      UD1 N/AD3 raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
: 3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?
YO NDI UD1 N/AD3
,If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
,If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.
AWC - I ,TXB-20120620.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 96 of 105
AWC - I,TXB-20120620.DOC CNC-1206.03-00-0203 Rev 1 A Page 96 of 105


Sheet 2 of 4 Status: YD&#xfd; NDi UD-Area Walk-By Checklist (AWC)
Sheet 2 of 4 Status: YD&#xfd; NDi UD-Area Walk-By Checklist (AWC)
Location: Bldg. Aux             Floor El. 560           Room, Arca'I/ux 560 Rin 372, AA-S]
Location: Bldg. Aux Floor El. 560 Room, Arca' I/ux 560 Rin 372, AA-S]
: 4. Does it appear that the area is free of potentially adverse seismic spatial YN ND UD N/AD' interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
: 5. Does it appear that the area is free of potentially adverse seismic         YE Nn U0 N/AD interactions that could cause flooding or spray in the area?
: 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
: 6. Does it appear that the area is free of potentially adverse seismic         YZ ND UD N/AD interactions that could cause a fire in the area?
: 6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
: 7. Does it appear that the area is free of potentially adverse seismic         Y{J N[D] UD N/ADI interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?
: 8. Have you looked for and found no other seismic conditions that could       YE1 ND UD adversely affect the safety functions of the equipment in the area?
YN ND UD N/AD' YE Nn U0 N/AD YZ ND UD N/AD Y{J N[D] UD N/ADI
AWC - IFIX~3-20120 620. DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 97 of 105
: 8. Have you looked for and found no other seismic conditions that could YE1 ND UD adversely affect the safety functions of the equipment in the area?
AWC - IFIX~3-20120 620. DOC CNC-1206.03-00-0203 Rev 1 A Page 97 of 105


Sheet 3 of 4 Status: Y[       N7 U[]
Sheet 3 of 4 Status: Y[
N7 U[]
Area Walk-By Checklist (AWC)
Area Walk-By Checklist (AWC)
Location: Bldg. Aiux               Floor El. 560           Room, Areal AJg 560 Rkn 372, AA-51 Comments (Additional pages may be added as necessary)
Location: Bldg. Aiux Floor El. 560 Room, Areal AJg 560 Rkn 372, AA-51 Comments (Additional pages may be added as necessary)
Area was very neat and clean. Noted 4 hand held fire extinguishers hanging on hooks fairly low on columns in the area.
Area was very neat and clean. Noted 4 hand held fire extinguishers hanging on hooks fairly low on columns in the area.
These are not likely to come off hooks during event, because the vertical component of seismic acceleration in this area is less than Ig. Also, no significant spray targets were noted in the immediate vicinity of these devices.
These are not likely to come off hooks during event, because the vertical component of seismic acceleration in this area is less than Ig. Also, no significant spray targets were noted in the immediate vicinity of these devices.
A rigid cable tray support with approximately 3/8" clearance between the support and a lifting lug on I ETXF was noted. (see photo) This is acceptable by comparison, because rigid cabinets in this area will experience a lateral seismic movement of approx. 0.1 inches, and the transformer is at least as rigid as these cabinets. Similarly, the cable tray support frame is rigid, and seismic movements of approx 0.1 inches are expected. Therefore this clearance should be adequate to prevent interaction.
A rigid cable tray support with approximately 3/8" clearance between the support and a lifting lug on I ETXF was noted. (see photo) This is acceptable by comparison, because rigid cabinets in this area will experience a lateral seismic movement of approx. 0.1 inches, and the transformer is at least as rigid as these cabinets. Similarly, the cable tray support frame is rigid, and seismic movements of approx 0.1 inches are expected. Therefore this clearance should be adequate to prevent interaction.
Evaluated by: Thomas R Leitch           -          *
Evaluated by: Thomas R Leitch Date:
* Date:                   20--1-3"27 Ravniond Fzmgw                                                             Date:     /-   /7   *,
1-3"27 20--
AWC   - ICTXB-20120620.DOC CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 98 of 105
Ravniond Fzmgw Date:  
/-  
/7 AWC - I CTXB-20120620.DOC CNC-1206.03-00-0203 Rev 1 A Page 98 of 105


Sheet 4 of 4 Status: YE NE]       U-Area Walk-By Checklist (AWC)
Sheet 4 of 4 Status: YE NE] U-Area Walk-By Checklist (AWC)
Location: Bldg. Aux             Floor El. 560           Room, Area, Aux 560 RnI 372, AA-51 i'iote: t.awie tray supporr ciose uo im iug on 7t: i At-   Note:
Location: Bldg. Aux Floor El. 560 Room, Area, Aux 560 RnI 372, AA-51 i'iote: t.awie tray supporr ciose uo im iug on 7t: i At-Note:
Note:                                                       Note:
Note:
AWC - IMTB-20120620.DOX7 CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 99 of 105
Note:
AWC - IMTB-20120620.DOX7 CNC-1206.03-00-0203 Rev 1 A Page 99 of 105


Sheet I of 3 Status: YED N-- U-Seismic Walkdown Checklist (SWC)
Sheet I of 3 Status: YED N-- U-Seismic Walkdown Checklist (SWC)
Equipment ID No. 1ETXB                           Equip. Class' 4 (Transformers)
Equipment ID No. 1ETXB Equip. Class' 4 (Transformers)
Equipment Description 4160/600 VAC Transformer Location: Bldg. Aux                 Floor El. 560           Room, Area Rm 372 Area AA-47 Manufacturer, Model, Etc. (optional but recommended)               Westing house 4160-600Y/346 Instructions for Completing Cheeldist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Equipment Description 4160/600 VAC Transformer Location: Bldg. Aux Floor El. 560 Room, Area Rm 372 Area AA-47 Manufacturer, Model, Etc. (optional but recommended)
Westing house 4160-600Y/346 Instructions for Completing Cheeldist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorae.
Anchorae.
: 1. Is the anchorage configuration verification required (i.e., is the ilem one     YZ NEI of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the ilem one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?               YN NED UIJ] N/AF!
YZ NEI
Transformeris welded to W section that is welded to steel plate which is welded to embedments. No broken welds or bent areas were observed..
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surface                 YtN NEI U7- N/AD oxidation?
Transformer is welded to W section that is welded to steel plate which is welded to embedments. No broken welds or bent areas were observed..
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?         YDE NEI UW1 N/AZ There are no anchors,but the concrete is free of cracks.
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 5. Is the anchorage configuration consistent with plant documentation?               Y5 NEI UD) N/A[U (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
: 6. Based on the above anchorage evaluations, is the anchorage free of               YE    Nn UE1 potentially adverse seismic conditions?
There are no anchors, but the concrete is free of cracks.
Elner the equipment class name from Appendix B: Classes of Equipmein.
: 5. Is the anchorage configuration consistent with plant documentation?
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 100 of 105
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YN NED UIJ] N/AF!
YtN NEI U7-N/AD YDE NEI UW1 N/AZ Y5 NEI UD) N/A[U YE Nn UE1 Elner the equipment class name from Appendix B: Classes of Equipmein.
CNC-1206.03-00-0203 Rev 1 A Page 100 of 105


Sheet 2 of 3 Status: YN NO) UF]
Sheet 2 of 3 Status: YN NO) UF]
Seismic Walkdown Checklist (SWC)
Seismic Walkdown Checklist (SWC)
Equipment ID No. 1ETXB                   Equip. Class' 4 (Transformers)
Equipment ID No.
1ETXB Equip. Class' 4 (Transformers)
Equipment Description 4160/600 VAC Transformer Interaction Effects
Equipment Description 4160/600 VAC Transformer Interaction Effects
: 7. Are soft targets free from impact by nearby equipment or structures?       YE     ND U0- N/AD
: 7. Are soft targets free from impact by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting,   YZ ND U[] N/AD]
YE ND U0- N/AD
: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND U[] N/AD]
and mason'y block walls not likely to collapse onto the equipment?
and mason'y block walls not likely to collapse onto the equipment?
: 9. Do attached lines have adequate flexibility to avoid damage?                 Y9 NDI UD1 N/A[I
: 9. Do attached lines have adequate flexibility to avoid damage?
: 10. Based on the above seismic interaction evaluations, is equipment free       YO* ND U[D of potentially adverse seismic interaction effects?
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
Other Adverse Conditions
Y9 NDI UD1 N/A[I YO* ND U[D Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could         Y[9 ND UED adversely affect the safety functions of the equipment?
: 11. Have you looked for and found no other seismic conditions that could Y[9 ND UED adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Noted one cable tray support (rigid)has only minimal clearance (approx. 118') from transformer cooling fin support steel. Based on comparison with rigid cabinets in this area, this could result in minimal seismic interactionbetween the fin support steel and the cable tray support. This interactionwould be in the orderof 0. 1 inches or less, since the tray support could move approx.
Noted one cable tray support (rigid) has only minimal clearance (approx. 118') from transformer cooling fin support steel. Based on comparison with rigid cabinets in this area, this could result in minimal seismic interaction between the fin support steel and the cable tray support. This interaction would be in the order of 0. 1 inches or less, since the tray support could move approx.
: 0. 1 inches and the transformer could move approx. 0. 1 inches, which could result in some minor yielding and distortion, primarilyin the cable tray support unistrut material.
: 0. 1 inches and the transformer could move approx. 0. 1 inches, which could result in some minor yielding and distortion, primarily in the cable tray support unistrut material.
Evaluated by: Thomas R Leitch                                                       Date:   ,2   ,--    _-    _ _
Evaluated by: Thomas R Leitch Date:  
Raymond C Funa              fi~&~                                    Date:     2/7 2.e/3 CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 101 of 105
,2 Date:
2/7 2.e/3 Raymond C Funa fi~&~
CNC-1206.03-00-0203 Rev 1 A Page 101 of 105


Sheet 3 of 3 Status: YN NR- UR Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: YN NR-UR Seismic Walkdown Checklist (SWC)
Equipment ID No. 1ETXB                   Equip. Class' 4 (Transformers)
Equipment ID No. 1ETXB Equip. Class' 4 (Transformers)
Equipment Description 4160/600 VAC Transformer Ph, Photographs Note: Minimal clearance between lug and cable         Note:
Equipment Description 4160/600 VAC Transformer Ph, otographs Photographs Note: Minimal clearance between lug and cable tray support.
tray support.
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 102 of 105
CNC-1206.03-00-0203 Rev 1 A Page 102 of 105


Sheet 1 of 3 Status: Y[K N--     UD Seismic Walkdown Checklist (SWC)
Sheet 1 of 3 Status: Y[K N-- UD Seismic Walkdown Checklist (SWC)
Equipment ID No.         IETXD                   Equip. Class' 4 (Transformers)
Equipment ID No.
Equipment Description 4160/600 VAC Transformer Location: Bldg. Aux                 Floor El. 560           Room, Area Rm 372 Area AA-46 Manufacturer, Model, Etc. (optional but recommended)             Westing house 4160-600Y/346 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
IETXD Equip. Class' 4 (Transformers)
Equipment Description 4160/600 VAC Transformer Location: Bldg. Aux Floor El. 560 Room, Area Rm 372 Area AA-46 Manufacturer, Model, Etc. (optional but recommended)
Westing house 4160-600Y/346 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.
Anchorage
Anchorage
: 1. Is the anchorage configuration verification required (i.e., is the item one   Y[  NO of the 50% of SWEL items requiring such verification)?
: 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?             YN ND U0 N/AE]
Y[
Transformeris welded to Wsection that is welded to steel plate which is welded to embedments. No broken welds or bent areas were observed.
NO
: 3. Is the anchorage free of corrosion that is more than mild surface             YZ NDI- UDE N/AD oxidation?
: 2. Is the anchorage free of bent, broken, missing or loose hardware?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?     YD ND UD N/AED The concrete is free of visible cracks near the embedded plates. The only anchors are the nelson studs that are welded to the underside of the embedded plates.
Transformer is welded to Wsection that is welded to steel plate which is welded to embedments. No broken welds or bent areas were observed.
: 5. Is the anchorage configuration consistent with plant documentation?           YD    ND UD- N/AD (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
: 6. Based on tlhe above anchorage evaluations, is the anchorage free of             YZ ND UD potentially adverse seismic conditions?
: 4. Is the anchorage free of visible cracks in the concrete near the anchors?
IEnter the equipment class name from Appendix B: Classes of Equipmem.
The concrete is free of visible cracks near the embedded plates. The only anchors are the nelson studs that are welded to the underside of the embedded plates.
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 103 of 105
: 5. Is the anchorage configuration consistent with plant documentation?
(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
: 6. Based on tlhe above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YN ND U0 N/AE]
YZ NDI-UDE N/AD YD ND UD N/AED YD ND UD-N/AD YZ ND UD I Enter the equipment class name from Appendix B: Classes of Equipmem.
CNC-1206.03-00-0203 Rev 1 A Page 103 of 105


Sheet 2 of 3 Status: Y[     Nn U-Seismic Walkdown Checklist (SWC)
Sheet 2 of 3 Status: Y[
Equipment ID No.     1ETXD                   Equip. Class, 4 (Transformers)
Nn U-Seismic Walkdown Checklist (SWC)
Equipment ID No.
1ETXD Equip. Class, 4 (Transformers)
Equipment Description 4160/600 VAC Transformer Interaction Effects
Equipment Description 4160/600 VAC Transformer Interaction Effects
: 7. Are soft targets free from impact, by nearby equipment or structures?       YID NI U-I N/ADl
: 7. Are soft targets free from impact, by nearby equipment or structures?
: 8. Are overhead equipment, distribution systems., ceiling tiles and lighting, YN NDI UD1 N/AD1 and masonry block walls not likely to collapse onto the equipment?
YID NI U-I N/ADl
: 9. Do attached lines have adequate flexibility to avoid damage?               YZ NDI UD N/AD)
: 8. Are overhead equipment, distribution systems., ceiling tiles and lighting, YN NDI UD1 N/AD1 and masonry block walls not likely to collapse onto the equipment?
: 10. Based on the above seismic interaction evaluations, is equipment free       YE NDI UD1 of potentially adverse seismic interaction effects?
: 9. Do attached lines have adequate flexibility to avoid damage?
Other Adverse Conditions
: 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?
: 11. Have you looked for and found no other seismic conditions that could       YER ND- U[I adversely affect the safety functions of the equipment?
YZ NDI UD N/AD)
YE NDI UD1 Other Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could YER ND-U[I adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Comments (Additional pages may be added as necessary)
Noted one cable tray support (rigid) has only X" clearance from large steel box attached to South end of transformer.This is acceptable because both items are rigid and Y1/4" gap will prevent any seismic interaction.
Noted one cable tray support (rigid) has only X" clearance from large steel box attached to South end of transformer. This is acceptable because both items are rigid and Y1/4" gap will prevent any seismic interaction.
Evaluated by: Thomas R Leitch       ,                                            Date: 11/01/2012 Raymond C Fung          .            -                                    i 111' /
Evaluated by: Thomas R Leitch Raymond C Fung Date: 11/01/2012 i 111' /
Zv/
Zv/
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 104 of 105
CNC-1206.03-00-0203 Rev 1 A Page 104 of 105


Sheet 3 of 3 Status: Y[ NE] UP-Seismic Walkdown Checklist (SWC)
Sheet 3 of 3 Status: Y[
Equipment ID No. IETXD               Equip. Class' 4 (Transformers)
NE] UP-Seismic Walkdown Checklist (SWC)
Equipment Description 4160/600 VAC Transformer Phiotogra pbs               ________
Equipment ID No. IETXD Equip. Class' 4 (Transformers)
Note: No photographs.                               Note:
Equipment Description 4160/600 VAC Transformer Phiotogra pbs Note: No photographs.
Note:                                               Note:
Note:
CNC-1206.03-00-0203 Rev 1 Attachment 7A Page 105 of 105
Note:
Note:
CNC-1206.03-00-0203 Rev 1 A Page 105 of 105


                                                                      .10 N~o.:       1,'15769030:3
.10 N~o.:
                              *Aohile A   WO)kica" Ine,             D~oc. No.: 1,157690:03 RA.l-M00001-()
1,'15769030:3
Revision: 0-CA             ThCHJN       AL IMEPORT                   Clienlt: D~ilkc I         ~C 2nwba ata Uniit I N'TTV 2.3.. E]ISMIC' PEE~R REIU~EW StJPPIAEiVEN'ARV M)'TR (XI'AWHA NOCLEAR &#xfd;RTATJI)N UJNIT I Pre-pared lbr:
*Aohile A WO)kica" Ine, D~oc. No.:
Duike F"Dergy Carolinas, LL.C PreparedI by: Stone & Webster, hic. and A RE'S Corp~orahion M~'arch Ill, 2013 QA CATEGORY III 311,112013 ARES Corporation 3/1 4/2013 3/1-112013attc Slone and Wiabsicr. lInc. (A CBMl Company) 3/1,1/2013                                             3/14/2013 Dille         CIMI Approval: Atilliony F, Fazio     Date Duike Vnetrty                                                        PtqiL!V.t Mallager
1,157690:03 RA.l-M00001-()
Revision: 0-CA ThCHJN AL IMEPORT Clienlt:
D~ilkc I  
~C ata 2nwba Uniit I N'TTV 2.3.. E]ISMIC' PEE~R REIU~EW StJPPIAEiVEN'ARV M)'TR (XI'AWHA NOCLEAR &#xfd;RTATJI)N UJNIT I Pre-pared lbr:
Duike F"Dergy Carolinas, LL.C PreparedI by: Stone & Webster, hic. and A RE'S Corp~orahion M~'arch Ill, 2013 QA CATEGORY III ARES Corporation Slone and Wiabsicr. lInc. (A CBMl Company)
Duike Vnetrty 311,112013 3/1-112013attc 3/1 4/2013 3/1,1/2013 3/14/2013 Dille CIMI Approval: Atilliony F, Fazio Date PtqiL!V.t Mallager ml
: 0) 2013 by Stone &- Webster, hic. All rights rewirvcet.
: 0) 2013 by Stone &- Webster, hic. All rights rewirvcet.
Ai  .
A i.
ml CNC-1206.03-00-0203 Rev 1 Attachment BA Page 1 of 15
CNC-1206.03-00-0203 Rev 1 Attachment BA Page 1 of 15


N'l1'1F 2-.3 Si-,ismic 1   [vw~ St.jjpPI.E\u-I\'IETAR\'
N'l1'1F 2-.3 Si-,ismic 1 Ri-i.a
Ri-i.a REPORT, CATAWBIA NUCLEAR STATION UNIT             I Revision Description CNC-1206.03-00-0203 Rev 1 Attachment 8A Page 2 of 15
[vw~ St.jjpPI.E\\u-I\\'IETAR\\'
REPORT, CATAWBIA NUCLEAR STATION UNIT I Revision Description CNC-1206.03-00-0203 Rev 1 A Page 2 of 15


NTTFF2.3 Si-lsmic PiA.iR REV 113WSUPPLEU3MNTAR\'                                                 Report No. 1457690303-R-M-00004, Rev. 0 Rrpoiwr, CATAWBA      NUCl'AR SiTATION UNIT I                                                                                                            March 2013
NTTFF2.3 Si-lsmic PiA.iR REV 113W SUPPLEU3MNTAR\\'
                                                                'Fable of Contents
Rrpoiwr, CATAWBA NUCl'AR SiTATION UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013
'Fable of Contents


==1.0   INTRODUCTION==
==1.0 INTRODUCTION==
...........................................................................................................................                      I 2 .0   SC O PE .............................................................................................................................................         1 3.0   M ETHODOLOGY ..........................................................................................................................                       1 4 .0   P E R S O N N EL. ..................................................................................................................................         2 5.0   SELECTION OF THE SSCs INCLUDED ON THE SWEI ........................                                                                                           2 6.0   SEISM IC WALKDOW NS AND AREA W ALK-BYS ............................................................                                                           3 7.0   LICENSING BASIS REVIEW S ................................................................................................                                     4 8.0   DECISIONS ON ENTERING POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCEISS .....................................................................................................                                   5 9.0   SUBM ITTAL REPORT. .................................................................................... 5
I 2.0 S C O P E.............................................................................................................................................
1 3.0 M ETHODOLOGY..........................................................................................................................
1 4.0 P E R S O N N E L...................................................................................................................................
2 5.0 SELECTION OF THE SSCs INCLUDED ON THE SWEI........................
2 6.0 SEISM IC WALKDOW NS AND AREA W ALK-BYS............................................................
3 7.0 LICENSING BASIS REVIEW S................................................................................................
4 8.0 DECISIONS ON ENTERING POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCEISS.....................................................................................................
5 9.0 SUBM ITTAL REPORT..................................................................................... 5


==10.0 CONCLUSION==
==10.0 CONCLUSION==
S ..............................................................................................................................                     6
S..............................................................................................................................
6


==11.0   REFERENCES==
==11.0 REFERENCES==
................................................................................................................................                  6 Appendices Appendix A: Summary of Peer Review of Final SWCs and AWCs for Inaccessible Items ............ 5 Pages (IlL>                                                                                                                                       Page iii CNC-1206.03-00-0203 Rev 1 Attachment 8A Page 3 of 15
6 Appendices Appendix A: Summary of Peer Review of Final SWCs and AWCs for Inaccessible Items............ 5 Pages (IlL>
Page iii CNC-1206.03-00-0203 Rev 1 A Page 3 of 15


N'1TF 2.3 SrEiSmIC P1EER REVII;W SUI[.LEM INTItY                Report No. 1457690303-R-M-00004, Rev. 0 RI.TIORT, CATAWB'1A NUCLEAR STATION tiNII I'                                                March 2013 Acronyms ARES             ARES Corporation AWC              Area Walk-By Checklist CAP              Corrective Action Program CB&I              CB&I Company CNS              Catawba Nuclear Station Duke Energy      Duke Energy Carolinas, LLC EPRI              Electric Power Research Institute IPEEE            Individual Plant Examination of External Events NRC              U.S. Nuclear Rcgulatory Commission NT''F            Near-Term Task Force Pil              Problem Investigation Process SQUG              Seismic Qualification Utility Group SSC              Structure, System and Component SWC              Seismic Walkdown Checklist SWE              Seismic Walkdown Engineer SWEL              Seismic Walkdown Equipment List Page iv CNC-1 206.03-00-0203 Rev 1 Attachment BA Page 4 of 15
N'1TF 2.3 SrEiSmIC P1EER REVII;W S U I[.LEM INTIt Y RI.TIORT, CATAWB'1A NUCLEAR STATION tiNII I' Report No. 1457690303-R-M-00004, Rev. 0 March 2013 Acronyms ARES AWC CAP CB&I CNS Duke Energy EPRI IPEEE NRC NT''F Pil SQUG SSC SWC SWE SWEL ARES Corporation Area Walk-By Checklist Corrective Action Program CB&I Company Catawba Nuclear Station Duke Energy Carolinas, LLC Electric Power Research Institute Individual Plant Examination of External Events U.S. Nuclear Rcgulatory Commission Near-Term Task Force Problem Investigation Process Seismic Qualification Utility Group Structure, System and Component Seismic Walkdown Checklist Seismic Walkdown Engineer Seismic Walkdown Equipment List Page iv CNC-1 206.03-00-0203 Rev 1 Attachment BA Page 4 of 15


NTTF 2.3 SI~ISMIC PIiR Riw mw Surri .EN4ENIARY                     Report No. I457690303-R-M-00004, Rev. 0 NT'-IF-2.3 Srlis.MIC" h;! RimVm* SUJPPLEME'NTARY                   Report No. 1457690303-R-M-00004, Rev. 0 RF'TORT, CATAWB*A N UCLEAR STATION UNIT I                                                       March 2013
NTTF 2.3 SI~ISMIC PIiR Riw mw Surri.EN4ENIARY Report No. I 457690303-R-M-00004, Rev. 0 NT'-IF-2.3 Srlis.MIC" h;!
RimVm*
SUJPPLEME'NTARY Report No. 1457690303-R-M-00004, Rev. 0 RF'TORT, CATAWB*A N UCLEAR STATION UNIT I March 2013


==1.0     INTRODUCTION==
==1.0 INTRODUCTION==
 
Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidance for Resolution qofFukushima Near-Term Task Force Reconmnendation 2.3: Seismic, was issued in,June 2012. This document provides guidance and procedures to perform seismic walkdowns as required by the U,S. Nuclear Regulatory Commission's (NRC's) 50.54(l) letter regarding Near-Term Task Force (N'T'TF) Recommendation 2.3: Seismic. The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components (SSCs) that represent diversity of component types and ensures inclusion of components from critical systems/functions; conduct of the walkdowns; evaluation of potentially adverse conditions against the plant seismic licensing basis; peer review; Individual Plant Examination of External Events (Ii1EEE) vulnerabilities; and reporting requirements. It was intended that all U.S. nuclear pOWCer plants utilize this guidance document in meeting the requirements of the NRC 50.54(f) letter.
Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidancefor Resolution qofFukushima Near-Term Task Force Reconmnendation 2.3: Seismic, was issued in ,June 2012. This document provides guidance and procedures to perform seismic walkdowns as required by the U,S. Nuclear Regulatory Commission's (NRC's) 50.54(l) letter regarding Near-Term Task Force (N'T'TF) Recommendation 2.3: Seismic. The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components (SSCs) that represent diversity of component types and ensures inclusion of components from critical systems/functions; conduct of the walkdowns; evaluation of potentially adverse conditions against the plant seismic licensing basis; peer review; Individual Plant Examination of External Events (Ii1EEE) vulnerabilities; and reporting requirements. It was intended that all U.S. nuclear pOWCer plants utilize this guidance document in meeting the requirements of the NRC 50.54(f) letter.
D)uke Energy Carolinas, LLC (Duke Energy) contracted with Stone and Webster, Inc., a CB&I Company (CB&I) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). This report documents that peer review. A peer review of the NTTF 2.3 seismic walkdowns of Units I and 2 was conducted in September 2012 and documented in CB&!
D)uke Energy Carolinas, LLC (Duke Energy) contracted with Stone and Webster, Inc., a CB&I Company (CB&I) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). This report documents that peer review. A peer review of the NTTF 2.3 seismic walkdowns of Units I and 2 was conducted in September 2012 and documented in CB&!
/ARES Technical Report 1457690303-R-M-00003, NTTF 2.3 Seismic PeerReview Report, Catawba Nuclear Station Units I and 2. At that time, some items had not been walked down due to being inaccessible during plant operation. Walkdown of the Unit I inaccessible items were deferred to the Unit I l EOC20 refueling outage scheduled for November 2012. This report documents the supplementary peer review performed at Unit I in March 2013. The supplementary peer review covered the walkdown of inaccessible items at Unit I performed by Duke Energy during the Unit I refueling outage.
/ARES Technical Report 1457690303-R-M-00003, NTTF 2.3 Seismic Peer Review Report, Catawba Nuclear Station Units I and 2. At that time, some items had not been walked down due to being inaccessible during plant operation. Walkdown of the Unit I inaccessible items were deferred to the Unit I l EOC20 refueling outage scheduled for November 2012. This report documents the supplementary peer review performed at Unit I in March 2013. The supplementary peer review covered the walkdown of inaccessible items at Unit I performed by Duke Energy during the Unit I refueling outage.
2.0       SCOPE The scope of this supplementary effort was to perform the NTTF 2.3 Seismic Peer Review of the walkdown of the inaccessible items at CNS Unit 1, in accordance with the guidelines in Section 6, Peer Review, of EPRI 1025286. It is intended that the information contained herein will be utilized by Duke Energy as part of its overall NT7F 2.3 final submittal report for Unit I to be delivered to the NRC in March 2013.
2.0 SCOPE The scope of this supplementary effort was to perform the NTTF 2.3 Seismic Peer Review of the walkdown of the inaccessible items at CNS Unit 1, in accordance with the guidelines in Section 6, Peer Review, of EPRI 1025286. It is intended that the information contained herein will be utilized by Duke Energy as part of its overall NT7F 2.3 final submittal report for Unit I to be delivered to the NRC in March 2013.
3.0       METHODOLOGY The CB&i/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the applicable activities. The Peer Review Team for the supplementary peer review consisted of the same individuals that performed the September 2012 peer review.
3.0 METHODOLOGY The CB&i/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the applicable activities. The Peer Review Team for the supplementary peer review consisted of the same individuals that performed the September 2012 peer review.
The peer review process for the Seismic Walkdown Equipment List (SWEL) development and seismic walkdowns was documented in CB&l / ARES Technical Report 1457690303-R-M-00003. Since the OPage                                                                                           1 CNC-1206.03-00-0203 Rev 1 Attachment 8A Page 5 of 15
The peer review process for the Seismic Walkdown Equipment List (SWEL) development and seismic walkdowns was documented in CB&l / ARES Technical Report 1457690303-R-M-00003. Since the OPage 1
CNC-1206.03-00-0203 Rev 1 A Page 5 of 15


N'TI'T 2.3 SiI.sMi(: lcl.PER RRr.vNirW StJiIi,.IMENTARY                 Report No. 1457690303-R-M-00004, Rev. 0 RI.POt, CATAWBA NUCIEAR STATION UNIT I                                                             March 2013 SWEL did not change from the time of the September 2012 peer review, it was not part of the supplementary peer review.
N'TI'T 2.3 SiI.sMi(: lcl.PER RRr.vNirW StJiIi,.IMENTARY Report No. 1457690303-R-M-00004, Rev. 0 RI.POt, CATAWBA NUCIEAR STATION UNIT I March 2013 SWEL did not change from the time of the September 2012 peer review, it was not part of the supplementary peer review.
The peer review process for the scismic walkdowns and walk-bys of the inaccessible items consisted of conducting a final review of the completed documentation. The other, in-process, steps in the review methodology described in CB&I / ARES Technical Report 1457690303-R-M-00003 were not considered necessary since the Duke Energy seismic walkdown engineers (SWEs) were included in the September 2012 peer review of in-process activities.
The peer review process for the scismic walkdowns and walk-bys of the inaccessible items consisted of conducting a final review of the completed documentation. The other, in-process, steps in the review methodology described in CB&I / ARES Technical Report 1457690303-R-M-00003 were not considered necessary since the Duke Energy seismic walkdown engineers (SWEs) were included in the September 2012 peer review of in-process activities.
The peer review process Ibr the licensing basis evaluations and the decisions for entering potentially adverse conditions into the Corrective Action Program (CAP) consisted of reviewing all of the licensing basis reviews resulting f'rom the walkdown of'the inaccessible items. The peer review process fbr the submittal report consisted of reviewing the draft submittal revision prepared by Catawba Design Engineering for licensing review.
The peer review process Ibr the licensing basis evaluations and the decisions for entering potentially adverse conditions into the Corrective Action Program (CAP) consisted of reviewing all of the licensing basis reviews resulting f'rom the walkdown of 'the inaccessible items. The peer review process fbr the submittal report consisted of reviewing the draft submittal revision prepared by Catawba Design Engineering for licensing review.
4.0     PERSONNEL The CNS Peer Review Team fbr the supplemental peer review consisted of the following individuals.
4.0 PERSONNEL The CNS Peer Review Team fbr the supplemental peer review consisted of the following individuals.
As noted above, these are the same individuals who performed the September 2012 peer review.
As noted above, these are the same individuals who performed the September 2012 peer review.
    "    Paid Baughman, P.E., ARES Corporation, Team Leader. Mr. Baughman is a licensed structural engineer with over 40 years of experience in seismic engineering fbr nuclear power stations.
Paid Baughman, P.E., ARES Corporation, Team Leader. Mr. Baughman is a licensed structural engineer with over 40 years of experience in seismic engineering fbr nuclear power stations.
Mr. Baughman is a subject matter expert and trainer for the Seismic Qualification Utility Group (SQUG). Mr. Baughman has performed seismic assessment activities for CNS and is familiar with the CNS seismic licensing basis. Mr. Baughman has performed many seismic margin assessments and seismic probabilistic risk assessments, and is familiar with systems modeling and development of safe shutdown equipment lists.
Mr. Baughman is a subject matter expert and trainer for the Seismic Qualification Utility Group (SQUG). Mr. Baughman has performed seismic assessment activities for CNS and is familiar with the CNS seismic licensing basis. Mr. Baughman has performed many seismic margin assessments and seismic probabilistic risk assessments, and is familiar with systems modeling and development of safe shutdown equipment lists.
    "   George Bushnell, P.E., CB&I Power Group. Mr. Bushnell is a licensed mechanical engineer with over 40 years of experience in engineering qualification of electrical and mechanical equipment for nuclear power stations. Mr. Bushnell is a qualified SQUG Seismic Capability Engineer and company specialist for design and qualification of ASME. III components.
" George Bushnell, P.E., CB&I Power Group. Mr. Bushnell is a licensed mechanical engineer with over 40 years of experience in engineering qualification of electrical and mechanical equipment for nuclear power stations. Mr. Bushnell is a qualified SQUG Seismic Capability Engineer and company specialist for design and qualification of ASME. III components.
    " Robert Keiser, P.E., Duke Energy. Mr. Keiser is a licensed professional engineer in North and South Carolina with over 20 years of experience in the seismic qualification of electrical equipment for Duke Energy's McGuire, Catawba, and Oconee Nuclear Stations. Mr. Keiser received training as a SQUG Seismic Capability Engineer and was involved with the SQUG effort at Oconee and the IPEEE efforts at all three stations.
" Robert Keiser, P.E., Duke Energy. Mr. Keiser is a licensed professional engineer in North and South Carolina with over 20 years of experience in the seismic qualification of electrical equipment for Duke Energy's McGuire, Catawba, and Oconee Nuclear Stations. Mr. Keiser received training as a SQUG Seismic Capability Engineer and was involved with the SQUG effort at Oconee and the IPEEE efforts at all three stations.
5.0     SELECTION OF THE SSCs INCLUDED ON THE SWEL Peer review of the SWEL is described in CB&I /ARES Technical Report 1457690303-R-M-00003.
5.0 SELECTION OF THE SSCs INCLUDED ON THE SWEL Peer review of the SWEL is described in CB&I /ARES Technical Report 1457690303-R-M-00003.
Since the SWEL did not change from September 2012 no further peer review was required.
Since the SWEL did not change from September 2012 no further peer review was required.
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NTTP 2.SPPLM~i~hR SESMI PHR R~vl~w             ReortNo.I 4569003--M-000, Rv.I N"VIF 2.3 Si::ASMKi: liu.'1 RE.VllE.W SUPPL'EME"NTAR*Y               Report No. 1457690303-R-M-00004, Rev. 0 REPORT, CATAWBA NUJCL.EAIR STATION UNIT I                                                         March 2013 6.0     SEISMIC WALKI)OWNS AND AREA WALK-BYS The inaccessible equipment items and areas to be walked down were listed in Appendix C of CB&I /
NTTP 2. SESMI PHR R~vl~w SPPLM~i~hR ReortNo.I 4569003--M-000, Rv.I N"VIF 2.3 Si::ASMKi: liu.'1 RE.VllE.W SUPPL'EME"NTAR*Y Report No. 1457690303-R-M-00004, Rev. 0 REPORT, CATAWBA NUJCL.EAIR STATION UNIT I March 2013 6.0 SEISMIC WALKI)OWNS AND AREA WALK-BYS The inaccessible equipment items and areas to be walked down were listed in Appendix C of CB&I /
ARES Technical Report 1457690303-R-M-00001. The walkdowns consist of two parts: equipment-specific seismic walkdowns and area walk-bys. The specific instructions for each part are delineated in EPRI 1025286. The walkdowns were performed by Duke Energy.
ARES Technical Report 1457690303-R-M-00001. The walkdowns consist of two parts: equipment-specific seismic walkdowns and area walk-bys. The specific instructions for each part are delineated in EPRI 1025286. The walkdowns were performed by Duke Energy.
Seismic walkdowns of specific items focused on identifying adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions that coulId challenge the seismic adequacy ofa SWEI item.
Seismic walkdowns of specific items focused on identifying adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions that coulId challenge the seismic adequacy ofa SWEI item.
Line 1,633: Line 2,418:
Area walk-bys consisted of examining the general area surrounding the specific SWEL items for potentially adverse seismic conditions. The area examined included either the entire room enclosing the SWEL item or at least 35 feet in any direction. The examination looked for degraded anchorage conditions of equipment in the area; significantly degraded equipment; poorly supported cable/conduit raceways, IHVAC ducting, or piping; and unsecured temporary equipment that could cause seismic interactions (seismic housekeeping concerns). The area walk-by included looking for potential seismic interactions from flooding, spray, or fire. These potential seismic interactions are described in Section 4 of EPRI 1025286.
Area walk-bys consisted of examining the general area surrounding the specific SWEL items for potentially adverse seismic conditions. The area examined included either the entire room enclosing the SWEL item or at least 35 feet in any direction. The examination looked for degraded anchorage conditions of equipment in the area; significantly degraded equipment; poorly supported cable/conduit raceways, IHVAC ducting, or piping; and unsecured temporary equipment that could cause seismic interactions (seismic housekeeping concerns). The area walk-by included looking for potential seismic interactions from flooding, spray, or fire. These potential seismic interactions are described in Section 4 of EPRI 1025286.
The Peer Review Team reviewed the qualifications of the Duke Energy engineers performing the walkdowns and verified that they meet the requirements for a SWE in EPRI 1025286. The Peer Review Team also conducted interviews with the engineers to confirm that they had a good understanding of the guidance in EPRI 1025286.
The Peer Review Team reviewed the qualifications of the Duke Energy engineers performing the walkdowns and verified that they meet the requirements for a SWE in EPRI 1025286. The Peer Review Team also conducted interviews with the engineers to confirm that they had a good understanding of the guidance in EPRI 1025286.
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NT`'/F 2.3 Si.isM . Pi.BR R1:Nvr-w SUPPILEiMENTARY               Report No. 1457690303-R-M-00004, Rev. 0 REY'OR r, CATAWBA N UCI..IAR STATION UN IT]                                                   March 2013 The individuals interviewed were:
NT`'/F 2.3 Si.isM. Pi.BR R1:Nvr-w SUPPILEiMENTARY Report No. 1457690303-R-M-00004, Rev. 0 REY'OR r, CATAWBA N UCI..IAR STATION UN IT ]
    "   T. R. .Leitch- Duke Energy, Senior Walkdown Team Member
March 2013 The individuals interviewed were:
    " R. C. Fung- Duke Energy, Walkdown 'learn Member
" T. R..Leitch - Duke Energy, Senior Walkdown Team Member
    " J.D. Kennedy- Duke Enei'gy, Walkdown ''eam Member Interviews of walkdown personnel were jointly performed by the Duke Energy, ARES, and CB&I members of the Peer Review Teamr. Personnel were interviewed to assess their working synergy as well as individual capabilities/knowledge. All were verified to have attended the EPRI NTTF 2.3 Seismic Walkdown Training Course. Discussion provided positive indication that the walkdown personnel had adequate experience and training to perform walkdown and walk-by activities in compliance with the EP'RI Seismic Walkdown Guidance. They displayed knowledge of the primary objectives of the walkdowns, appropriate levels of dialog between themselves to reach common agreement without excessive discussion, and adequate objectivity in identification of significant discrepancies between as-designed and as-found conditions. Team member qualifications are included in the Duke Energy walkdown report.
" R. C. Fung-Duke Energy, Walkdown 'learn Member
" J.D. Kennedy-Duke Enei'gy, Walkdown ''eam Member Interviews of walkdown personnel were jointly performed by the Duke Energy, ARES, and CB&I members of the Peer Review Teamr. Personnel were interviewed to assess their working synergy as well as individual capabilities/knowledge. All were verified to have attended the EPRI NTTF 2.3 Seismic Walkdown Training Course. Discussion provided positive indication that the walkdown personnel had adequate experience and training to perform walkdown and walk-by activities in compliance with the EP'RI Seismic Walkdown Guidance. They displayed knowledge of the primary objectives of the walkdowns, appropriate levels of dialog between themselves to reach common agreement without excessive discussion, and adequate objectivity in identification of significant discrepancies between as-designed and as-found conditions. Team member qualifications are included in the Duke Energy walkdown report.
The September 2012 peer review included review of in-process Area Walkdown Checklists (AWCs) and Seismic Walkdown Checklists (SWCs). Group meetings were held with the SWEs to address the peer review comments. The Duke Energy personnel who perlorned walkdowns of the inaccessible items attended these meetings.
The September 2012 peer review included review of in-process Area Walkdown Checklists (AWCs) and Seismic Walkdown Checklists (SWCs). Group meetings were held with the SWEs to address the peer review comments. The Duke Energy personnel who perlorned walkdowns of the inaccessible items attended these meetings.
The Peer Review Team reviewed 100% of the final SWCs and AWCs for the inaccessible items. This is more than the 10% sample that the EPRI guidance requires. The review is summarized in Appendix A of this report. The table in Appendix A lists the 16 SWCs and I I AWCs reviewed.
The Peer Review Team reviewed 100% of the final SWCs and AWCs for the inaccessible items. This is more than the 10% sample that the EPRI guidance requires. The review is summarized in Appendix A of this report. The table in Appendix A lists the 16 SWCs and I I AWCs reviewed.
The Peer Review Team concluded that the walkdowns were conducted in accordance with the EPRI guidance.
The Peer Review Team concluded that the walkdowns were conducted in accordance with the EPRI guidance.
The Peer Review Team has reviewed the Duke Energy walkdown report (Duke Energy Calculation CNC-i 206.03-00-0203, Futkushima Near-Term Task Force (7VTTb) Recommendation 2.3: NRC Submittal Reportfor Seismic Walk-downs, Attachment 7A, "Duke Portion of Walkdown.") The report describes the walkdown and summarizes the results. The report contains all of the information required by the EPRI guidance.
The Peer Review Team has reviewed the Duke Energy walkdown report (Duke Energy Calculation CNC-i 206.03-00-0203, Futkushima Near-Term Task Force (7VTTb) Recommendation 2.3: NRC Submittal Report for Seismic Walk-downs, Attachment 7A, "Duke Portion of Walkdown.") The report describes the walkdown and summarizes the results. The report contains all of the information required by the EPRI guidance.
7.0     LICENSING BASIS REVIEWS All potentially adverse conditions require a licensing basis review in accordance with the EPRI guidance. For CNS, the licensing basis reviews were performed by Duke Energy Design Engineering personnel. Mr. Thomas Leitch performed most of the licensing basis reviews. He was assisted by Messrs. Raymond Fung, Robert Pryce, and David Kennedy. These individuals meet the personnel requirements in EPRI 1025286.
7.0 LICENSING BASIS REVIEWS All potentially adverse conditions require a licensing basis review in accordance with the EPRI guidance. For CNS, the licensing basis reviews were performed by Duke Energy Design Engineering personnel. Mr. Thomas Leitch performed most of the licensing basis reviews. He was assisted by Messrs. Raymond Fung, Robert Pryce, and David Kennedy. These individuals meet the personnel requirements in EPRI 1025286.
The walkdown of the inaccessible items identified four potentially adverse seismic conditions. As with the accessible items, each potentially adverse condition identified by the walkdown team was entered Page 4 CNC-1206.03-00-0203 Rev 1 Attachment 8A Page 8 of 15
The walkdown of the inaccessible items identified four potentially adverse seismic conditions. As with the accessible items, each potentially adverse condition identified by the walkdown team was entered Page 4 CNC-1206.03-00-0203 Rev 1 A Page 8 of 15


NTF 2.3 SISMIc P-:ER REvII:Mw SUPII..EIMENTARY                   Report No. 1457690303-R-M-00004, Rev. 0 REPORT. CATAWBA NuCl-AR STATlON tJNrT I                                                       March 2013 into the CAP via the Problem Investigation Process (PIP) to enable tracking to closure. All of the items were entered into a single PIP, but they are listed separately. The Duke Energy Licensing Basis Reviewer stated that the licensing basis reviews were documented in the PIP associated with the potentially adverse conditions and no conditions were ibund to violate the CNS seismic licensing basis.
NTF 2.3 SISMIc P-:ER REvII:Mw SUPII..EIMENTARY Report No. 1457690303-R-M-00004, Rev. 0 REPORT. CATAWBA NuCl-AR STATlON tJNrT I March 2013 into the CAP via the Problem Investigation Process (PIP) to enable tracking to closure. All of the items were entered into a single PIP, but they are listed separately. The Duke Energy Licensing Basis Reviewer stated that the licensing basis reviews were documented in the PIP associated with the potentially adverse conditions and no conditions were ibund to violate the CNS seismic licensing basis.
The potentially adverse seismic conditions identified by the wvalkdown of the inaccessible items are listed in Appendix B ofthe Duke Energy walkdown report. The peer reviewers verified that all of the potentially adverse seismic conditions listed in Appendix B of the walkdown report had licensing basis reviews documented in the referenced lI'll. The Peer Review Team reviewed the licensing basis evaluations fbr all of the potentially adverse seismic conditions and concluded that they were conducted in accordance with the EPRI guidance The peer reviewers also reviewed the licensing basis reviews for the items with comments provided to l)uke Energy during the September peer review. The Peer Review Team concluded that the comments were acceptably resolved.
The potentially adverse seismic conditions identified by the wvalkdown of the inaccessible items are listed in Appendix B ofthe Duke Energy walkdown report. The peer reviewers verified that all of the potentially adverse seismic conditions listed in Appendix B of the walkdown report had licensing basis reviews documented in the referenced lI'll. The Peer Review Team reviewed the licensing basis evaluations fbr all of the potentially adverse seismic conditions and concluded that they were conducted in accordance with the EPRI guidance The peer reviewers also reviewed the licensing basis reviews for the items with comments provided to l)uke Energy during the September peer review. The Peer Review Team concluded that the comments were acceptably resolved.
8.0       DECISIONS ON ENTERING POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCESS All of the potentially adverse seismic conditions identified by the seismic walkdown of the inaccessible items were entered in the CAP for further evaluation. The Peer Review Team review of the seismic walkdowns determined that the identifications of potentially adverse seismic conditions were conservatively made. Thus, the decision to enter all of them into the CAP was likewise conservative.
8.0 DECISIONS ON ENTERING POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCESS All of the potentially adverse seismic conditions identified by the seismic walkdown of the inaccessible items were entered in the CAP for further evaluation. The Peer Review Team review of the seismic walkdowns determined that the identifications of potentially adverse seismic conditions were conservatively made. Thus, the decision to enter all of them into the CAP was likewise conservative.
The licensing basis reviews determined none of the potentially adverse seismic conditions violated the CNS licensing basis. Therefore, it was not necessary to perform any extent of condition evaluations.
The licensing basis reviews determined none of the potentially adverse seismic conditions violated the CNS licensing basis. Therefore, it was not necessary to perform any extent of condition evaluations.
The licensing basis evaluations of the potentially adverse seismic conditions identified enhancements, which were determined to improve the seismic condition of the plant. Work orders were assigned for implementation of the enhancements.
The licensing basis evaluations of the potentially adverse seismic conditions identified enhancements, which were determined to improve the seismic condition of the plant. Work orders were assigned for implementation of the enhancements.
The Peer Review Team concludes that the decisions on entering potentially adverse conditions in the CAP process were in accordance with the EPRI guidance.
The Peer Review Team concludes that the decisions on entering potentially adverse conditions in the CAP process were in accordance with the EPRI guidance.
9.0     SUBMITTAL REPORT The Peer Review Team reviewed a draft of the revised submittal report for CNS Unit I provided by Mr. Thomas Leitch on March 12, 2013. The report contained the required sections and discussions.
9.0 SUBMITTAL REPORT The Peer Review Team reviewed a draft of the revised submittal report for CNS Unit I provided by Mr. Thomas Leitch on March 12, 2013. The report contained the required sections and discussions.
Comments on the submittal were provided to Mr. Leitch on March 13, 2013.
Comments on the submittal were provided to Mr. Leitch on March 13, 2013.
The Peer Review Team concludes that the submittal report is in accordance with the EPRI guidance.
The Peer Review Team concludes that the submittal report is in accordance with the EPRI guidance.
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N'PFF 2.3 Si-lsmic PiiizR Rvv.;vu       ~
N'PFF 2.3 Si-lsmic PiiizR Rvv.;vu  
S.i'.IN1NI'ARY               Report No. 1457690303-R-M-00004, Rev. 0 RFIrOiRT, CATAWBIA NUCLFAR STATION UNIT I                                                    March 2013
~
S.i'.IN1NI'ARY RFIrOiRT, CATAWBIA NUCLFAR STATION UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013


==10.0     CONCLUSION==
==10.0 CONCLUSION==
S The conclusion of the peer review is that the CNS NTTF 2.3 scismic walkdown for the inaccessible items has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the September 2012 peer review have been addressed satisfactorily.
S The conclusion of the peer review is that the CNS NTTF 2.3 scismic walkdown for the inaccessible items has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the September 2012 peer review have been addressed satisfactorily.


==11.0   REFERENCES==
==11.0 REFERENCES==
 
CB&I / ARES Technical Report 1457690303-R-M-00001, Seismic Wealkdowin Repoitijbr Duke Energy's Catawba Nuclear Station Unit I. Revision 2, November 14, 2012.
CB&I / ARES Technical Report 1457690303-R-M-00001, Seismic Wealkdowin Repoitijbr Duke Energy's Catawba NuclearStation Unit I. Revision 2, November 14, 2012.
CB&J / ARES Technical Report 1457690303-R-M-00003, N77"F 2.3 Sei'inic Peer Review Report, Catawba Nuclear Station Units I and 2, Revision 0, November 18, 2012.
CB&J / ARES Technical Report 1457690303-R-M-00003, N77"F 2.3 Sei'inic Peer Review Report, Catawba Nuclear Station Units I and 2, Revision 0, November 18, 2012.
Duke Energy Calculation CNC- 1206.03-00-0203, Fukutshima Near-T1erm Task Force (N7TF)
Duke Energy Calculation CNC-1206.03-00-0203, Fukutshima Near-T1erm Task Force (N7TF)
Recommendation 2.3: NRC Sitbmittal Reporl fior Seismic Walk-downs, Revision I, DRAFT, March 2013.
Recommendation 2.3: NRC Sitbmittal Reporl fior Seismic Walk-downs, Revision I, DRAFT, March 2013.
EPRI 1025286, Seismic Wclkdown Guidance/for Resolution of Fukushima Near-Term Task Force Recommendation 2.3. Seismic, June 2012, Electric Power Research Institute, Palo Alto, CA.
EPRI 1025286, Seismic Wclkdown Guidance/for Resolution of Fukushima Near-Term Task Force Recommendation 2.3. Seismic, June 2012, Electric Power Research Institute, Palo Alto, CA.
Letter, E. Leeds and M. Johnson (NRC) to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Tern Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3: Seismic," dated March 12, 2012.
Letter, E. Leeds and M. Johnson (NRC) to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Tern Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3: Seismic," dated March 12, 2012.
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I Nil-E 2.3 Sf:'ISMlC P1iluI', RE-VIEW SuPi+/-LiiNENARY               Report No. 1457690303-R-M-00004, Rev. 0 RiFio'oR CATAWBIA NUCLEAR STATION UN IT I                                                      March 2013 APPENDIX A
I Nil-E 2.3 Sf:'ISMlC P1iluI', RE-VIEW SuPi+/-LiiNENARY RiFio'oR CATAWBIA NUCLEAR STATION UN IT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013 APPENDIX A


==SUMMARY==
==SUMMARY==
OF PEER REVIEW OF FINAL SWCs AND AWCs FOR INACCESSIBLE ITEMS Page A- I CNC-1206.03-00-0203 Rev i Attachment BA Page 11 of 15
OF PEER REVIEW OF FINAL SWCs AND AWCs FOR INACCESSIBLE ITEMS Page A-I CNC-1206.03-00-0203 Rev i Attachment BA Page 11 of 15


NTTF 2.3 SEISMIC PEER REVIEW SUPPLEMENTARY REPORT                                                               Report No. 1457690303-R-M-00004, Rev. 0 CATAWBA NUCLEAR STATION       UNIT 1                                                                                                                 March 2013 Walkdown Team Members:
NTTF 2.3 SEISMIC PEER REVIEW SUPPLEMENTARY REPORT Report No. 1457690303-R-M-00004, Rev. 0 CATAWBA NUCLEAR STATION UNIT 1 March 2013 Walkdown Team Members:
T. R. Leitch, Duke Energy       R. C. Fung, Duke Energy               J. D. Kennedy, Duke Energy Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID       Equipment     50%     Non 50%     Line       Overall       Team                                       Comments Class   Anchorage Anchorage   Mounted       Status CVI El 557                                                                                   Area Walkdown (De- 58 Rad 40):
T. R. Leitch, Duke Energy R. C. Fung, Duke Energy J. D. Kennedy, Duke Energy Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID Equipment 50%
Reactor Bldg                                                                   Leitch/           I. WD centered around AOV INV52A Y           Funo             2. No adverse conditions noted
Non 50%
: n. Apparently abandoned scgmcnt o01eCectray noted
Line Overall Team Comments Class Anchorage Anchorage Mounted Status CVI El 557 Area Walkdown (De-58 Rad 40):
: 4. Photos included INV52A                                                                         Leitch/     No adverse condition noted 7                     -                                  L itc         Minor interaction with air line: deemed insignificant Fung       Photos provided CVI El 560                                                                                   Area Walkdown (Deg 46 Rad 47)
Reactor Bldg Leitch/
Reactor Bldg                                                                                       I. WD centered aroundlNI54A
I.
                                                                      -          Leitch/           2. No adverse condition noted Fung             3. Loose locknut noted: Work Request generated (PIP                                                                                                           10589)
WD centered around AOV INV52A Y
: 4. Photos included INI0054A                                                                       Leitcht       No adverse condition noted 8                               X             Y         Lcth         Documents referenced Fung__ _ _ _ _Photos provided CVI El 562                                                                                   Area Walkdown (Deg 40 Rad 55)
Funo
Reactor Bldg                                                                   Leitch/           I. WD centered around IN1438A Y           Fung             2. No seismically adverse condition noted
: 2.
: 3. Housekeeping: boron deposits noted on adjacent tubing:
No adverse conditions noted
work request initiated INI438A                                                                         i             No adverse condition noted 8         -          -                                    Fling       Documents referenced FIng       Photos provided Page A-2 CNC-1206.03-00-0203 Rev 1 Attachment SA Page 12 of 15
: n.
Apparently abandoned scgmcnt o01eCectray noted
: 4.
Photos included INV52A Leitch/
No adverse condition noted 7
L itc Minor interaction with air line: deemed insignificant Fung Photos provided CVI El 560 Area Walkdown (Deg 46 Rad 47)
Reactor Bldg I.
WD centered aroundlNI54A Leitch/
: 2.
No adverse condition noted Fung
: 3.
Loose locknut noted: Work Request generated (PIP 10589)
: 4.
Photos included INI0054A Leitcht No adverse condition noted 8
X Y
Lcth Documents referenced Fung__ _ _ _ _Photos provided CVI El 562 Area Walkdown (Deg 40 Rad 55)
Reactor Bldg Leitch/
I.
WD centered around IN1438A Y
Fung
: 2.
No seismically adverse condition noted
: 3.
Housekeeping: boron deposits noted on adjacent tubing:
work request initiated INI438A i
No adverse condition noted 8
Fling Documents referenced FIng Photos provided Page A-2 CNC-1206.03-00-0203 Rev 1 Attachment SA Page 12 of 15


NTTF 2.3 SEISMIC PEER REVIEW SUPPLEMENTIPARY REPORT                                                               Report No. ]457690303-R-M-00004, Rev. 0 CATAWBA NUCLEAR STATION UNIT I                                                                                                                            March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID     Equipment     50%       Non 50%       Line         Overall       Team                                           Comments Class     Anchorage   Anchorage     Mounted       Status CVI El 567                                                                                   Area Walkdown (Deg 176 Rad 50)
NTTF 2.3 SEISMIC PEER REVIEW SUPPLEMENTIPARY REPORT CATAWBA NUCLEAR STATION UNIT I Report No. ]457690303-R-M-00004, Rev. 0 March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID Equipment 50%
Reactor Bldg                                                                                       I. WD centered around pump IND2A tLeitch/             2. Unattached cable runs noted in area; work request Kennedy                   initiated
Non 50%
: 3. No seismically adverse conditions noted
Line Overall Team Comments Class Anchorage Anchorage Mounted Status CVI El 567 Area Walkdown (Deg 176 Rad 50)
: 4. Photo provided IND2A                                                                         Leitch/       No seismically adverse condition noted 8                                   X             Y       Kennedy       Safetly related cable fasteners and supports in degraded condition
Reactor Bldg I.
                                                                                          "_noted; work request initiated (work order 02070468)
WD centered around pump IND2A tLeitch/
CV) El 568                                                                                   Area Walkdown (Deg 176 Rad 25)
: 2.
Reactor Bldg                                                                                       1. WD centered around pump IND IB Leitch/             2. No seismically adverse conditions noted Fung               3. Temporary shielding judged adequately supported; tubing as-found condition judged insignificant
Unattached cable runs noted in area; work request Kennedy initiated
_4. .      Photos provided INDIB                                                                         Leitch/       No adverse condition noted 8                                   X             Y           litg       Documents referenccd Fung       Photos provided CVI El 635                                                                                   Area Walkdown (DegI05 Rad 37)
: 3.
Reactor Bldg                                                                   Leitch/               I. WD centered around 3 inline components
No seismically adverse conditions noted
                                                                                  -                  2. No seismically adverse conditions noted 3ung
: 4.
                                                                                                        . Photos provided to illustrate congested but adequate clearance   conditions INC34A                                                                         Leitch/     No adverse condition noted 7                       -          X                       Leth         Documents referenced Fung_   _Comment         provided wrt maintenance schedtle lbr component INC32B           7                                                           l.,eitch/
Photo provided IND2A Leitch/
Funn        No Photosadverse  condition noted provided INC36B                                                                                     No adverse condition noted Leitch/
No seismically adverse condition noted 8
Fung        Comment       provided Photos provided         wrt maintenance to illustrate         schedule congested       for component but adequate clearance I_                           conditions
X Y
                                                  .4.                                                                                                         Page A-3 CNC-1206.03-00-0203 Rev 1 Attachment BA Page 13 of 15
Kennedy Safetly related cable fasteners and supports in degraded condition
"_noted; work request initiated (work order 02070468)
CV) El 568 Area Walkdown (Deg 176 Rad 25)
Reactor Bldg
: 1.
WD centered around pump I ND I B Leitch/
: 2.
No seismically adverse conditions noted Fung
: 3. Temporary shielding judged adequately supported; tubing as-found condition judged insignificant
_4.
Photos provided INDIB Leitch/
No adverse condition noted 8
X Y
litg Documents referenccd Fung Photos provided CVI El 635 Area Walkdown (DegI05 Rad 37)
Reactor Bldg Leitch/
I.
WD centered around 3 inline components
: 2.
No seismically adverse conditions noted 3ung Photos provided to illustrate congested but adequate clearance conditions INC34A Leitch/
No adverse condition noted 7
X Leth Documents referenced Fung_ _Comment provided wrt maintenance schedtle lbr component INC32B 7
l.,eitch/
No adverse condition noted Funn Photos provided INC36B No adverse condition noted Leitch/
Comment provided wrt maintenance schedule for component Fung Photos provided to illustrate congested but adequate clearance I_
conditions
.4.
Page A-3 CNC-1206.03-00-0203 Rev 1 Attachment BA Page 13 of 15


NTTF 2.3 SEIS.MIC PEER REVIEW SUPPLEMENTARY REPORT                                                         Report No. 1457690303-R-M-00004, Rev. 0 CATAB\VIA NUCLEAR STATION UNIT I                                                                                                                    March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID     Equipment Cas j Ancho50%     Non 50%
NTTF 2.3 SEIS.MIC PEER REVIEW SUPPLEMENTARY REPORT CATAB\\VIA NUCLEAR STATION UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID Equipment j 50%
Anchorage Line Mounted Overall Status Team                                   Comments CV I I.156,s                                                                               Area Walkdown (Deg 244 Rad 47)
Non 50%
Rczictor 1ldg 1                                                                     Leitch/         I. WD centered around drain I                                       Kennedy         2. No seismically adverse conditions noted
Line Overall Team Comments Cas Ancho Anchorage Mounted Status CV I I.156,s Area Walkdown (Deg 244 Rad 47)
Rczictor 1ldg 1
Leitch/
I.
WD centered around drain I
Kennedy
: 2.
No seismically adverse conditions noted
: 3. Comments/photos included describingfjustif&#xfd;ing minor
: 3. Comments/photos included describingfjustif&#xfd;ing minor
_ _conditions IF\V8                   I                                                     Leitch     SWEL 2 component 00                       x                       Y         KNo             seismically adverse condition noted Kennedy     Documents referenced; photo provided CV I El 563                                                                               Area Walkdown (Deg 300 Rad 33)
_ _conditions IF\\V8 I
Reactor Bldo                                                         y-Leitch/                 1. WD centered around drain Fung           2. No seismically adverse conditions noted
Leitch SWEL 2 component 00 x
: 3. Comments describing/justifying minor conditions I1-FW46                                                                         Leitch/   SWEL 2 component 00                                 X             Y           Fung      No seismically adverse condition noted
Y KNo seismically adverse condition noted Kennedy Documents referenced; photo provided CV I El 563 Area Walkdown (Deg 300 Rad 33)
__ _    _Documents   referenced; photo provided RXI E1557                                                                                  Area Walkdown (Deg 280 Rad 58-63)
Reactor Bldo y-Leitch/
R13 Annulus                                                                                     I. WD centered on 3 SWEL 2 components y         Leitch/         2. No seismically adverse conditions noted Fung           3. Comments/photos included describing/justifying minor conditions, apparent good practice issue re: clearances INVI'D0042                                                                               SWEL 2 component 00                                                           Leitch/   No seismically adverse condition noted 0         -        X                       Y           Fun       Documents referenced; photos provided Fung     Comments justify adequacy of close clearance/potential interaction condition NV865Leitch                                                                             SWEL 2 component No seismically adverse condition noted Fung     Documents referenced; photos provided
: 1.
  &#xfd; NV
WD centered around drain Fung
    ' FI SUS5                                                                               Anchorage verified 5Leitch/   SWEL 2 component; anchorage verified x                                 Y           Fung     No seismically adverse condition noted Documents referenced; photos provided
: 2.
__            _      _  _Background                                                                   comments provided Page A-4 CNC-1 206.03-00-0203 Rev 1 Attachment 8A Page 14 of 15
No seismically adverse conditions noted
: 3.
Comments describing/justifying minor conditions I1-FW46 Leitch/
SWEL 2 component 00 X
Y No seismically adverse condition noted Fung
_Documents referenced; photo provided RXI E1 557 Area Walkdown (Deg 280 Rad 58-63)
R13 Annulus I.
WD centered on 3 SWEL 2 components y
Leitch/
: 2.
No seismically adverse conditions noted Fung
: 3. Comments/photos included describing/justifying minor conditions, apparent good practice issue re: clearances INVI'D0042 SWEL 2 component 00 Leitch/
No seismically adverse condition noted 0
X Y
Fun Documents referenced; photos provided Fung Comments justify adequacy of close clearance/potential interaction condition NV865Leitch SWEL 2 component No seismically adverse condition noted Fung Documents referenced; photos provided
&#xfd; '
FI NV SUS5 Anchorage verified 5Leitch/
SWEL 2 component; anchorage verified x
Y Fung No seismically adverse condition noted Documents referenced; photos provided
_Background comments provided Page A-4 CNC-1 206.03-00-0203 Rev 1 A Page 14 of 15


NTTF 2.3 SEISMIC PEER REVwIW SUPPL.EMENTARY REPORT                                                             Report No. 1457690303-R-M-00004, Rev. 0 CATAWIBA NUCLEAR STA'rlON UNIT I                                                                                                                    March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items Equipment     r     50%     Non 50%     Line       Overall IDClass      _______
NTTF 2.3 SEISMIC PEER REVwIW SUPPL.EMENTARY REPORT CATAWIBA NUCLEAR STA'rlON UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items Equipment r 50%
Anchorage Anchorage       I Mounted     Status       Team____                            Comments l31dg El                                                     IArea                           Walkdown (CC-55) 594                                                                                             I. WD centered on SSPS Train A cabinets Control Roon         -                                                    Y         Fung       2. Required removal of some ceiling panels; opening of cabinets to complete
Non 50%
: 3. No seismically adverse conditions noted "SSA         I         ....                                                                Anchorage verified 1                                                               Leitch/ No seismically adverse conditions noted 18                 X                                             Fung   Documents referenced; photos provided Background discussion included in form of comments AuN ido E1                                                                                   Area Walkdown (Room 372 AA-51) 560                                                                                             1. WD centered on 2 transformers Leitch/     2. No seismically adverse condition noted Fung       3. Documents referenced; photos provided
Line Overall ID I
: 4. Discussion provided on resolution of apparent close clearance conditions I E"Xt                       ILech                                                         Anchorage verified Leitch/ No seismically adverse conditions noted Fung   Documents referenced; photos provided Background discussion included in form of comments I ETXD                                                                                     Anchorage verified i
Team____
4      I        Xy                                           Leitch/
Comments Class Anchorage Anchorage Mounted Status l 31dg El IArea Walkdown (CC-55) 594 I.
Fung No seismically adverse conditions noted Background discussion included in form of comments to resolve I_                                     apparent close clearance condition op4#~                                                                                                                                     Page A-5 CNC-1206.03-00-0203 Rev 1 Attachment 8A Page 15 of 15
WD centered on SSPS Train A cabinets Control Roon Y
Fung
: 2.
Required removal of some ceiling panels; opening of cabinets to complete
: 3.
No seismically adverse conditions noted "SSA I
Anchorage verified 1
Leitch/
No seismically adverse conditions noted 18 X
Fung Documents referenced; photos provided Background discussion included in form of comments AuN ido E1 Area Walkdown (Room 372 AA-51) 560 1.
WD centered on 2 transformers Leitch/
: 2.
No seismically adverse condition noted Fung
: 3.
Documents referenced; photos provided
: 4.
Discussion provided on resolution of apparent close clearance conditions I E"Xt ILech Anchorage verified Leitch/
No seismically adverse conditions noted Fung Documents referenced; photos provided Background discussion included in form of comments I ETXD Anchorage verified i
Xy Leitch/
No seismically adverse conditions noted 4
I Fung Background discussion included in form of comments to resolve I_
apparent close clearance condition op4#~
Page A-5 CNC-1206.03-00-0203 Rev 1 A Page 15 of 15


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 1 of 15 Executive Summary The results of the Catawba Unit 1 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns are provided herein. The walkdowns were performed in accordance with Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, as issued in June 2012. Catawba committed to utilize this guidance for the conduct of the seismic walkdowns via docketed correspondence dated 7/9M12. The EPRI walkdown guidance provided guidance and procedures to perform seismic walkdowns as required by the U.S. Nuclear Regulatory Commission (NRC) 50.54(f) letter regarding NTTF Recommendation 2.3: Seismic. The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components that represent diversity of component types and assures inclusion of components from critical systems / functions; conduct of the walkdowns, evaluation of potentially adverse conditions against the plant seismic licensing basis; and reporting requirements. It also includes checklists to be used by the Seismic Walkdown Engineers (SWEs) in the performance of the seismic walkdowns and walk-bys.
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 1 of 15 Executive Summary The results of the Catawba Unit 1 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns are provided herein. The walkdowns were performed in accordance with Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, as issued in June 2012. Catawba committed to utilize this guidance for the conduct of the seismic walkdowns via docketed correspondence dated 7/9M12.
The EPRI walkdown guidance provided guidance and procedures to perform seismic walkdowns as required by the U.S. Nuclear Regulatory Commission (NRC) 50.54(f) letter regarding NTTF Recommendation 2.3: Seismic.
The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components that represent diversity of component types and assures inclusion of components from critical systems / functions; conduct of the walkdowns, evaluation of potentially adverse conditions against the plant seismic licensing basis; and reporting requirements. It also includes checklists to be used by the Seismic Walkdown Engineers (SWEs) in the performance of the seismic walkdowns and walk-bys.
Revision 0 of the submittal report documented the results of the walkdown of accessible items in September 2012. Revision 1 of the submittal report adds the results of the walkdown of inaccessible items performed in November 2012.
Revision 0 of the submittal report documented the results of the walkdown of accessible items in September 2012. Revision 1 of the submittal report adds the results of the walkdown of inaccessible items performed in November 2012.
The results of the walkdowns and licensing basis evaluations verified the adequacy of the Catawba monitoring and maintenance procedures with regard to the seismic licensing basis.
The results of the walkdowns and licensing basis evaluations verified the adequacy of the Catawba monitoring and maintenance procedures with regard to the seismic licensing basis.
Line 1,738: Line 2,626:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 2 of 15 Structure, System and Component (SSC) Seismic Design:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 2 of 15 Structure, System and Component (SSC) Seismic Design:
All structures, systems and components required to shut down and maintain the reactor in a safe and orderly condition or prevent the uncontrolled release of excessive amounts of radioactivity have a seismic classification of Category I. The Catawba design complies with Regulatory Guide 1.29 for SSC seismic design requirements, with the exception of SSCs provided in the Westinghouse scope. The seismic design for the Westinghouse supplied SSC satisfied the classification of safety related systems and components as outlined by ANSI-N18.2a-1975 "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants" and is presented in UFSAR section 3.2. (CNS-1465.00-00-0007).
All structures, systems and components required to shut down and maintain the reactor in a safe and orderly condition or prevent the uncontrolled release of excessive amounts of radioactivity have a seismic classification of Category I. The Catawba design complies with Regulatory Guide 1.29 for SSC seismic design requirements, with the exception of SSCs provided in the Westinghouse scope. The seismic design for the Westinghouse supplied SSC satisfied the classification of safety related systems and components as outlined by ANSI-N18.2a-1975 "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants" and is presented in UFSAR section 3.2. (CNS-1465.00-00-0007).
a   Duke Class A, B, C piping per ASME Section I11,1974, Class III (Reference UFSAR TABLE 3-5) a   Duke Class A, B, C valves per ASME Section I11,1974 (Reference UFSAR TABLE 3-6)
a Duke Class A, B, C piping per ASME Section I11, 1974, Class III (Reference UFSAR TABLE 3-5) a Duke Class A, B, C valves per ASME Section I11, 1974 (Reference UFSAR TABLE 3-6)
* Duke Class F piping per ANSI B31.1, 1973 (Reference UFSAR TABLE 3-5)
Duke Class F piping per ANSI B31.1, 1973 (Reference UFSAR TABLE 3-5)
* Duke Class F valves per ANSI B31.1, Class Ill (Reference UFSAR TABLE 3-6)
Duke Class F valves per ANSI B31.1, Class Ill (Reference UFSAR TABLE 3-6)
* Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.
Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.
&   Regulatory Guide 1.48, "Design Limits and Loading Combinations for Category I Fluid System Components,"
& Regulatory Guide 1.48, "Design Limits and Loading Combinations for Category I Fluid System Components,"
May 1973.
May 1973.
* Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nucl.ir Pet:."-- Plants," Revision 1, December 1973.
Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nucl.ir Pet:."-- Plants," Revision 1, December 1973.
* Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants," October 1973.
Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants," October 1973.
* Regulatory Guide 1.92, "Combining Responses and Spatial Components in Seismic Response Analysis,"
Regulatory Guide 1.92, "Combining Responses and Spatial Components in Seismic Response Analysis,"
Revision 1, February 1976.
Revision 1, February 1976.
* Regulatory Guide 1.122, "Development of Floor Response Spectra for Seismic Design of Floor Supported Equipment or Componenls," Revision 1, February 1978.
Regulatory Guide 1.122, "Development of Floor Response Spectra for Seismic Design of Floor Supported Equipment or Componenls," Revision 1, February 1978.
* Regulatory Guide 1.100, 'Seismic Qualification of Electric Equipment for Nuclear Power Plants," Revision 1, August 1977.
Regulatory Guide 1.100, 'Seismic Qualification of Electric Equipment for Nuclear Power Plants," Revision 1, August 1977.
* IEEE Standard 344-1971, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Station.
IEEE Standard 344-1971, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Station.
* IEEE Standard 344-1975, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.
IEEE Standard 344-1975, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 3 of 15 2.0 Personnel Qualifications The personnel involved in the Catawba NTTF Recommendation 2.3 Seismic Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in rABLE 2-1 below. Additional Peer Review Team experience is outlined within the Peer Review Summary Report (ATTACHMENTS 6A and BA).
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 3 of 15 2.0 Personnel Qualifications The personnel involved in the Catawba NTTF Recommendation 2.3 Seismic Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in rABLE 2-1 below.
TABLE 2-1 IL&
Additional Peer Review Team experience is outlined within the Peer Review Summary Report (ATTACHMENTS 6A and BA).
Personnel Qualifications 6~ Qr      .2 a)                X SW E1             J >
TABLE 2-1 Personnel Qualifications SW E1 E
E      -o
-o 6~
                                                                                              -~                  0>
Qr
Oa        PE0                                                              ui~Lu         UX           a)..
.2 Oa 0
Bryan Hanna, P.E.*, (ARES-         BS/Civi Engineering       12   SW E       X Kevin Rubright, (ARES)             BS/Civil Engineering       30   SWGE     "  X John North, P.E., (ARES)           BS/Civil Engineering       28     SWE       X X...
ui~
Anthony Fazio, (Shaw)               BS/Chemical               >40     SWE       X Engineering Philip Berdos, (Shaw)               BS/Mechanical SEngIineering                 6   __XSWE James Pappas, P.E.,                 MS/Energy                 31     SWE       X (Shaw)                             Engineering James Adam, P.E., (Shaw)           IMS/Nuclear Engineering               4       S     (2) x Tom R Leitch, P.E., (Duke)         BS/Civil Engineering       35     SWE (2)   X       X X     X J David Kennedy (Duke)             B/Civil Engineering       22   SWE t       X '
PE Lu UX a)..
Michael F Medlin, P.E.             25/Civil Engineering       31   SWE         X'         xX (Duke)                             BS/Civi Enierig3_
a)
Raymond C Fung,         E.,         MS/Civil Engineering     32   S<X                     X Duyke)                                                                     1
X J
__XQG Robert L. Keiser P.E.,             MS/Civil Engineering       >20   SQUG                                 X (Duke)                                           __X        >20_SWE___
-~
Charles M.Conselman, P.E.           BS/Civil Engineering     28     SWE   2X)
0>
Bryan Hanna, P.E.*, (ARES-BS/Civi Engineering 12 SW E X
Kevin Rubright, (ARES)
BS/Civil Engineering 30 SWGE X
John North, P.E., (ARES)
BS/Civil Engineering 28 SWE X
X...
Anthony Fazio, (Shaw)
BS/Chemical  
>40 SWE X
Engineering Philip Berdos, (Shaw)
BS/Mechanical SEngIineering 6
SWE
__X James Pappas, P.E.,
MS/Energy 31 SWE X
(Shaw)
Engineering James Adam, P.E., (Shaw)
IMS/Nuclear Engineering 4
S (2) x Tom R Leitch, P.E., (Duke)
BS/Civil Engineering 35 SWE (2)
X X
X X
J David Kennedy (Duke)
B/Civil Engineering 22 SWE t X '
Michael F Medlin, P.E.
25/Civil Engineering 31 SWE X'
X x
(Duke)
BS/Civi Enierig3_
Raymond C Fung, E.,
MS/Civil Engineering 32 S<X X
Duyke)
XQG 1
Robert L. Keiser P.E.,
MS/Civil Engineering  
>20 SQUG X
(Duke)  
>20_SWE___
__X Charles M. Conselman, P.E.
BS/Civil Engineering 28 SWE 2X)
(ARES)
(ARES)
Paul Baughman P.E.,                 B5/Civil Engineering     >40   SQUG11t (ARES)                             BCi           _Enned             SW 12 E
Paul Baughman P.E.,
Robert N Pryce (Duke)             BS/Mech Engineering       28     PSRO               X   X             X Tom Baumgardner (Duke)                       n/a             45     PSRO               X               X Fred Willis P.E., (Duke)           BS/Civil Engineern       32                           X Mark Shutt P E., (Duke)             BS/Civil Engineering     32                           X George Bushnell P.E.,               25CiilEninein           4+       WE 2 BS/Civil Engineering     40+     SWE('                               X (Shaw)
B5/Civil Engineering  
NOTES:
>40 SQUG11t (ARES)
: 1)   SQUG Seismic Capability Engineers (SCEs) have successfully completed SQUG training.
BCi
: 2)   SeismIcWalkdown Engineers (SWEs) have successfully completed EPRI 1025286 2 day walkdown training course.
_Enned SW E12 Robert N Pryce (Duke)
: 3)   Senior Team Member
BS/Mech Engineering 28 PSRO X
: 4)   Prior Senior Reactor Operator (SRO).
X X
Tom Baumgardner (Duke) n/a 45 PSRO X
X Fred Willis P.E., (Duke)
BS/Civil Engineern 32 X
Mark Shutt P E., (Duke)
BS/Civil Engineering 32 X
George Bushnell P.E.,
25CiilEninein 4+
WE 2 (Shaw)
BS/Civil Engineering 40+
SWE('
X NOTES:
: 1)
SQUG Seismic Capability Engineers (SCEs) have successfully completed SQUG training.
: 2)
SeismIcWalkdown Engineers (SWEs) have successfully completed EPRI 1025286 2 day walkdown training course.
: 3)
Senior Team Member
: 4)
Prior Senior Reactor Operator (SRO).
IL&


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 4 of 15 3.0 Selection of Equipment for the SWEL-1 and SWEL-2 Lists The Catawba Unit 1 SWEL-1 and SWEL-2 equipment selection was performed in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference CNC-1206.03-00-0202, Rev. 0).
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 4 of 15 3.0 Selection of Equipment for the SWEL-1 and SWEL-2 Lists The Catawba Unit 1 SWEL-1 and SWEL-2 equipment selection was performed in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference CNC-1206.03-00-0202, Rev. 0).
SWEL -1 The EPRI SWEL-1 Screening Criteria #1 through #3 are as follows:
SWEL -1 The EPRI SWEL-1 Screening Criteria #1 through #3 are as follows:
: 1) Seismic Category I licensing bases
: 1) Seismic Category I licensing bases
: 2) Exclude structures, penetrations, and piping systems
: 2)
: 3) Equipment must perform safety function (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, decay heat removal, containment integrity). The EPRI screening criteria further allows major NSSS equipment inside containment to be excluded.
Exclude structures, penetrations, and piping systems
: 3)
Equipment must perform safety function (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, decay heat removal, containment integrity).
The EPRI screening criteria further allows major NSSS equipment inside containment to be excluded.
The original Catawba IPEEE Seismic Walkdown list (CNC-1535.00-00-0005, Rev. 3), was used as an initial "Base-1 List" of potential SWEL-1 walkdown components. After exclusion of non-seismic equipment, the prior IPEEE list effectively represents the output of EPRI guidance equipment Screening criteria's #1, #2 and #3. The Catawba Unit 1 SWEL-1 "Base-1 List" Is provided in ATTACHMENT 1A. Some equipment on the list is denoted as non-seismic and two non-seismic items were included on the final SWEL-1 equipment list.
The original Catawba IPEEE Seismic Walkdown list (CNC-1535.00-00-0005, Rev. 3), was used as an initial "Base-1 List" of potential SWEL-1 walkdown components. After exclusion of non-seismic equipment, the prior IPEEE list effectively represents the output of EPRI guidance equipment Screening criteria's #1, #2 and #3. The Catawba Unit 1 SWEL-1 "Base-1 List" Is provided in ATTACHMENT 1A. Some equipment on the list is denoted as non-seismic and two non-seismic items were included on the final SWEL-1 equipment list.
EPRI Screening criteria #4 was then used to select equipment from this "Base-1 List." EPRI screening criteria
EPRI Screening criteria #4 was then used to select equipment from this "Base-1 List." EPRI screening criteria
    #4 requires a representative cross-section of the following sample selection attributes:
#4 requires a representative cross-section of the following sample selection attributes:
          "  include a variety of systems
include a variety of systems Include variety of types of equipment Include a variety of equipment environments Include major new/replacement equipment Include equipment enhancements implemented in response to prior IPEEE walkdown identified discrepancies The Catawba Unit 1 SWEL-1 equipment list (ATTACHMENT 2A) comprised 119 components in 26 different systems. The SWEL-1 list represented equipment from each of the EPRI guidance equipment classes, with the exception of Low Voltage Switchgear, Engine Generators, and Motor-Generator Sets. Catawba does not have any Seismic Cat I equipment within the motor generator equipment class. The SWEL-1 lists included equipment located in -40 different plant areas/rooms locations. The selected equipment locations represent a broad range of equipment environmental conditions (e.g. inside containment, partial outdoor exposure, electrical/mechanical penetration rooms, pipe-chases, control room, etc.). Modified, new, and/or replacement equipment comprised
          "  Include variety of types of equipment
-25% of the SWEL-1 list.
          "  Include a variety of equipment environments
Significant modified/new/replacement equipment since the IPEEE was limited, and primarily included equipment such as battery racks/chargers/inverters, MOV/AOVs, and controls upgrades/replacements. Some of the items listed included equipment which was enhanced in response to the prior IPEEE walkdown effort.
          "  Include major new/replacement equipment
          . Include equipment enhancements implemented in response to prior IPEEE walkdown identified discrepancies The Catawba Unit 1 SWEL-1 equipment list (ATTACHMENT 2A) comprised 119 components in 26 different systems. The SWEL-1 list represented equipment from each of the EPRI guidance equipment classes, with the exception of Low Voltage Switchgear, Engine Generators, and Motor-Generator Sets. Catawba does not have any Seismic Cat I equipment within the motor generator equipment class. The SWEL-1 lists included equipment located in -40 different plant areas/rooms locations. The selected equipment locations represent a broad range of equipment environmental conditions (e.g. inside containment, partial outdoor exposure, electrical/mechanical penetration rooms, pipe-chases, control room, etc.). Modified, new, and/or replacement equipment comprised
      -25% of the SWEL-1 list. Significant modified/new/replacement equipment since the IPEEE was limited, and primarily included equipment such as battery racks/chargers/inverters, MOV/AOVs, and controls upgrades/replacements. Some of the items listed included equipment which was enhanced in response to the prior IPEEE walkdown effort.
The SWEL-1 component selection further considered PRA risk significance relative to the external seismic event.
The SWEL-1 component selection further considered PRA risk significance relative to the external seismic event.
The SWEL-1 component list included a broad sampling of components, which were identified to have a significant contribution to CDF for the external seismic event.
The SWEL-1 component list included a broad sampling of components, which were identified to have a significant contribution to CDF for the external seismic event.
Line 1,796: Line 2,743:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 5 of 15 SWEL -2 The Catawba Unit 1 SWEL-2 spent fuel pool equipment list was developed in accordance with the EPRI guidance. Seismic Category I structures, piping, and containment penetrations were specifically excluded by the EPRI guidance. The four screening criteria specified were as follows:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 5 of 15 SWEL -2 The Catawba Unit 1 SWEL-2 spent fuel pool equipment list was developed in accordance with the EPRI guidance. Seismic Category I structures, piping, and containment penetrations were specifically excluded by the EPRI guidance. The four screening criteria specified were as follows:
: 1) Seismic Category I licensing bases
: 1) Seismic Category I licensing bases
: 2) Spent Fuel Pool (SFP) equipment appropriate for an equipment walkdown process
: 2)
Spent Fuel Pool (SFP) equipment appropriate for an equipment walkdown process
: 3) Sample considerations represent broad population of equipment with considered sample selection attributes such as:
: 3) Sample considerations represent broad population of equipment with considered sample selection attributes such as:
: a. represent a variety of systems
: a.
: b. major new/replacement equipment
represent a variety of systems
: c. variety of equipment types
: b.
: d. variety of environments OR
major new/replacement equipment
: c.
variety of equipment types
: d.
variety of environments OR
: 4) Equipment which could result In rapid drain down of the SFP (includes both seismic and non-seismic components and similar factors outlined in 3) above, as practical).
: 4) Equipment which could result In rapid drain down of the SFP (includes both seismic and non-seismic components and similar factors outlined in 3) above, as practical).
The SWEL-2 equipment "Base-2 List" (ATTACHMENT 3A) was established based on screens #1 and #2 above.
The SWEL-2 equipment "Base-2 List" (ATTACHMENT 3A) was established based on screens #1 and #2 above.
Equipment was selected from the Base-2 List based on screening criteria #3 above, and primarily included major equipment such as the spent fuel cooling system pumps and heat-exchangers.
Equipment was selected from the Base-2 List based on screening criteria #3 above, and primarily included major equipment such as the spent fuel cooling system pumps and heat-exchangers.
The SWEL-2 list was further supplemented based on screening criteria #4 above, to include equipment which could result In SFP rapid drain-down, as defined by the EPRI guidance. The SWEL-2 Rapid Drain Down Equipment List is also provided in ATTACHMENT 3A. The screen criteria #4 did not exclude non-seismic components from SWEL-2 selection. Due to the siphon and drain down resistant design of the spent fuel pool systems at Catawba, some manual valves and a strainer that would not be in the specific "classes of equipment" outlined by the EPRI guidelines were included in the "Rapid Draindown List". The final SWEL-2 list is provided in ATTACHMENT 4A and was comprised of 9 components.
The SWEL-2 list was further supplemented based on screening criteria #4 above, to include equipment which could result In SFP rapid drain-down, as defined by the EPRI guidance.
The SWEL-2 Rapid Drain Down Equipment List is also provided in ATTACHMENT 3A.
The screen criteria #4 did not exclude non-seismic components from SWEL-2 selection. Due to the siphon and drain down resistant design of the spent fuel pool systems at Catawba, some manual valves and a strainer that would not be in the specific "classes of equipment" outlined by the EPRI guidelines were included in the "Rapid Draindown List". The final SWEL-2 list is provided in ATTACHMENT 4A and was comprised of 9 components.


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 6 of 15 4.0 Seismic Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group / ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at Catawba Nuclear Station. The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the accessible items, are provided in Attachment 5A 1. Duke Energy self-performed the NTTF 2.3 seismic walkdown of inaccessible items.
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 6 of 15 4.0 Seismic Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group / ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at Catawba Nuclear Station.
The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the accessible items, are provided in Attachment 5A 1. Duke Energy self-performed the NTTF 2.3 seismic walkdown of inaccessible items.
The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the inaccessible items, are provided in Attachment 7A.
The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the inaccessible items, are provided in Attachment 7A.
The seismic walkdowns and area walk-bys were conducted in accordance with the guidance outlined in EPRI Report 1025286. The EPRI Seismic Walkdown Checklists (SWC)s were completed for each equipment item on the SWEL. The EPRI Area Walk-By Checklists (AWC)s were completed for areas/rooms associated with SWEL equipment.
The seismic walkdowns and area walk-bys were conducted in accordance with the guidance outlined in EPRI Report 1025286. The EPRI Seismic Walkdown Checklists (SWC)s were completed for each equipment item on the SWEL. The EPRI Area Walk-By Checklists (AWC)s were completed for areas/rooms associated with SWEL equipment.
Line 1,816: Line 2,771:
If the Seismic Walkdown Engineers (SWEs) determined a potentially adverse seismic condition existed, then thie issue was entered into the corrective action program (CAP) to allow further engineering evaluation. The CAP engineering evaluation determined whether the potentially adverse seismic condition was degraded, unanalyzed, or non-conforming to the design and licensing bases.
If the Seismic Walkdown Engineers (SWEs) determined a potentially adverse seismic condition existed, then thie issue was entered into the corrective action program (CAP) to allow further engineering evaluation. The CAP engineering evaluation determined whether the potentially adverse seismic condition was degraded, unanalyzed, or non-conforming to the design and licensing bases.
Seismic Walkdown Checklists (SWC) have been completed for all of the components listed on the SWEL. This total is comprised of 119 SWEL-1 components, and nine SWEL-2 components. Sixteen of the SWCs, which were inaccessible2 during the ShawtARES walkdown, were completed by Duke personnel. Fourteen of these p.,
Seismic Walkdown Checklists (SWC) have been completed for all of the components listed on the SWEL. This total is comprised of 119 SWEL-1 components, and nine SWEL-2 components. Sixteen of the SWCs, which were inaccessible2 during the ShawtARES walkdown, were completed by Duke personnel. Fourteen of these p.,
were completed during the outage, and two were completed prior to the outage. For the non-line mounted L\K SWEL equipment, an anchorage as-built verification was completed for 76% of the equipment with anchorage.
were completed during the outage, and two were completed prior to the outage. For the non-line mounted L\\K SWEL equipment, an anchorage as-built verification was completed for 76% of the equipment with anchorage.
Additionally, a total of 76 Area Walk-Bys Checklists (AWC) were completed. Eleven AWC's were completed by Duke personnel during the outage.
Additionally, a total of 76 Area Walk-Bys Checklists (AWC) were completed. Eleven AWC's were completed by Duke personnel during the outage.
The seismic walkdowns and walk-bys identified 40 "Potentially Adverse Seismic Conditions", which are itemized in TABLE 4-1. Refer to the notes for the walkdown items for the "CAP Disposition" explanation. Each of the potentially adverse seismic conditions was entered into the CAP. Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. InL\
The seismic walkdowns and walk-bys identified 40 "Potentially Adverse Seismic Conditions", which are itemized in TABLE 4-1.
some cases work requests or CAP ACTIONS were initiated as required to resolve minor issues and/or to enhance/evaluate field equipment clearances. Potentially Adverse Seismic Condition #33 is not listed in Appendix B of ATTACHMENT 5A. It was imported from the Unit 2 walkdown report as a shared equipment walkdown Item.
Refer to the notes for the walkdown items for the "CAP Disposition" explanation. Each of the potentially adverse seismic conditions was entered into the CAP. Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. InL\\
some cases work requests or CAP ACTIONS were initiated as required to resolve minor issues and/or to enhance/evaluate field equipment clearances.
Potentially Adverse Seismic Condition #33 is not listed in Appendix B of ATTACHMENT 5A. It was imported from the Unit 2 walkdown report as a shared equipment walkdown Item.
1CNS documented the submittal attachments as 1A, 2A, etc. for Unit 1, and 1B, 2B, etc. for Unit 2.
1CNS documented the submittal attachments as 1A, 2A, etc. for Unit 1, and 1B, 2B, etc. for Unit 2.
Fourteen were Inaccessible during plant operation. Two had anchorage partly obscured and work orders were required to access the obscured anchorage.
Fourteen were Inaccessible during plant operation. Two had anchorage partly obscured and work orders were required to access the obscured anchorage.


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 7 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item                                               Potenlially Adverse Condition                                       Disposition (See notes)
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 7 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potenlially Adverse Condition Disposition (See notes)
: 1) Romn 400, NN-53         Poorly restrained small cable tray with polential tbr interaction with 10" fire water header. Also.
: 1) Romn 400, NN-53 Poorly restrained small cable tray with polential tbr interaction with 10" fire water header. Also.
Walk-by for           poi- lateral support of .iunction box that coHsts-.ts flCxiblC c0ndtuitlcabling to IRNTE5010.(Nois-         1,9 I RN225 B             QA) It has a potential for cnble to tear out ClUring n seismic event and lose function.
Walk-by for poi-lateral support of.iunction box that coHsts-.ts flCxiblC c0ndtuitlcabling to I RNTE5010.(Nois-1,9 I RN225 B QA) It has a potential for cnble to tear out ClUring n seismic event and lose function.
1,arge bore RF lite (approx. 10" dia.) and branch lines arc generally very poorly latcrally
1,arge bore RF lite (approx. 10" dia.) and branch lines arc generally very poorly latcrally
: 2) Room 400, NN-53         restrained throUtghout the area. One instance the unrestrained 10" line is toUCtiing I vertical Walk-by for           support Ibr the RN Return Hleader. I-1/4" din. SS line (no label; dark-bloc pain)) ruits through             2, 9 I RN2253               tilse area and is poorly-SUpported (laterally). Potential for seismic interaction in several locations.
: 2) Room 400, NN-53 restrained throUtghout the area. One instance the unrestrained 10" line is toUCtiing I vertical Walk-by for support Ibr the RN Return H leader. I-1/4" din. SS line (no label; dark-bloc pain)) ruits through 2, 9 I RN2253 tilse area and is poorly-SUpported (laterally). Potential for seismic interaction in several locations.
: 3) Room 407, QQ-61         A continuations Iiom other walk-down areas (see AWC for Atix, 577', Room 400, QQ-60 area)
: 3) Room 407, QQ-61 A continuations Iiom other walk-down areas (see AWC for Atix, 577', Room 400, QQ-60 area)
Walk-by for           of unsupported stainless steel piping (app'ox. 2" to 2-1/2" line / Refl"Deminenalizcd Water) is               1,9 IWakN58B               poorly supported (laterally) and is likely to interact with various structures and fcntures during a
Walk-by for of unsupported stainless steel piping (app'ox. 2" to 2-1/2" line / Refl" Deminenalizcd Water) is 1,9 IWakN58B poorly supported (laterally) and is likely to interact with various structures and fcntures during a
                          .5seismic event and cause tlooding or sprit.
.5seismic event and cause tlooding or sprit.
,I) Room 400, 1..,-
,I) Room 400, 1..,-
53: Area Walk-       RF line valve IRF254 actuator stem is within 3/16" of vertically-mounted TS Mx8         (approx). The       1,9 By for I KC8113B     R1 line on which the valve is mounted (inline) is poorly supported (laterally).
53: Area Walk-RF line valve I RF254 actuator stem is within 3/16" of vertically-mounted TS Mx8 (approx). The 1,9 By for I KC8113B R1 line on which the valve is mounted (inline) is poorly supported (laterally).
: 5) Room 400, LL-           VVB   breaking nir line and YM dcrifseralization. Water lines are poorly supported and are 53: Area Walk-       currently touching near L..-53. Also, WE (Equipment Decontamination) lines in the amen are                   1,9 B)' for I KC813B      poorly laterally supported.
: 5)
Door 4809 associated with the adjacent Unit I, 113Battery Elnclosure opens outward toward
Room 400, LL-VVB breaking nir line and YM dcrifseralization. Water lines are poorly supported and are 53: Area Walk-currently touching near L..-53. Also, WE (Equipment Decontamination) lines in the amen are 1,9 B)' for I KC813 B poorly laterally supported.
: 6)     1DGCB: 11.t         subject equipment. The door can only open about 8-9 inches and cannot be used for access.
Door 4809 associated with the adjacent Unit I, 113 Battery Elnclosure opens outward toward
Diesel Generator     Il      'owcvr, the door could be accidentally opened from the inside of the enclosure and could               1, 9 Battery Charger       strike the subject equipment.
: 6) 1 DGCB: 11.t subject equipment. The door can only open about 8-9 inches and cannot be used for access.
: 7)   Aux Bldg, 594',
Diesel Generator I l
Room 500, NN-         Base orNon-QA ONFIHG (NF Ice Bin) has boric acid around perimeter. The white residue and                     2, 9 59 Area Walk-By       corrosion is at anchors and drains.
'owcvr, the door could be accidentally opened from the inside of the enclosure and could 1, 9 Battery Charger strike the subject equipment.
: 7)
Aux Bldg, 594',
Room 500, NN-Base orNon-QA ONFIHG (NF Ice Bin) has boric acid around perimeter. The white residue and 2, 9 59 Area Walk-By corrosion is at anchors and drains.
for I KCTKB
for I KCTKB
: 8) DHI (Inner), FF-53: Area By foA     Walk-I SVc,       Scaffold storage needs tie-back to "dedicated" tic-off point, approved by engineering                       1, 9 BySAS, afnd         department. Also, one ladder eottied back.
: 8) DHI (Inner), FF-53: Area Walk-By foA I SVc,
Scaffold storage needs tie-back to "dedicated" tic-off point, approved by engineering 1, 9 BySAS, afnd department. Also, one ladder eot tied back.
I SV26B
I SV26B
: 9)     1VGCPBI: IBI         Four anchor bolts total. The two bolts on the east side have mild corrosion with the bolt in the EDG Starting Ai'     NE corner having the most serious corrosion.                                                                 1, 9 Compressor
: 9) 1VGCPBI: IBI Four anchor bolts total. The two bolts on the east side have mild corrosion with the bolt in the EDG Starting Ai' NE corner having the most serious corrosion.
: 10) IVGCPBI: IBI           An adjacent hand wheel chain for EQ IRNP08 hangs low enough such that it could impact or EDG Sting Air         become entangled with the subject equipment.
1, 9 Compressor
Compressor T1: wo adjacent fire extinguishers (one each containing C02 and water) are hanging from small 11)Room 372, BB-5           hooks and could jump offduring a seissIlic event. The extinguishers could discharge retardant IEADB                  and could lurch across the floor and strike adjacent equipment. These hooks should be evaluated to confirm the extinguishers will not jump off.
: 10) IVGCPBI: IBI An adjacent hand wheel chain for EQ I RNP08 hangs low enough such that it could impact or EDG Sting Air become entangled with the subject equipment.
Compressor T1:
wo adjacent fire extinguishers (one each containing C02 and water) are hanging from small 11)Room 372, BB-5 hooks and could jump offduring a seissIlic event. The extinguishers could discharge retardant I EADB and could lurch across the floor and strike adjacent equipment. These hooks should be evaluated to confirm the extinguishers will not jump off.
: 12) Yard, Bottom of IFWTK0001 Containment Basin:
: 12) Yard, Bottom of IFWTK0001 Containment Basin:
Area Walk-By for     Unistrut base for cable tray support and various instrumentation cabinets are severely corroded.           2, 7 1FWLTSOO,I FWL T5010, IFWTKOI, and FWLT5130
Area Walk-By for Unistrut base for cable tray support and various instrumentation cabinets are severely corroded.
2, 7 1FWLTSOO,I FWL T5010, IFWTKOI, and FWLT5130


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 8 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item           Polentially Adverse Condition                                                                       Disposition (See notes) 13)] FWI..T5000:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 8 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions Walkdown Item Polentially Adverse Condition CAP Disposition (See notes) 13)] FWI..T5000:
FWST WR             Instrumentation panel angle frame supports and associated wedge anchors arc severcly oxidized 2,7 Level Channel        / corroded.
FWST WR Level Channel
    #1l
#1l Instrumentation panel angle frame supports and associated wedge anchors arc severcly oxidized
/ corroded.
2,7
: 14) I F W L r5010:
: 14) I F W L r5010:
    ]:WST \VR.           Instrumentation panel angle roani sujoporls antd associated %%edgeanchors arc severely oxidized           2,7 Level Channel       / colroded.                                                                                               2 15)1ECA: 125VDC         CN- 1214-08.08 Rev does not indicatc weld al the inierrace beween chnrger bottom rnr             d aue Vital Battery       field-installed plates. See section C-C. (Shown on CN-1214-08.08 Rev 1A)                                 3,9 Charger L16)   IEBA: IAI, ESSENTIA            One ( I) achoIr nut appCarsi to lack full engagement with the anchor stud. Location of specilic BATIAL             slud/nut: starting fioom doorway to battery rack enclosure find the second row ol'baltery BATTERY                                                                                                                      1, 6 rack/frame anchors. Observe second anchor in from aisle way.
]:WST \\VR.
Instrumentation panel angle roani sujoporls antd associated %%edge anchors arc severely oxidized 2,7 Level Channel  
/ colroded.
2 15)1ECA: 125VDC CN-1214-08.08 Rev does not i ndicatc weld al the inierrace beween chnrger bottom rnr aue d Vital Battery field-installed plates. See section C-C. (Shown on CN-1214-08.08 Rev 1A) 3,9 Charger L16)
IEBA: IA ESSENTIA I, One ( I) achoIr nut appCarsi to lack full engagement with the anchor stud. Location of specilic BATIAL slud/nut: starting fioom doorway to battery rack enclosure find the second row ol'baltery 1, 6 BATTERY rack/frame anchors. Observe second anchor in from aisle way.
RACK
RACK
: 17) Aux Bldg, 543',
: 17) Aux Bldg, 543',
Room 23!, 11,-
Room 23!, 11,-
55: Area Walk-     Valve I NV203A has a heavy operator with long moment arm and should be verified against By for             design isometric drawing. (Duke comment - This is a rigorously analyzed system)                           1, 9 I NVIIU13CC and INV202B
55: Area Walk-Valve I NV203A has a heavy operator with long moment arm and should be verified against By for design isometric drawing. (Duke comment - This is a rigorously analyzed system) 1, 9 I NVIIU13CC and INV202B
: 18) 1 EMXB: 600 VAC Essential Motor       I out o1"96 bolts are missing (below bucket IEMXB FOID: back-left bolt location).                       1, 8 Control Center
: 18) 1 EMXB: 600 VAC Essential Motor I out o1"96 bolts are missing (below bucket IEMXB FOID: back-left bolt location).
: 19) AWC Aux Bldg,       An approx. 214" diameter fire suppression pipe is suspended by threaded rods and clevises. Rods 554', Rm 350 5-545: 350 Are    are approximately 20 feet long. End of rod at lower end is adjacent to Unistrut. Clevis can swing BB-5455: Area     into Unistrut. Pipe connections are welded. Pipe may become damaged by interacting with                   1,9 Walk-By for       Unistrut. (Duke comment -Evaluation determined interaction is limited to minor IEID and IEIF                                                                                         scraping) 20)1 [1F: t20 VAC Vital An approximately three inch diameter rigid electrical conduit sweeps 90 degrees from I ElF to Swing nlverter       Unistrut support. Unistrut is connected to column and to a network of Unistrut which is also             2, 9 connected to ceiling (upper diaphragm)...__
1, 8 Control Center
: 19) AWC Aux Bldg, An approx. 214" diameter fire suppression pipe is suspended by threaded rods and clevises. Rods 554', Rm 350 5-545: Are 350 are approximately 20 feet long. End of rod at lower end is adjacent to Unistrut. Clevis can swing BB-5455: Area into Unistrut. Pipe connections are welded. Pipe may become damaged by interacting with 1,9 Walk-By for Unistrut. (Duke comment -Evaluation determined interaction is limited to minor scraping)
IEID and IEIF 20)1 [1F: t20 VAC Vital An approximately three inch diameter rigid electrical conduit sweeps 90 degrees from I ElF to Swing nlverter Unistrut support. Unistrut is connected to column and to a network of Unistrut which is also 2, 9 connected to ceiling (upper diaphragm)...__
: 21) ALIx Bldg, 543',
: 21) ALIx Bldg, 543',
Room 2t7,FF53-JJ51: Area Walk-By There was a missing stud and nut on a base plate fora stand-off arm for instrument fortNt185A.       tubing1 WLIV606I(Non-QA).                                                                                 2,9 INV77A, and INV312A
Room 2t7,FF53-JJ51: Area Walk-By There was a missing stud and nut on a base plate fora stand-off arm for instrument fortNt185A.
tubing1 WLIV606I(Non-QA).
2,9 INV77A, and INV312A
: 22) Aux Bldg, 543',
: 22) Aux Bldg, 543',
Room 217,FF53-     Relatively congested to very congested area. There was a hand wheel for 1FW24 (4" line) that is J.J5 1:Area Walk-By about 3/8" from a perpendicular pipe (lYN127) (Non QA '" dia pipe). During seismic event                 1,9 forlNt185A, INV77A, and         interaction line could damage both pieces of equipment.
Room 217,FF53-Relatively congested to very congested area. There was a hand wheel for 1FW24 (4" line) that is J.J5 1: Area Walk-By about 3/8" from a perpendicular pipe (lYN127) (Non QA '" dia pipe). During seismic event 1,9 forlNt185A, INV77A, and interaction line could damage both pieces of equipment.
INV312A
INV312A


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 9 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item           Potentially Adverse Condition                                                                   Disposition (See noteg)
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 9 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potentially Adverse Condition Disposition (See noteg)
: 23) Aux Bldg, 594',
: 23) Aux Bldg, 594',
Room 570, Various:
Room 570, Various:
Area Walk-By forICRA-C-I CP,     I CRA-C- I condenser head pressure transmitter (OYCPT6120) has vulnerable tubing which ICRA-C-I,ICRA-     could be compromised by lateral displacement of operator for I YC6 (YC Chiller A Supply to             1,9 PFT-l, ICRA-       Channel A Header Isolation). (Duke verified OK per CNC-1206.02-89-2003)
Area Walk-By forICRA-C-I CP, I CRA-C-I condenser head pressure transmitter (OYCPT6120) has vulnerable tubing which ICRA-C-I,ICRA-could be compromised by lateral displacement of operator for I YC6 (YC Chiller A Supply to 1,9 PFT-l, ICRA-Channel A Header Isolation). (Duke verified OK per CNC-1206.02-89-2003)
PFTF-I, CR-AHlU-1, ICRA-D-1, and OYCPUCWI
PFTF-I, CR-AHlU-1, ICRA-D-1, and OYCPUCWI
: 24) Aux Bldg, 594",
: 24) Aux Bldg, 594",
Room 570,Various:
Room 570,Various:
Area Walk-By forlCRA-C-I CP,     Operator could be damaged (stein) due to potential impact with rigid veir. Support for control ICRA-C-lICRA-1, lRT-I,ICRA.       panel. Approx 1.25" gap. (Duke verified OK per CNC-l1206.02-89-2003)                                   1,9 PFTF-lICR-AI-U-
Area Walk-By forlCRA-C-I CP, Operator could be damaged (stein) due to potential impact with rigid veir. Support for control ICRA-C-lICRA-1, lRT-I,ICRA.
panel. Approx 1.25" gap. (Duke verified OK per CNC-l1206.02-89-2003) 1,9 PFTF-lICR-AI-U-
: 1. ICRA-D-1, and OYCPUCWI
: 1. ICRA-D-1, and OYCPUCWI
: 25) Aux Bldg. 594',
: 25) Aux Bldg. 594',
Room 570,Various:
Room 570,Various:
Area Walk-By for] CRA-C-I CP,   1YC5 (YC Chiller A supply to channel A header drain) has only a 3/16" gap from hand wheel ICRA-C- I. CRA-                                                                                                           2 PFT-rI, ICRA-       to adjacent YC drain.
Area Walk-By for] CRA-C-I CP, 1YC5 (YC Chiller A supply to channel A header drain) has only a 3/16" gap from hand wheel ICRA-C-I. CRA-2 PFT-rI, ICRA-to adjacent YC drain.
PFTF-I,ICR-AHFU-1, ICRA-D-1, and OYCPUCWI
PFTF-I,ICR-AHFU-1, ICRA-D-1, and OYCPUCWI
: 26) Aux Bldg, 594',
: 26) Aux Bldg, 594',
Room 570,Various:
Room 570,Various:
Area Walk-By forlCRA-C-l CP.
Area Walk-By forlCRA-C-l CP.
ICRA-C-I,ICRA-     I" O.D. drain line has an approximately I" gap from IYC5 drain.                                       2, 9 P'FT-1, ICRA-PFTF-I,l CR-AHU-1, ICRA-D-t, and OYCPUCWI
ICRA-C-I,ICRA-I" O.D. drain line has an approximately I" gap from IYC5 drain.
: 27) Room 234, Aux Bldg, 543'%Area     A VQ system pipe (approx. 4" dia. CS) is within 1/8" of safety injection pump suction line Walk-By for         vertical restraint. The VQ system line is only supported vertically with clevis hangers, and IN[PUB,           would interact significantly with the suction line vertical restraint.
2, 9 P'FT-1, ICRA-PFTF-I,l CR-AHU-1, ICRA-D-t, and OYCPUCWI
1MV253B,IN1136B                                                                                                           1, 9
: 27) Room 234, Aux Bldg, 543'% Area A VQ system pipe (approx. 4" dia. CS) is within 1/8" of safety injection pump suction line Walk-By for vertical restraint. The VQ system line is only supported vertically with clevis hangers, and IN[PUB, would interact significantly with the suction line vertical restraint.
      , INl144A,         Approx. mid-line on the 4" VQ system line is a flange connection and a likely source of leak or INII47B, and       spray.
1, 9 1MV253B,IN1136B
, INl144A, Approx. mid-line on the 4" VQ system line is a flange connection and a likely source of leak or INII47B, and spray.
IKCHX0052
IKCHX0052
[28)   RN Pump Hotuse, Pit A, Area Walk- Safety hoist located over access shaft could swing toward adjacent wall and impact adjacent By for IRN.30 A,   spiral tubing. Recommend securing hoist to access shaft handrail.                                     2, 5 and ORNLT7390.
[28) RN Pump Hotuse, Pit A, Area Walk-Safety hoist located over access shaft could swing toward adjacent wall and impact adjacent By for IRN.30 A, spiral tubing. Recommend securing hoist to access shaft handrail.
: 29) 1 FWLT5130 FWST     Instrumentation panel angle frame supports, and associated wedge anchors arc severely                 2, 7 WR Level Ch4         oxidized/corroded.*(Also, see item 13)                                                                 2, 7 30)Area Walk-By for     No lateral bracing in the weak direction for IDCSMC2. (QA-4). Impact on other panels is               2,9 1MCI and 2MC2       unknown.                                                                                               2,_9
2, 5 and ORNLT7390.
: 31) DHI, 587',Room 591: Area Walk-By   1Wz conduit is loosely attached to ICA149 (QA-1) termination box (I2"x12"x6") for limit               2,9 for I CA62A and   switches.
: 29) 1 FWLT5130 FWST Instrumentation panel angle frame supports, and associated wedge anchors arc severely 2, 7 WR Level Ch4 oxidized/corroded.*(Also, see item 13) 2, 7 30)Area Walk-By for No lateral bracing in the weak direction for IDCSMC2. (QA-4).
Impact on other panels is 2,9 1MCI and 2MC2 unknown.
2,_9
: 31) DHI, 587',Room 591: Area Walk-By 1Wz conduit is loosely attached to ICA149 (QA-1) termination box (I2"x12"x6") for limit 2,9 for I CA62A and switches.
ICA66B
ICA66B


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 10 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item           Potentially Adverse Condition                                                                     Disposition ISoe notes)
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 10 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potentially Adverse Condition Disposition ISoe notes)
: 32) 1CRA-c.. CP:     Anchorage system is very robust for seismic loads, Bolts appear to be 518' O.D. Still requires Chiller Comp Cont.                                                                                                         2,9 Panel "A"Trn       drawing verification.
: 32) 1CRA-c..
: 33) Aux Bldg 594, Room 560, FF-59 Area Walkby for     Corrosion: AHU plenum has rusty anchor bolts.                                                           2, 9 2CRA-FAN
CP:
      ,(2CtRA-MU-1)
Anchorage system is very robust for seismic loads, Bolts appear to be 518' O.D. Still requires Chiller Comp Cont.
: 34) 2CRA-FAN             Anchorage layout dimensions were verified; however current licensing basis were not available         2,9 (2CRA-AHU-I)       to verify anchor bolt sizes.
2,9 Panel "A" Trn drawing verification.
: 35) 2CRA-FAN             Hardware: Four anchor bolts are slightly bent. Up to approx. 3/8" gap is created between one           3 (2CRA-A.HU-I)       side of nut and mounting flange.                 ___3,_9
: 33) Aux Bldg 594, Room 560, FF-59 Area Walkby for Corrosion: AHU plenum has rusty anchor bolts.
: 36) CV 1.560' Dcg 46,   Loose locknut on rod supporting I WL820 could lead to support failure unless corrected. This RAD 47, Area                                                                                                               2,9 Walkby for I NI54A was corrected on 12/08/2012 per work order 02070034.
2, 9 2CRA-FAN
: 37) CVI, 567', DEG       Electray marked 140722 not secured to unistrut due to missing/loose fasteners, and cables are 176, RAD 50, Area not well attached to the tray due to missing/loose straps. These cables attach to I ND37A. This         2, 9
,(2CtRA-MU-1)
        \Valkby for IND2A.             was corrected on 12/11/2012 per work order 02070453.
: 34) 2CRA-FAN Anchorage layout dimensions were verified; however current licensing basis were not available 2,9 (2CRA-AHU-I) to verify anchor bolt sizes.
: 38) cvM,567',DEG         Nue, Safety RO. cables run fTom the valve operator to ajunction box. Box found not fastened 176, RAD 50         to the unistrut support that goes to the wall due to fasteners between box and Unistrut being Seismic Walkdown     either loose or missing. During Seismic event, box could fall off unistrut and only be supported       2, 9 for IND2A.         by cables. Resolved per work order 02070468, completed 12/11/2012.
: 35) 2CRA-FAN Hardware: Four anchor bolts are slightly bent. Up to approx. 3/8" gap is created between one 3
SWEL-2 A conduit/cable attached to a temperature element on one of the pump bearings, via a cable
(2CRA-A.HU-I) side of nut and mounting flange.
: 1)  IK.FPUA: IA        tray-mounted junction box has very little slack (IKFTE5330)(Non QA). The installation is Spent Fuel Pool    further subject to adverse seismic interaction due to a lack of support for the cable tray that Pump                supports the J-box. A similar situation exists with a conduit/cable, sensor, and cable tray-supported J-box at the rear pump motor bearing.                                                                 R
___3,_9
: 2)   CVI 568' DEG 244, RAD 47, Area Walkby for Noted that first tubing clamp off operator for I VP7A is loose. This is VI tubing attached to 1V13690. Resolved per work order 02070028, completed 12/15/2012.                                       2,9       A"N I FW8 CAP DISPOSITION Notes:
: 36) CV 1.560' Dcg 46, Loose locknut on rod supporting I WL820 could lead to support failure unless corrected. This RAD 47, Area 2,9 Walkby for I NI54A was corrected on 12/08/2012 per work order 02070034.
: 1) Field configuration m             Current Licensing Bases (CLB) requirements, and no field work required.
: 37) CVI, 567', DEG Electray marked 140722 not secured to unistrut due to missing/loose fasteners, and cables are 176, RAD 50, Area not well attached to the tray due to missing/loose straps. These cables attach to I ND37A. This 2, 9
: 2) Field configuration meets CLB requirements; however, work request/work order/ACTION initiated to resolve minor issue, verify unknown condition, or enhance/correct field configuration.
\\Valkby for IND2A.
was corrected on 12/11/2012 per work order 02070453.
: 38) cvM, 567',DEG Nue, Safety RO. cables run fTom the valve operator to ajunction box. Box found not fastened 176, RAD 50 to the unistrut support that goes to the wall due to fasteners between box and Unistrut being Seismic Walkdown either loose or missing. During Seismic event, box could fall off unistrut and only be supported 2, 9 for IND2A.
by cables. Resolved per work order 02070468, completed 12/11/2012.
SWEL-2
: 1)
IK.FPUA: IA Spent Fuel Pool Pump A conduit/cable attached to a temperature element on one of the pump bearings, via a cable tray-mounted junction box has very little slack (IKFTE5330)(Non QA). The installation is further subject to adverse seismic interaction due to a lack of support for the cable tray that supports the J-box. A similar situation exists with a conduit/cable, sensor, and cable tray-supported J-box at the rear pump motor bearing.
R
: 2)
CVI 568' DEG 244, RAD 47, Noted that first tubing clamp off operator for I VP7A is loose. This is VI tubing attached to Area Walkby for 1 V13690. Resolved per work order 02070028, completed 12/15/2012.
2,9 I FW8 CAP DISPOSITION Notes:
: 1) Field configuration m Current Licensing Bases (CLB) requirements, and no field work required.
: 2)
Field configuration meets CLB requirements; however, work request/work order/ACTION initiated to resolve minor issue, verify unknown condition, or enhance/correct field configuration.
: 3) Field configuration meets CLB requirements; however, design drawing updated to reflect field configuration.
: 3) Field configuration meets CLB requirements; however, design drawing updated to reflect field configuration.
: 4) CLB not met, and required field modification. (No items required this designation.)                                           I&L
: 4) CLB not met, and required field modification. (No items required this designation.)
A "N I&L


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 11 of 15
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 11 of 15
: 5) Lifeline hoist at RN Pumphouse was found installed such that it may contact safety related tubing during a seismic event. The hoist was secured such that no adverse interaction would occur during a seismic event,
: 5) Lifeline hoist at RN Pumphouse was found installed such that it may contact safety related tubing during a seismic event. The hoist was secured such that no adverse interaction would occur during a seismic event,
: 6) Battery 1EBA rack anchor (one of 48) identified to have less than full thread engagement which was evaluated and determined to be acceptable. Also, the hoist in the lEBA Battery Room was evaluated for potential seismic interaction and it was determined that there is nothing in the travel path which would be contacted if the hoist moved.
: 6)
Battery 1EBA rack anchor (one of 48) identified to have less than full thread engagement which was evaluated and determined to be acceptable. Also, the hoist in the lEBA Battery Room was evaluated for potential seismic interaction and it was determined that there is nothing in the travel path which would be contacted if the hoist moved.
: 7) The mounting bolts for the Refueling Water Storage Tank level transmitters were evaluated for corrosion and determined to be robust and acceptable as is. Work Request 01073777 will be used to address/refurbish the corroded mounts.
: 7) The mounting bolts for the Refueling Water Storage Tank level transmitters were evaluated for corrosion and determined to be robust and acceptable as is. Work Request 01073777 will be used to address/refurbish the corroded mounts.
: 8) One (of 96) mounting bolt was found missing on Motor Control Center 1EMXB. Engineering initially determined that, based on the total number of mounting bolts, seismic anchorage is adequate.
: 8) One (of 96) mounting bolt was found missing on Motor Control Center 1EMXB. Engineering initially determined that, based on the total number of mounting bolts, seismic anchorage is adequate.
Line 1,922: Line 2,916:
: 9) Less significant item, identified in the CAP to drive appropriate actions or document disposition of the issue.
: 9) Less significant item, identified in the CAP to drive appropriate actions or document disposition of the issue.
INACCESSIBLE COMPONENTS:
INACCESSIBLE COMPONENTS:
Unit 1 components that were Inaccessible until the next unit shutdown are listed in TABLE 4-2. There were   A fourteen of these components. These component seismic walkdowns and associated area walk-bys were completed by Duke Energy during the outage.
Unit 1 components that were Inaccessible until the next unit shutdown are listed in TABLE 4-2. There were A
TABLE 4-2 Walkdown Inspections Performed in Fall Refueling Outage Location'     EquiprpentID                         Narntale :'
fourteen of these components.
1     Reactor Bldg.       1NV52A               1A NC PUMP SEAL RETURN 1     Reactor Bldg.       1NI54A             C-Leg Accum A Discharge Isolation 1     Reactor Bldg.       1N1438A           Emergency N2 From CLA to 1NC-34A 1     Reactor Bldg.       1ND2A               ND Pump 1A Suct From Loop B 1     Reactor Bldg.       INDIB               ND Pump IA Suct From Loop B 1     Reactor Bldg.     1NC34A                       Unit I PZR PORV 1     Reactor Bldg       1NC32B                      Unit I PZR PORV 1     Reactor Bldg.     1NC36B                       Unit 1 PZR PORV 1     Reactor Bldg.     1NV865A               SBMUP Suction from xfer Tube 1     Reactor Bldg.         VFW8                   Refueling Cavity Drain 1     Reactor Bldg.       1FW46                   Refueling Cavity Drain 1       Annulus.       1NVPDO042           SBMUP Discharge Pulsalion Dampener 1       Annulus         1NVPUSB                 Standby Makeup Pump (NV) 1     Control Room       1SSPSA                 Solid State Prot Sys TT A
These component seismic walkdowns and associated area walk-bys were completed by Duke Energy during the outage.
TABLE 4-2 Walkdown Inspections Performed in Fall Refueling Outage Location' EquiprpentID Narntale :'
1 Reactor Bldg.
1NV52A 1A NC PUMP SEAL RETURN 1
Reactor Bldg.
1NI54A C-Leg Accum A Discharge Isolation 1
Reactor Bldg.
1N1438A Emergency N2 From CLA to 1NC-34A 1
Reactor Bldg.
1ND2A ND Pump 1A Suct From Loop B 1
Reactor Bldg.
INDIB ND Pump IA Suct From Loop B 1
Reactor Bldg.
1NC34A Unit I PZR PORV 1
Reactor Bldg 1 NC32B Unit I PZR PORV 1
Reactor Bldg.
1NC36B Unit 1 PZR PORV 1
Reactor Bldg.
1NV865A SBMUP Suction from xfer Tube 1
Reactor Bldg.
VFW8 Refueling Cavity Drain 1
Reactor Bldg.
1FW46 Refueling Cavity Drain 1
Annulus.
1NVPDO042 SBMUP Discharge Pulsalion Dampener 1
Annulus 1NVPUSB Standby Makeup Pump (NV) 1 Control Room 1SSPSA Solid State Prot Sys TT A


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 12 of 15 RESOLUTION OF UNKNOWN ITEMS There were a total of eighteen SWCs originally designated to be "unknown" in the walkdown report in Attachment 5A. The resolution of these items is described below.
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 12 of 15 RESOLUTION OF UNKNOWN ITEMS There were a total of eighteen SWCs originally designated to be "unknown" in the walkdown report in Attachment 5A. The resolution of these items is described below.
There were three SWCs in the Auxiliary Building which were designated "unknown."                                   It o   Two SWCs were associated with plant operations activities which would not allow access during the walkdown time frame. These items were 1ETXA (4160/600 VAC Transformer) and 1SSPSA (Solid State Protection System). 1ETXA was removed from the list and replaced with 1ETXB (4160/600 VAC Transformer). This item was walked down by Duke Energy. 1SSPSA was walked down during the fall Unit 1 outage (see Table 4-2).
There were three SWCs in the Auxiliary Building which were designated "unknown."
      "    One SWC (iEMXC) was inaccessible at the time of the walkdown. Also some anchors were not visually           IA->
It o
accessible. 1EMXC was removed from the list and replaced with 1ETXD (4160/600 VAC Transformer).
Two SWCs were associated with plant operations activities which would not allow access during the walkdown time frame. These items were 1ETXA (4160/600 VAC Transformer) and 1SSPSA (Solid State Protection System).
1ETXA was removed from the list and replaced with 1ETXB (4160/600 VAC Transformer). This item was walked down by Duke Energy.
1SSPSA was walked down during the fall Unit 1 outage (see Table 4-2).
One SWC (iEMXC) was inaccessible at the time of the walkdown. Also some anchors were not visually IA->
accessible.
1EMXC was removed from the list and replaced with 1ETXD (4160/600 VAC Transformer).
This item was walked down by Duke Energy.
This item was walked down by Duke Energy.
There were eight items from the SWEL-1 list that were designated to be "unknown" because they are located in the Reactor Building.
There were eight items from the SWEL-1 list that were designated to be "unknown" because they are located in the Reactor Building.
* These eight items are shown in Table 4-2. They are INV52A, 1N154A, 1N1438A, 1ND2A, 1NDIB, 1NC34A,           (,4 1NC32B, and 1NC36B. The walkdowns were performed by Duke Energy during the fall 2012 refueling outage.
These eight items are shown in Table 4-2. They are INV52A, 1N154A, 1N1438A, 1ND2A, 1NDIB, 1NC34A,
There were five items from the SWEL-2 list that were designated to be "unknown" because they are located in the   i*L*
(,4 1NC32B, and 1NC36B. The walkdowns were performed by Duke Energy during the fall 2012 refueling outage.
There were five items from the SWEL-2 list that were designated to be "unknown" because they are located in the i*L*
Reactor Building.
Reactor Building.
These items are shown in Table 4-2. They are 1NV865A, 1VFW8, 1FW46, 1NVPD0O42, and 1NVPUSB.
These items are shown in Table 4-2. They are 1NV865A, 1VFW8, 1FW46, 1NVPD0O42, and 1NVPUSB.
They were all walked down by Duke Energy during the fall 2012 refueling outage.                         A_
They were all walked down by Duke Energy during the fall 2012 refueling outage.
A_
There were two items from the SWEL-1 list that were designated to be "unknown" because the anchorage could not be completely verified. They were resolved as described below:
There were two items from the SWEL-1 list that were designated to be "unknown" because the anchorage could not be completely verified. They were resolved as described below:
* 1FWTK01 - Due to enclosure of the tank with sheet metal siding material, the anchorage was not visible and the anchorage configuration could not be verified. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program. This was documented in PIP.
1FWTK01 - Due to enclosure of the tank with sheet metal siding material, the anchorage was not visible and the anchorage configuration could not be verified. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program. This was documented in PIP.
* 1DGBNGC - Anchors between the Unistrut and the concrete wall are not visible or accessible. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program.
1 DGBNGC - Anchors between the Unistrut and the concrete wall are not visible or accessible. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program.
The Unistrut and the anchors from the cubicle to the Unistrut were confirmed in very good material condition, and the location environment is mild most of the time. This was documented in PIP.
The Unistrut and the anchors from the cubicle to the Unistrut were confirmed in very good material condition, and the location environment is mild most of the time. This was documented in PIP.
5.0   Licensing Basis Evaluations As shown in Table 4-1, a total of 40 potentially adverse seismic conditions were identified by the seismic walkdowns and area walk-bys. Also, one issue with the anchor bolts for 0YCPUCW1 was identified during the TI-188 walk-down inspection with the regional NRC inspector. All of the potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to correct minor issues and/or to enhance fiela equipment clearances.
5.0 Licensing Basis Evaluations As shown in Table 4-1, a total of 40 potentially adverse seismic conditions were identified by the seismic walkdowns and area walk-bys. Also, one issue with the anchor bolts for 0YCPUCW1 was identified during the TI-188 walk-down inspection with the regional NRC inspector. All of the potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to correct minor issues and/or to enhance fiela equipment clearances.


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 13 of 15 The potentially adverse seismic conditions and their individual Problem Investigation Process (PIP) tracking numbers are listed in the Unit 1 NTTF 2.3 Seismic Walkdown Summary Reports (Attachment 5A and Attachment 7A).
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 13 of 15 The potentially adverse seismic conditions and their individual Problem Investigation Process (PIP) tracking numbers are listed in the Unit 1 NTTF 2.3 Seismic Walkdown Summary Reports (Attachment 5A and A).
6.0 IPEEE Vulnerabilities The Catawba IPEEE NRC submittal of 6/21/94 (Reference 8) concluded that there were no seismic vulnerabilities from external events. Thus, there were no identified plant changes which would significantly reduce the risk from seismic external events. Table 3-3 of the IPEEE NRC submittal identified one enhancement to resolve minor field walk-down issues, This enhancement is described in Table 6-1.
6.0 IPEEE Vulnerabilities The Catawba IPEEE NRC submittal of 6/21/94 (Reference 8) concluded that there were no seismic vulnerabilities from external events.
TABLE 6-1 IPEEE Enhancements Equipment Deficiency Identified                     Resolution               Date Resolved Installed missing spacers, added Unit 1 EDG battery racks were missing   dummy batteries, stiffened side spacers.                                 rails.
Thus, there were no identified plant changes which would significantly reduce the risk from seismic external events. Table 3-3 of the IPEEE NRC submittal identified one enhancement to resolve minor field walk-down issues, This enhancement is described in Table 6-1.
racks Later   replaced with new  design.batteries and   09/28/2005 (EC12956) 7.0 Peer Review Duke Energy (Duke) contracted with the Shaw Group (Shaw) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). The Peer Review Report is contained in ATTACHMENT 6A.
TABLE 6-1 IPEEE Enhancements Equipment Deficiency Identified Resolution Date Resolved Installed missing spacers, added Unit 1 EDG battery racks were missing dummy batteries, stiffened side spacers.
rails. Later replaced batteries and 09/28/2005 racks with new design.
(EC12956) 7.0 Peer Review Duke Energy (Duke) contracted with the Shaw Group (Shaw) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). The Peer Review Report is contained in ATTACHMENT 6A.
The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the activities. The peer review team is identified in Table 2-1 and their qualifications are provided in ATTACHMENT 6A.
The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the activities. The peer review team is identified in Table 2-1 and their qualifications are provided in ATTACHMENT 6A.
The Shaw/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The peer review covered the following:
The Shaw/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The peer review covered the following:
          "    The selection of the SSCs included on the Seismic Walkdown Equipment List (SWEL).
The selection of the SSCs included on the Seismic Walkdown Equipment List (SWEL).
          "    A sample of the checklists prepared for the seismic walkdowns and area walk-bys.
A sample of the checklists prepared for the seismic walkdowns and area walk-bys.
* The licensing basis evaluations.
The licensing basis evaluations.
* The decisions for entering the potentially adverse conditions in the Corrective Action Program (CAP) process.
The decisions for entering the potentially adverse conditions in the Corrective Action Program (CAP) process.
          "      The submittal report.
The submittal report.
The peer review process for the SWEL development and the seismic walkdowns consisted of the following:
The peer review process for the SWEL development and the seismic walkdowns consisted of the following:
* Reviewing the activity guidance in EPRI 1025286, the NEI Q&A bulletins, the NEI first-mover reports, and NRC Temporary Instruction 25151188.
Reviewing the activity guidance in EPRI 1025286, the NEI Q&A bulletins, the NEI first-mover reports, and NRC Temporary Instruction 25151188.


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 14 of 15 0     Conducting an in-process review at the plant site, including interviews with the personnel performing the activity and reviewing in-process documentation.
NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 14 of 15 0
0       Performing an in-plant surveillance (for the walkdown activity) of a seismic walkdown and an area walk-by.
Conducting an in-process review at the plant site, including interviews with the personnel performing the activity and reviewing in-process documentation.
6     Providing in-process observations and comments to the personnel performing the activities.
0 Performing an in-plant surveillance (for the walkdown activity) of a seismic walkdown and an area walk-by.
a     Conducting a final review of a sample of the completed documentation.
6 Providing in-process observations and comments to the personnel performing the activities.
a Conducting a final review of a sample of the completed documentation.
The peer review process for the licensing basis evaluations and the decisions for entering potentially adverse conditions into the CAP consisted of reviewing the overall review process and a sample of the licensing basis reviews. The peer review process for the submittal report consisted of reviewing the draft submittal prepared by Catawba Design Engineering for licensing review.
The peer review process for the licensing basis evaluations and the decisions for entering potentially adverse conditions into the CAP consisted of reviewing the overall review process and a sample of the licensing basis reviews. The peer review process for the submittal report consisted of reviewing the draft submittal prepared by Catawba Design Engineering for licensing review.
The peer review identified several items, previously added to the Corrective Action Program, which may need           IIN additional detail with respect to the licensing basis review. It should be noted that these items were not considered in error, only that they may require more specific detail in the licensing basis evaluation to document that they were thoroughly assessed.
The peer review identified several items, previously added to the Corrective Action Program, which may need IIN additional detail with respect to the licensing basis review. It should be noted that these items were not considered in error, only that they may require more specific detail in the licensing basis evaluation to document that they were thoroughly assessed.
The Items identified by the peer review were reviewed by CNS Civil Design Engineering. Additional detail was added to each, as appropriate to document the licensing basis evaluation.
The Items identified by the peer review were reviewed by CNS Civil Design Engineering. Additional detail was added to each, as appropriate to document the licensing basis evaluation.
The bulleted items of Section 1 (Purpose and Approach) of EPRI 1025286 were reviewed and determined to be properly assessed by the Peer Review Team. The conclusion of the peer review was that the CNS NTTF 2.3 seismic walkdown effort has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the in-process review of the SWEL development and the walkdowns have been addressed satisfactorily.
The bulleted items of Section 1 (Purpose and Approach) of EPRI 1025286 were reviewed and determined to be properly assessed by the Peer Review Team. The conclusion of the peer review was that the CNS NTTF 2.3 seismic walkdown effort has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the in-process review of the SWEL development and the walkdowns have been addressed satisfactorily.
Line 1,972: Line 3,001:
==REFERENCES:==
==REFERENCES:==
: 1) CNS-1465.00-00-0007, Rev. 2, Seismic Design Bases Specification Document
: 1) CNS-1465.00-00-0007, Rev. 2, Seismic Design Bases Specification Document
: 2) UFSAR Section 3.2.1 Seismic Classification
: 2)
UFSAR Section 3.2.1 Seismic Classification
: 3) UFSAR Section 2.5.1.2 Site Geology
: 3) UFSAR Section 2.5.1.2 Site Geology
: 4) UFSAR Sections 2.5.2.6, 2.5.2.7 SSE/OBE
: 4)
: 5) UFSAR Section 3.7 Seismic Design
UFSAR Sections 2.5.2.6, 2.5.2.7 SSE/OBE
: 6) CNC-1206.03-00-0202, Rev. 0, 10CFR50.54(f) Rec. 2.3 Fukushima Seismic Walkdowns
: 5)
: 7) EPRI Report 1025286, Dated June 2012, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 B) Catawba Response to GL 88-20, Individual Plant Examination of External Events (IPEEE) Submittal, dated June 21, 1994, D.L. Rehn to NRC.
UFSAR Section 3.7 Seismic Design
: 9) CNC-1 535.00-00-0006, Rev. 0, Seismic Hazard Curve Sensitivity for the Catawba IPEEE.
: 6)
CNC-1206.03-00-0202, Rev. 0, 10CFR50.54(f) Rec. 2.3 Fukushima Seismic Walkdowns
: 7)
EPRI Report 1025286, Dated June 2012, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 B) Catawba Response to GL 88-20, Individual Plant Examination of External Events (IPEEE) Submittal, dated June 21, 1994, D.L. Rehn to NRC.
: 9)
CNC-1 535.00-00-0006, Rev. 0, Seismic Hazard Curve Sensitivity for the Catawba IPEEE.
: 10) CNC-1 535.00-00-0005, Rev. 3, Seismic Capacity Evaluations for IPEEE and EPRI Margins Study.
: 10) CNC-1 535.00-00-0005, Rev. 3, Seismic Capacity Evaluations for IPEEE and EPRI Margins Study.
: 11) Equipment Deficiencies Identified During the 1994 IPEEE Seismic Walkdowns - (See Ref 8 Table 3-3).
: 11)
Equipment Deficiencies Identified During the 1994 IPEEE Seismic Walkdowns - (See Ref 8 Table 3-3).


Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

Latest revision as of 07:47, 11 January 2025

Response to NRC Request for Information Pursuant to Title 10 Code of Federal Regulations 50.54(f) Regarding Seismic Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-Ichi Accident
ML13162A092
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 03/28/2013
From: Henderson K
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13162A092 (166)
v • d • e


Text

DukeKELVIN HENDERSON Catawba Nuclear Station MSite Vice President Carolinas Duke Energy Carolinas, LLC 4800 Concord Rd.

York, SC 29745 803-701-4251 SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED March 28, 2013 10 CFR 50.54(f)

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

Subject:

Duke Energy Carolina, LLC (Duke Energy)

Catawba Nuclear Station (CNS), Unit 1 Docket Nos. 50-413 Renewed License Nos. NPF-35 Response to NRC Request for Information Pursuant to Title 10 Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident.

Reference:

1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(o Regarding Recommendations 2.1, 2.3, and 9,3 of the Near-Term Task Force Review of Insights form the Fukushima Dai-lchi Accident, dated March 12, 2012
2. EPRI Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012
3. NRC Letter, Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, "Seismic Walkdown Guidance", dated May 31, 2012
4. Duke Energy's 180-Day Response to March 12, 2012, Request for Information Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights for the Fukushima Dai-Ichi Accident SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED www.duke-energy.com ron

SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission March 28, 2012 Page 2 On March 12, 2012, the NRC staff issued Reference 1. On November 27, 2012, Duke Energy responded to the request and submitted the Unit 1 and Unit 2 Seismic Walkdown Reports for the accessible areas of the plant. In the response, Duke Energy also committed to provide an updated report for those inaccessible areas within 90 days of the completion of the Unit 1 refueling outage. An electronic copy of the Unit 1 report is attached which documents the inspection results. Attachments 1A through 6A of the Unit 1 report are unchanged, but are included for completeness. Attachments 7A and 8A of the report are new and reflect the inaccessible area inspection results for Unit 1. A of the report contains information that Duke Energy is requesting the NRC withhold from public disclosure in accordance with the requirements of 10 CFR 2.390(d)(1). In accordance with NRC Regulatory Issue Summary 2005-26, an affidavit is not required for security-sensitive information withheld under 10 CFR 2.390(d)(1). A separate uncontrolled electronic copy has been provided within this letter that does not include Attachment 5.

This letter contains no new regulatory commitments.

Should you have any questions concerning this letter, or require additional information, please contact Phil Barrett at (803) 701-4138.

I declare under penalty of perjury that the foregoing is true and correct. Executed March 28, 2013.

Respectfully submitted, Kelvin Henderson Enclosure SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED

j -

.A 4t SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission March 28, 2012 Page 3 xc:

V.M. McCree, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 Eric J. Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13-H16M 11555 Rockville Pike Rockville, MD 20852-2738 J.H. Thompson, Project Manager U.S. Regulatory Commission One White Flint North, Mailstop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto NRC Senior Resident Catawba Nuclear Station Document Control Desk (Electronic Disk)

U.S. Nuclear Regulatory Commission Washington, DC 20555-001 Justin Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453 SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED

CNC-1206.03-00-0203 Rev 0 A Page 1 of 36 Page 1 of 36 Unit I SWEL - 1 "Base List" The Catawba Unit 1 SWEL - 1 "base list" is a copy of the original IPEEE list for Unit 1, as recorded in Calculation CNC-1535.00-00-0005, rev. 0.

A copy is provided as Attachment 1.

SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission March 28, 2012 Page 5 ENCLOSURE SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED

CNC-1206.03-00-0203 Rev 0 A Page 1 of36 Page 1 of 36 Unit I SWEL - 1 "Base List" The Catawba Unit 1 SWEL-1 "base list" is a copy of the original IPEEE list for Unit 1, as recorded in Calculation CNC-1535.00-00-0005, rev. 0. A copy is provided as Attachment 1.

CNC-1206.03-00-0203 Rev 0 A Page 2 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1 535.00-00-0005 Rev. 0 sht I of Lt Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study By: *J, 13.*

612L[t Ck. By:

JT Page 2 of 36 PROBLEM STATEMENT:

NRC Generic Letter 88-20 requests nuclear plant licensees to perform Individual Plant Examinations for Extrernal Events (IPEEE) for several topics including seismic events. NUREG 1407 identifies acceptable methods for performing the Seismic IPEEE. The purpose of the seismic examination is to review the seismic margin of selected plant structures, components, and Iquipment for seismic vulnerabilities using a review level seismic event of

/0.30g peak ground acceleration. A seismic margir) assessment was already done of CNS Unit 2 for an EPRI trial plant review.yin 1986 and 1987. It used the criteria of EPRI NP-6041 and was documented in EPRI NP-6359 (see the reference list below). The method selected for the Catawba Seismic IPEEE consists of the EPRI Seismic Margins Methodology and the existing Catawba Probabilistic Risk Asse9!ment (PRA) along with the enhancements outlined in NUREG-1407, Use is made of work already done in the EPRI trial plant seismic margin assessment. Walkdown and evaluation documentation from that assessment is included along.with more recent walkdown and evaluation documentation in the attachments to this /

calculation. Walkdo-wns also serve the purpose of helping to validate the seismic portions of the Catawba PRA. The Seismic Review Team (SRT) for the walkdowns consisted of W.M. Hogan, D.A. Kaul, J.T.Gruber, and W.B/

Shoemaker. All are registered professional engineers. The SRT for the earlier seismic margin assessment consisted of D.R. Kulla, W. B. /

Shoemaker, B.F. Henley, and R.D. Campbell. All are registered professional engineers. No training was available at the time the earlier work was done.

R. D. Campbell is a recognized industry expert in the area of seismic evaluations of nuclear power plants. He was the primary author of the EPRI seismic margins criteria document, Reference (1).

The Catawba Seismic Margins Assessment as documented in Reference (3) is recognized throughout the industry and is referenced in NUREG 1407. Given the standards available at the time each of the two portions of the seismic review was done, the Seismic Review Team meets the requirements and intent of EPRI NP-6041 and NUREG 1407.

This calculation and its attachments provide the documentation jor the seismic walkdown and evaluation for the CNS Seismic IPEEE. /

The Safe Shutdown Equipment Lists (components to cover on walkdowns) were provided by P. T. Farish in a letter of March 11, 1993, file no. CN-9 1

535.00 (copy in attachment to this catc.).

CNC-1206.03-00-0203 Rev 0 A Page 3 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535.00-00-0005 Rev. 0 sht 2 of Lf Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study BCk.

By: *7~

QA CONDITION Page 3 of 36 This calculation is non QA Condition /

DESIGN / ANALYTICAL METHOD This calcuation performs no design, and it is not used to support any design 7 basis designs. In the calculation attachments information gathered in seismic margin walkdowns is compiled, and evaluations are performed using the methods given in EPRI NP-6041.

Any other method that may be used are documented where such methods are used in the attachments.

APPLICABLE CODES AND STANDARDS EPRI NP-6041 and NUREG-1 407 are used. Where other codes and

/

standards are recommended by these two publications such codes and standards are referenced.

DESIGN INPUTS Evaluation inputs are identified as applicable in the attachments.

FSAR The FSAR does not address IPEEE. This calculation has no impact on the 7' FSAR.

ASSUMPTIONS Structure and equipment qualification data in design documents were used to help evaluate seismic margin. Other assumptions are identified as applicable in the attachments.

.:!. *,:I W;

[.) IJ IJ IJ

-, I...

ýI. 1::: 1"1 ;::'

CNC-1206.03-00-0203 Rev 0 A Page 4 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535,00-00-0005 Rev. 0 sht 3 of.1 Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study By: tA)gJXAý i.ý

(,(2-Iqf Ck. By:*fZ

,/(;/4~

SOURCES OF INFORMATION / REFERENCES (1) NUREG 1407, "Procedural and Submittal Guidance for the Individual Plant Examination of External Events," June, 1911 (2) EPRI NP 6041, "A Methodology for Assessment of Nuclear Plant Seismic Margin," Rev 0, Oct., 1988, Rev. 1,Aug., 1991 (3)EPRI NP-6359, Seismic Margin Assessment Margin Assessment of the Catawba Nuclear Station," April, 1989 (4)P. T. Farish letter to W. B. Shoemaker of March 11, 1993, IPEEE Safe Shutdown Equipment Lists, file CN-1535.00.

Other sources of information and references are sited where appropriate in the attachments.

CALCULATION The results of the walkdowns, evaluations and other backup information are provided in the attachments.

CONCLUSION No significant areas of plant vulnerability were identified. Modification of the Diesel Generator Battery racks (and addition of spacers) was implemented largely as a result of the EPRI trial plant seismic margin assessment (NSMs CN-1 1161 and CN-20540). One or two other minor improvements were made to the station which slightly reduced seismic vulnerabilties. These improvements are noted where appropriate in the

/

calculation attachments.

Page 4 of 36

CNC-1 206.03-00-0203 Rev 0 lA Page 5 of 36

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8%1 #qPAp)E Page 5 of 36

CNC-1206.03-00-0203 Rev 0 A Page 6 of 36 A V T ArC 14VA FNi T-TO Cti.c 1;3s-oc2-)OOC00; PA 6-C-~ 1 CS I~js FF -

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""I Page 6 of 36

CNC-1 206.03-00-0203 Rev 0 A Page 7 of 36 A-TLA t~vvc-N T I

Tro C t) r 133 SO-,

00- 0

-0 0S§ pAG.E 2.

March 11, 1993 Catawba Nuclear Station Re:

Catawba Nuclear Station, Units 1 & 2 Individual Plant Examination - External Events Safe Shutdown Equipment Lists File: CN-1535.00 Please find attached for your use and information a copy of the safe shutdown equipment lists (SSELs) for Unit I as well as the lists of equipment required for the containment performance evaluation of Units I & 2.

Questions regarding the equipment selection may be directed to me at 382-6755.

P. T. Parish, Engineer Nu clear Engineering - Severe Accident Analysis Nuclear Services Attachment cc:

P.M. Abraham R. W. McAuley H. D. Brewer R. C. Bucy (CNS)

R. S. Bondurant (CNS)

J. H. Knuti (CNS)

Central Records EC 10A NSIO (M AA D IA-T~

I rot.-L-ow4 iN G-kj%. is I (1 311T Page 7 of 36

CNC-1206.03-00-0203 Rev 0 A Page 8 of 36 AT-T I1 O CN(

7 (

0~.

~3.

o -

C) 0 s 44 PA.-&E 3

GENERIC LETTER 88-20; SUPPLEMENT 4 INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT I

.)

Prepared By Reviewed By Approved By

..._/

3111Zý3

° 9

Page 8 of 36

CNC-1206.03-00-0203 Rev 0 A Page 9 of 36 Ei 004 GENERIC LETTER 88-20; SUPPLEMENT 4 INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT I In the NRC policy statement on severe accidents, issued on August 8, 1985, the Commission concluded that existing nuclear power plants pose no undue risks to the public health and safety.

The Commission also concluded that systematic plant-specific examinations are beneficial in identifying plant vulnerabilities to severe accidents that could be fixed with low cost improvements. The staff issued Generic Letter 88-20 on 11/23/88, requesting that each Licensee conduct an individual plant examination (IPE) for internally initiated events. To satisfy the IPE requirement, Duke utilized the Catawba PRA report, which included the analysis of internal and external events. The Catawba IPE was submitted to the NRC in September 1992.

Supplement 4 to G.L. 88-20 was issued on 6/28/91 and requested a systematic, individual plant examination for severe accidents initiated by external events (IPEEE). Among the events to be assessed was the plant's response to a seismic event.

There are two acceptable methods for responding to the IPEEE, as identified in NUREG-1407 and EPRI NP-6041, Rev. 1; (1) use of the seismic PRA and (2) the Seismic Margin Assessment S

(SMA) method. In addition, NUREG-1407 includes an assessment to identify vulnerabilitles that involve the early failure of containment functions.

In order to determine the seismic acceptability of the plant, walkdowns will be conducted of the various systems required to achieve safe shutdown and maintain containment performance, To this end, a listing of the various components and structures required for safe shutdown and containment performance will be prepared for use by the Catawba Seismic Review Team (SRI) to carry out the plant walkdowns.

The purpose of this document is to identify the various components and structures required for safe shutdown and containment performance after a seismic event and to detail the selection process employed. The listings generated herein will be used by the Catawba SRT in conducting walkdowns to assess the plant's response to a seismic event.

Methods of 1PEEE Resolati~o~

As mentioned above, there are two acceptable methods for IPEEE resolution. These are detailed below, Final selection of the components and structures are based upon these two methods.

9

. I.,,

Page 9 of 36

CNC-1206.03-00-0203 Rev 0 A Page 10 of 36 Catawba has previously generated a seismic PRA as part of its formal PRA report.

Iidtially, seismic hazard curves for peak acceleration were developed (Catawba currently uses hazard curves developed by EPRI using the Seismicity Owners Group methodology for seismic hazards analysis of nuclear power plant Sites in the central and eastern U.S.).

Next, an event tree was generated to characterize the plant response to a seismic event.

With the subsequent core melt sequences identified, a fault tree was then produced to determine the failure sequences (cut sets) of interest. Using previously estimated fragilitics of key components and structures, the conditional probability of failure as a function of ground acceleration was ascertained.

Finally, a resulting set of dominant accident sequences was developed based upon a convolution of the fragilities, fault tree cut sets, and the seismic hazard curve.

The plant component fragilities used in the analysis were calculated by Structural Mechanics Associates.

The walkdowns by the SRT will complement these fragility estimates.

Thus, the seismic PRA method primarily identifies areas of seismic vulnerability by determining a set of dominant accident seluences and components.

2)

SMA bMthd-The SMA method, as described in NP-6041, defines an earthquake level (or a 'margin')

above the design basis earthquake for which the ability to safely shut the plant down can be demonstrated with high confidence in a cost-effective manner.

It is the NRC staffs judgment that the use of a 0.3g review level earthquake for most nuclear plant sites in the central and eastern U.S. would serve to meet the objectives of the IPEEE. The SMA process is based upon a systems "success path" approach that defines and evaluates the capacity of the components required to bring the plant to a safe shutdown condition (either hot or cold) for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (further assumptions used in the analysis are given in the "Basic Assumptions" section of this report). Since several possible success paths may exist, cognizant engineering and operations personnel are needed for proper selection,.

Once chosen, a walkdown of the selected shutdown paths will determine whether the components and structures identified therein are in compliance with the 'seismic margin'.

Furthermore, the NRC defines Catawba as a 'focused-scope' plant requiring an evaluation of low-seismic-ruggedness relays in the shutdown paths. The relays associated with the shutdown paths will be reviewed against a 'bad actors' list (from EPRI NP-7148SL). The related power supply cabinets will also be reviewed for seismic ruggedness.

Method of Selection for Safe Shutdown Eo5unm.n A review of the current Catawba PRA report was conducted to determine those components and systems considered as important to safe plant shutdown from a PRA perspective. The review included the Seismic fault tree (PRA report Section 3.2) and the Small-Break LOCA fault tree (PRA report Section 2.3) along with their respective transfers to other system trees.

The individual shutdown system fault trees were also reviewed to obtain other key components, Page 10 of 36

CNC-1 206.03-00-0203 Rev 0 A Page 11 of 36 power sources, etc. The components and stnictures of concern to the seismic PRA are so noted in the resulting equipment lists.

U 1 Next, in accordance with NP-6041, two success paths (primary & alternate) per the SMA approach were selected to perform each of the following shutdown functions:

o Reactivity Control o

RCS Pressure and Inventory Control o

Decay Heat Removal The Catawba Unit 2 SMA pilot study (EPR NIP-6359) was also used as a guide for success path selection, All the primary and alternate 'front-liue' systems required to execute each shutdown function are shown in Table I along with their 'support' systems.

With the proper front-line and supporting systems identified, engineers traced out the success paths on the respective system flow diagrams, relying upon their knowledge and experience.

Individual components and instruments were noted and listed.

Several components were designated as "pressure boundary integrity only" which signifies components which ame part of the pressure boundary but do not perform an active function.

Method of Selection for Con..tainrnent PerfoQMna.

The equipment and structures necessary to support containment performance were selected per guidance from NUREG-1407.

The PRA report was used to generate an initial listing and included the Seismic Containment Safeguards fault tree (PRA report Section 3.2) and the Containment Safeguards fault tree (PRA report Chapter 4) along with their respective transfers to other system trees. The individual system fault trees (including the Containment Isolation fault tree) were also reviewed to obtain other key components, power sources, etc.

Following their preparation, the initial equipment lists were reviewed by licensed operators for sound selection methodology and conformance to existing procedures. Other systems engineers were included as necessary to complete the review. The resulting comments were incorporated and the finalized safe shutdown and containment performance equipment lists are given in Tables 2 through 5. A diskette with these tables will be given to the SRT so that walkdown information can be added per reporting requirements.

1)

Per IPEEE guidelines, the plant undergoes a seismic event and loses off-site power. A small-break LOCA (I in,) is also incurred. The plant must maintain shutdown status for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2)

Plant shutdown is conducted using cold leg injection. For a small-break LOCA. the cold leg accumulators are excluded since this is a relatively controlled shutdown situation.

9

,:1.

Page 11 of 36

CNC-1206.03-00-0203 Rev 0 A Page 12 of 36 Li

.0

3)

Assume initial suction is from the RWST (rather than through the Volume Control Tank) until RCS temperature and pressure are low enough to initiate RHR.

4)

Aswrie manual valves, check valves, non-active relief valves, and piping are seismically rugged-

5)

The analysis is based upon bringing the plant to hot shutdown with the option of going to cold shutdown with RHR.

6)

Instead of the normal Containment Spray System (NS), the RHR Auxiliary Spray headers will be used to mitigate any containment pressure increases.

References

1)

NUREG-1407; "Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities"

2)

EPRI NP-6041, Rev. 1; "A Methodology for Assessment of Nuclear Power Plant Seismic Margin"

3)

EPRI NP-7148SL; "Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality"

4)

EPRI NP-6359; "Seismic Margin Assessment o' the Catawba Nuclear Station"

5)

Catawba Flow Diagrams -

CN-1553-1.0, -1.1; NC System CN-1554--1.0, -1.1, -1.2. -1.5, -1.6, -1.7; NV System CN-1557 (2557)-l.0; VX System CN-1557-2.0; VZ System CN-1561 series: ND System CN-1562-l.0, -1.1, -1.2, -1.3; NI System CN-1563-1.0; NS System CN-1571-1,0; FW System CN-1573-1.0, -1.1, -2.0, -2.1, -2.2; KCSystem CN-1574-1.0, -1.,-1.2, -1.4, -2.0, -2.1,-2.4, -2.5; RN System CN-1577-1.0,-1.1,4-.2,-1.3; VASystem CN-1578-1,0, -1.1, -1.2, -1.4, -1.5; VC System CN-1578-2,x series; YCSystem CN-1579-1.0; VD System CN-1591-I,I; CFSystem CN-1592 series; CA System CN-1593-1.0, -1.1, -1.2, 1..3, -1.7 series; SM, SV Systems CN-1609 series; D/G Support Systems (KD, LD, FD, VC, VN)

6)

Catawba Final Safety Analysis Report (FSAR); dated 10/91

7)

Catawba Probabilistic Risk Assessment Report; dated 9/22/92

'Attachment 1

Page 12 of 36

CNC-1206.03-00-0203 Rev 0 A Page 13 of 36

@I Ges Several individuals were involved with the preparation and review of this report; however, those primarily responsible are listed below:

Name

)YorkAM Paul T. Farish William B. Shoemaker Russell C. Bucy R. Stuart Bondurant John -i, Knuti Nuclear Services / Nuclear Engineering Catawba / Civil Engineering Catawba / Mechanical Engineering Catawba / Electrical Engineering Catawba / Operations 19 Page 13 of 36

CNC-1206.03-00-0203 Rev 0 A Page 14 of 36 TABLE 1-609 LISTING OF PRIMARY & ALTERNATE StHUTDOWN PATHS 0

Reactivity Control -

Primary Path:

Front-line System - Reactor Protection System (control rod insertion / Reactor Trip Breakers)

Support Systems - None Alternate Path:

Front-line Systems - NV, NI (emergency boration flowpath), FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC. Vz, YC o

RCS Pressure and Inventory Control-

)

Primary Path:

Front-line Systems & Components - CA (Motor-Driven Pumps), SO PORVs, Main Steam Isolation Valves, SG Safety Relief Valves, NV, NI (not required for inventory control for 1" SBLOCA). FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, Vz, YC Alternate Path:

Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg accumulators for PORV actuation)

Support Systems - RN, KC, Diesel Generators & supporting systems *; VA, VC, VZ, YC The following systems are assumed to be used for all DIG support functions:

FD, KD, LD, VD, VG, VN Page 14 of 36

CNC-1206.03-00-0203 Rev 0 A Page 15 of 36 TABLE I (cont.)-

~h

~ (3 d

LISTING OF PRIMARY & ALTERNATE SHUTDOWN PATHS 0

Decay Heat Removal -

Primary Path:

Front-line Systems & Components - CA (Motor-Driven Pumps). SG PORVs, ND (if cold shutdown is needed)

Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, VZ, YC Alternate Path:

Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg acctnulators for PORV actuation), ND (if cold shutdown is needed)

Support Systems - RN, KC, VC, Vz, YC Diesel Generators & supporting systems *, VA, The following systems are assumed to be used for all DIG support functions:

FD, KD, LD, VD, VG, VN IJ IJ 1:.1 1.)

Page 15 of 36

CNC-1206.03-00-0203 Rev 0 Attachment IA Page 16 of 36 TABLE 2.

I rC.I.I MECHANICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN

('B' tro!n components are shown In parentheses. A detailed wolkdown of these components is not

)

9 necessary if the 'B' train configuration Is simllar to he 'A train. I

-_Line Included In Press. bndry.

CA SYSTEM COMPONENTS Size (in.)

Seismic PRA Integrity onty AO 6 A56

-(40)

____4 AOV 1CA60 (44) 4 MOV ICA7A 10 x___

MOV ICAllA (9B) 10 X

MOV ICA15A (18B) 6 MOV 1CA,54B (38A) 4 x

X_

MOV 1CA58A (42B) 4 MOV 1CA62A (468) 4 MOV 1CA66B (50A) 4 x

MOV ICA174

.8 x

MOV 1CA175 8

._X_,._

AUTO.-RECIRC. VALVE 1CA27 (32)

]

AUTO.-RECIRC. VALVE 1CA20 TURBINE DRIVEN PUMP 1 X

TDP TURBINE LUBE OIL COOLER MOTOR DRIVEN PUMP IA (18)

UPPER SURGE TANK X

CONDENSER HOTWELL x

CONDENSATE STORAGE TANK x

The following Unit I components were included on the Unit 2 walkdown:

MOV ICAB5B MOV ICA116A HYDRAULIC VLV 1CF33 HYDRAULIC VLV 1CF42 HYDRAULIC VLV 1CF51 HYDRAULIC VLV ICF6*

I DIESEL GENERATOR AND SUPPORTING Line Included In Press. bndry.

COMPONENTS Size (In.)

Seismic PRA lntegrity on.y__

DIESEL GENERATOR IA (1B) x SOLENOID VALVE 1 FD22 (62) 2 FD D/G FUEL OIL FILTER 1A 01B)

-i Page 1 IJ I..

Page 16 of 36

CNC-1206.03-00-0 2 0 3 Rev 0 A Page 17 of 36 fil oi-l TABLE 2 -

DIESEL GENERATOR AND SUPPORTING

.*U--_ ine Included In Press. bndry.,

COMPONENTS (con1.)

Inize (in.)

mic PRA FD DIG FUEL OIL DAY TANK IA(1B) 013).

I-D D/G FUEL OIL PUMP STRAINER IA (1 B)

FD D/G FUEL OIL STORAGE TANKS 1A1, 1A2 (111, 1B2)

FD DI.G_ FUEL OIL PUMP IA (0B)

-I.

KD D/G ENGINE JACKET WATER COOLER 1A (IB)

KD D/G ENGINE JACKET WATER CIRC. PUMP IA (18)

/

KD D/G ENGINE JACKET WATER STANDPIPE IA (18)

AOVTLD4 (34) 3 AOV ILD27 (57)

__3_

SOLENOID VLV ILD122 (123) 2 x

LD D/G GOVERNOR LUBE OIL COOLER LD D/G LUBE OIL FILTER )A (B)>

LD D/G LUBE OIL COOLER IA (I)

LD D/G LUBE OIL STRAINER IAI (1BI) & 1A2 (iB2)

UDD/G LUBE OILSUMP TANK IA (11)

LG D/G ENGINE LUBE OIL PUMP IA (1 B)

VD ELECTRO-HYDRAUUC DAMPER IDSF-D-1 (7)

VD EI.ECTRO-HYDRAULIC DAMPER 1DSF-D-2 (8)

VD ELECTRO-HYDRAULIC DAMPER 1DSF-D-3 (9)

VD ELECTRO-HYDRAUUC DAMPER 1DSF-D-4 (10) ))-_

DIESEL BLDG. VENTILATION FANS I A1, 1 A2 (0B1,81 B2)._

SOLENOID VALVE 1 VG25 (69)

SOLENOID VALVE IVG26 (70) 3 SOLENOID VALVE IVG27 (71) 3 SOLENOID VALVE 1VG28 (72) 3 VG D/G ENGINE STARTING AIR TANKS 1AI, IA2 (181, 132)

VN D/G ENGINE ITWAKE AIR FILTERS IA 1, 1A2 (1B I 182)

VN D/G ENGINE INTAKE AIR SILENCERS IAl. 1A2 (11. 1B2)

VN D/G ENGINE EXHAUSTSILENCER WA, IA2 (181, 182)

YVN D/G ENGINE AFTERCOOLERS ]A, 1A2 (111, 1152)

VN D/G ENGINE TURBO-CHARGER WA, 1A2 (113, 1132)

.. _Une I tncluded In Press. bndry. __

FW SYSTEM COMPONENTS Size (In.),

Seismic PRA Integrity only MOV lIA (32B) 4...

MOV 1FW27A (558) 12 MOV 1FW33A (498)_

2 2 RWST (REFUEUNG WATER STORAGE TANK)

X

)1 9

Page 2 ID 1-1

...:it 1 : I.1 "

Page 17 of 36

CNC-1206.03-00-0203 Rev 0 A Page 18 of 36

~I &i:~

TABLE 2 -

KC SSE

_OPNN Une Included In Pross. bndry.

SYSTEM COMPONENTS Size (in.)

Seismic PRA I integrity only q

AqV 1KC57A (828) 12 AOV 1KCD29 2

MOV IEKCA (2B) 20 MOV 1KC3A (18B) 10 MOV IKCSOA (53B) 20 MOV 1KC51A (548) 4

-X MOV IKC56A (818) 16 MOV IKC230A (2280) 8 MOV IKCC37A (40B) 6 KC HX JA (IB)

KC PUMPS IAI, 1A2 (IBI, 8112)

KC SURGE TANK IA (IB)

RHR PUMP MECH. SEAL HX IA (I6) B).

KC PUMPS IA, 1A2 (I81, 182) MOTOR COOLERS '

AUX. SHUTDOWN PANEL AREA AIR COND. UNIT 1 A X

CA MOTOR-DRIVEN PUMP IA (18) MOTOR COOLER RHR PUMP MOTOR COOLER IA (.18)

NI PUMP MOTOR COOLER IA (1B)

X NI PUMP BEARING OIL COOLER IA (1 B)

X NS PUMP MOTOR COOLER IA (IB)

XI_

NV PUMP MOTOR COOLER IA (18)

NV PUMP MOTOR SPEED REDUCER OIL COOLER I A (I B)

Une

.Included in Press. bndry.

NC SYSTEM COMPONENTS '_'size (In.)

Seismic PRA integrity only SAFE*Y REUEF VALVE 1NC 1 6

X SAFETY REUEF VALVE I NC2 6

X SAFETY REUEF VALVE 1NC3 6

X PZR PORV INC32B

-'3 X

PZR PORV 1NC34A 3

X PZR PORV INC36B 3

X MOV INC31B 3

MOV INC33A 3

MOV 1NC35B 3

PZR HEATER BANK A (B).....

Page 3 Page 18 of 36

CNC-1206.03-00-0203 Rev 0 A Page 19 of 36 TABLE 2 -

.,i ('14

_Line I

Included In Press. bndy._

ND SYSTEM COMPONENTS

{]Size (In.)j Seismtc PR.A._itgiyol A

w AOV 1ND26 (60) 8 AOV IND27 (61) 8 MOV INDIB (36B) 12 MOV IND2A (37A) 12 MOV 1ND24A (588) 2 MOV IND25A (598) 2 MOV I ND32A (65B) 2 x.....

MOV IND90 (9?)

2 ND PUMP IA (18)

NDHX 1A (1B) x MOV IND28A was included on the Unit 2 walkdown.

Une Included In Press. bndry, NI SYSTEM COMPONENTS Size (in.)

Seismic PRA Integrity only_

AOV INi50 (72) 1 AOV 1NI56 1

x AOV 1Ni57 0.75 X

AOV 1N8 0.75 x

AOV 1N161 (84) 1 AOV I N167 I

X AOV IN168 0.75 X

AOV IN169 0.75 X

AOV IN178 I

X AOV 1N179 0.75 X

AOV INf80 0.75 X

AOV IN190 I

X AOV IN191 0.75 X

AOV 1NI92 0.75 X

AOV 1N1391 (3.93) 0.75 X

AOV.N1392 (394) 0.75 X

MOV I*N19A (OB) 4 MOV 1N154A (76A) 10 X

MOV 1N165B (88B) 10 X

MOV iNIIOOB 8

X MOV INII03A (135B) 6 X

MOV 1NI115A,(144A) 2 X

MOV INII18A (150B) 4,_....

. 4 X

MOV 1NI120B 0,75 MOV INI!21A (052B) 4 X

4MOV 1N136B 8

MOV 1NI147B_

2 X

Page 4

)" l30], ()

1.

Page 19 of 36

CNC-1 206.03-00-0203 Rev 0 A Page 20 of 36 TABLE 2 -

~Ji C1~

__M______ULine Included in "Press. bndry.

NI SYSTEM COMPONENTS (cont.)

Size (in.)

Seismic PiRA It--grIty only OV

-1N173A (IB)8 78B)

MOV lN1183B 12 1

MOV ]N1185A (184B)

__10 MOV 1N1332A 6

MOV 1NI333B' 6

MOV 1N1334B (136B) 6 Ni PUMP IA (1B)

MOV 1NI438A (NIIROGEN BACKUP TO PZR PORV) 1 X

MOV 1NW4398 (NITROGEN BACKUP TO PZR PORV) 1 X

Une Included In

-- Press. bndry.

NV SYSTEM COMPONENTS Size (in.)

Seismic PRA Integrity only AOV 1NV52A 2

x AOV 1NV63B 2

X AOV INV74A 2

X AOV 1NV85B 2

X AOV INV101A 0.75 x

AOV 1 NV294 3

X AOV 1NV309 3

X MOV 1NV44A 2

X MOV 1NV55A 2

X MOV INV66A 2

x MOV 1NV77A.

2 X

MOV 1NVB9A (918) 4 x

MOV INVI88A (1898) 4 x

MOV 1 NV203A (20213) 2 x

MOV 1NV252A (253B) 8 MOV 1NV312A (3148) 3 CENTRIFUGAL CHARGING PUMP IA (1 B)

SEAL WATER INJECTION FILTER IA (1B)

Une Included In Press. bndry.,

RN SYSTEM COMPONENTS Size (In.)

Seismic PRA lntegrity only AOV 1RN291 (351) 12 MOV IRNIA (5A) 48 AOOV IRN2B (6B) 48 OV 1RN30A (408) 4 i

Page5 Cý D 1" I"!

.J:

Page 20 of 36

CNC-1 206.03-00-0203 Rev 0 A Page 21 of 36 U Ci GG TABLE 2 -

)

Line Included In Press. bndry_.

RN SYSTEM COMPONENTS (cont.)

Size (in.)

Seismic PRA integrity only MOV IRN36A (3713) 4 MOV IRN48B (47A) 20 MOV 1RN49A (501) 20 MOV IRN5IA (528) 20 MOV I RN54A (53B) 42 MOV 1RN63A (58B)

__42 MOV 1RN144A (2258) 18 X

MOV 1RN148A (2298) 18 X

MOV IRN232A (2928) 10 MOV IRN287A (347B) 20 X

MOV IRN843B (57A) 42 MOV 1RN846A (848B) 10 MOV 1RNB47A (849B) 10 RN STRAINER 1A (1B)

RN PUMP IA (IB) UPPER BEARING HX RN PUMP LUBE INJECTION SIMPLEX STRAINER A (B)

SNSWP INTAKE (video available)

II The following Unit I components and structures were included on the Unit 2 walkdown:

MOV IRN3A

[

MOV 1RN4B i

MOV IRN11A MOV 1 RN20B MOV I RN28A MOV IRN38B MOV 1 RN67A MOV IRN69B MOV 1RN250A [train B' valve (ORN310B) NOT reviewed]

ELECTROHYDRAULIC VLV 1RN244A ELECTROHYDRAULIC VLV IRN304B RN PUMP IA RN PUMP IB.Bi RN PUMP INTAKE PIT A BARS, DEBRIS SCREEN, & STRUCTURE R4j PUMP INTAKE PIT B BARS, DEBRIS SCREEN, & STRUCTURE STANDBY NUCLEAR SERVICE WATER POND Une Included in Press. bndry.

SA, SM, SV SYSTEM COMPONENTS Size (In.)

Seismic PRA Integrlty only AOV I SA2 (5) 4 AOV 1SM86 2

X AOV 1SM87

__2_

X Page 6

.... t*!;

':i*

1 :

I; Page 21 of 36

CNC-1206.03-00-0203 Rev 0 A Page 22 of 36 CI?

TABLE 2 -

_ Une Included In Press. bndry.

SA, SM, SV SYSTEM COMPONENTS (cont.)

Size (in.)

Seismic PRA Integrity only AOV 1SM88 2

X AOV I SM89 2

X MOV 1SM74B 2

X MOV 1SM75A 2

x MOV 1SM76B 2

X MOV 1SM77A 2

X MSIV ISM i 34 MSIV 1SM3 34 MSIV ISM5 34 MSIV 1SM7 34 MSI BYPASS VLV 1 SM9 3

x MSI BYPASS VLV 1SM1O 3

x MSI BYPASS VLV ISMI 1 3

X MSI BYPASS VLV 1SMJ12 3

_x SG PORV ISV]

6 X

SG PORV ISV7 6

X SG PORV ISV13 6

X SG PORV ISVM9 6

X SG SRV 1SV2 6x 10

_X SG SRV 1SV3 6 x 10 X

SG SRV 1SV4 6x 10 X

SG SRV 1SV5 6x 10 X

SG SRV 1SV6 6x 10 X

SG SRV ISV8 6x 10 X

SG SRV ]SV9 6x 10 X

SG SRV 1SVIO 6x 10 X

SG SRV ISVI I 6x 10 X

SG SRV 1SV12 6x 10 X

SG SRV 1SV14 6x 10 x

SG S1V ISV15 6x 10 X

SG SRV 1SV16 6x 10..

__X SG SRV 1SV17 6x 10 X

SG SRV SV18 6x 10 X

SG SRV 1SV20 6x 10 X

SG SRV ISV21 6 x 10 X

SG SRV 1SV22 6x 10 x

SG SRV 1SV23 6x10 X

SG SRV 1SV24 6x 10 X

MOV 1SV25B 6

X x

MOV 1SV26B 6

X MOV 1SV27A 6

x MOV ISV28A T,

6 x

)

Page 7

.;!ý

.1. ; -, ý, -:

Page 22 of 36

CNC-1206.03-00-0203 Rev 0 A Page 23 of 36 bi.018 TABLE 2 -

)

9 Une Included In Press. bndný.

,VA* SYSTEM COMPONENTS Size ((n.)

Seismic PRA integrity onjy MOV IVA28B(31A) 6 X

MOV 1VA29A (30B) 6 X

AIR-OPERATED DAMPER IABF-D-10 (3)

AIR-OPERATED DAMPER 1ABF-D-12 (5)

C._.

AIR-OPERATED DAMPER 1ABF-D-14 (7)

AIR-OPERATED DAMPER 1AB&.D-1 (3)

ELECTRO-HYDRAUUC DAMPER IABF-D-4 ELECTRO-HYDRAULIC DAMPER 1ABF-D-6 ELECTRO-HYDRAULIC DAMPER 1ABF-D-1 ELECTRO-HYDRAULIC DAMPER IABF-D-13 ELECTRO-HYDRAUUC DAMPER IABF-D-16 ELECTRO-HYDRAUUC DAMPER IABF-D-18 MOISTURE EUMINATOR PRHDS-1A (1B)

AUX. BLDG. FILTER UNIT ABFU-1A (I B)

AUX. BLDG. FAN ABFXF-1A (IB)..

AUX. BLDG, FAN SUPPLY UNIT ABSU-IA (i8)

Line Included in Press. bndry.

VC SYSTEM COMPONENTS Size (In.)

Seismic PRA Jntegrty only MOV IVC5B 24 MOV IVC6A 24 MOV 1VC7B.

4 MOV I VC8A 4

ELECTRO-HYDRAULIC DAMPER ICR-D-2 X

ELECTRO-HYDRAULIC DAMPER tCRA-D-5 ELECTRO-HYDRAULIC DAMPER 1CRA-D-7 CONTROL ROOM AHU 1CR-AHU-1............

PRESSURIZiNG FILTER I CRA-PFT-I.....

PRESSURIZING FILTER FAN 1CRA-PFTF-I CONTROL ROOM AREA AHU 1CRA-AHU-1 SWITCHGEAR ROOM AHU ISGR-AHU-1 (2),

SWITCHGEAR ROOM AHU 1 SGR-AHU-3 (4)

HEATER UNIT ICR-H-I x

HEATER UNIT 1CRA-H-1 x

HEATER UNIT ICRA-H-2 X

HEATER UNIT 1CRA-H-3 x

HEATER UNIT 1CRA-H-4 x

HEATER UNIT 1CRA-H-5 x

HEATER UNIT 1CRA-H-7

=___

x Page 8

,.:I IJ IJ I.)

Page 23 of 36

CNC-1206.03-00-0203 Rev 0 A Page 24 of 36 TABLE 2 -

&1 o iX/(c rj__Included in Press. bndry.

VZ SYSTEM COMPONENTS j

Seismic PRA flntegrit only NUCLEAR SERVICE WATER PUMPHOUSE FAN IA. 2A (1B, 21)

ELECTRO-HYDRAULIC DAMPERS A3A, A4A (A3B, A4B)

ELECTRO-HYDRAULIC DAMPERS B3A, B4A (B3B, 848)

Une Included In Pres. bndry.v YC SYSTEM COMPONENTS Stzo (in.)

Seismic PRA Integrity only MOV 1YC77A.(121B)

-2 X

ELECTRO-HYDRAUUC VLV 1YC26 (100) 2.5 ELECTRO-HYDRAULIC VLV IYC58 (15D) 4 ELECTRO-HYDRAULIC VLV 1YC 196 (208) 3 ELECTRO-HYDRAUUC VLV 1YC203 (214) 3 ELECTRO-HYDRAUUC VLV 1YC264 (274) 3 ELECTRO-HYDRAUUC VLV 1YC270 (281) 3 CONTROL ROOM AREA CHILLED WATER PUMP 1CRA-CHWP-1 YC CHILLER ICRA-C-1.

YC COMPRESSION TANK ICRA-CT MISC. CIVIL STRUCTURES INSIDE DOGHOUSE x

D/G BUILDING X

REACTOR COOLANT PUMP SUPPORTS X

CONTAINMENT INTERNAL STRUCTURE X

CONTROL ROD DRIVE MECHANISM X

REACTOR BUILDING X

AUXILIARY BUILDING SHEAR WALLS X

)

9 Page 9 Page 24 of 36

CNC-1206.03-00-0203 Rev 0 A Page 25 of 36 TABLE 3 -

020 ELECTRICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN I

il CB' train components are shown In parentheses. A detailed walkdown of these components IS not necessary if the 'B' train configuration Is similar to the 'A' train.)

)

9

___Included In SUPPORT FOR CA SYSTEM Seismic PRA 4160V AC SWITCHGEAR IETA (OEMB) x 600V AC MCC )EMXC x

600VAC MCC IEMXI (IEMXB) x.._

600VAC MCC IEMXK (IEMXB)

X 600V AC MCC IEMXL

__x 600V AC LOAD CENTER 1ELXA X_

600V AC LOAD CENTER IELXC x

600V AC LOAD CENTER 1 ELXD X

125V DC PANELBOARD ]EPA (OEPM) x 125V DC DISTRIBUTION CENTER IEDA X

125V DC DISiTRIUTION CENTER IEDE (QEDF) x 12V AC PANELBOARD I ERPA (I ERPD)_

X 125V DC VITAL I&C BATTERY CHARGER IEBA 125V DC VITAL I&C BATTERY CHARGER IECA i

126V DC VITAL &C BATTERY CHARGER IECS---

125V DC VITAL I&C BATTERY CHARGER 1EDS 48V DC ESFAS TRAIN A (B) SUPPLY POWER INSTR. LOOP CONTAINING 1CALL/SV/EP0560 (0400)

INSTR. LOOP CONTAINING 1CALL/SV/EP0600 (0440)

INSTR. LOOP CONTAINING 1CAFE/FT/P 5100 INSIT. LOOP CONTAINING 1 CAFE/FT/P 5110 INSTR. LOOP CONTAINING )CAFE/FT/P 5120

__}__-

INSTR, LOOP CONTAINING 1CAPS5220, 5221, & 5222 (5230, 5231 & 5232)

!NSTR. LOOP CONTAINING 1CFLT/P 5490 (5560)

'"_'l INSTR. LOOP CONTAINING CFLT/P (5550)

INSTR. LOOP CONTAINING 1CFLT/P 5501 (5551)

INSTR. LOOP CONTAINING ICFLT/P 5510 & P 5511 (5570)

INSTR. LOOP CONTAINING ICFLT/P 5520 & 1 CAP 5521 (5590 & 5591)

INSTR. LOOP CONTAINING ]CFLT/P5530 (5580)

INSTR. LOOP CONTAINING ICFLT/P 5540 (5600)

INSTR. LOOP CONTAINING 1 CFLT56 10 &P 5612 (5630 & 5632) i INSTR. LOOP CONTAINING ICFLT5620 & P 5622 (5640 & 5642)

POST-ACC(DENT MONITORING INSTRUMENTAT70N Page I D ID ID)")

Page 25 of 36

CNC-1206.03-00-0203 Rev 0 A Page 26 of 36 TABLE 3 -

w1 021

)

9 I__

!Included in SUPPORT FOR DIESEL GENERATORS______

Seismic PRA..

125V DC BATTERY/ PRACK 1

_X INVERTERS X

BATTERY 1 DGBA (1 DGBB) AND CHARGERS X

D/G CONTROL PANEL X

DIESEL ENGINE CONTROL PANEL X

D/G NEUTRAL GROUND PANEL x

AUCTIONEERING DIODE ASSEMBLY EVDA (EVDB)

__x LOAD SEQUENCER

_X INbTR. LOOP CONTAINING 1 FDFT5O00; 1 FDLT5003; & 1 FDPS5001 thru 5004 (5~5163;

& 5160-

  • )j fl-

__5

)

INSTR, LOOP CONTAINING I FDFT6010; 1FDLT5013; & iFDPS5011 i*hru 5014 (5170;5173; &6170- 5174)

.[

iIL__-.

INSTR. LOOP CONTAINING IFDLT5060; 1FDPG5061, 5062 (5200; 5201,520'2)

INSTR. LOOP CONTAINING I1LDPT/PG5 140; ILDPS5141; ILDPS/PT5I42; ILDPT5143;

& I.LDPT5144.

(5170;5171; 5172, 5173;&5174) l INSTR. LOOP CONTAINING LDPG/PS5160 & ILDPS5300 (5190 & 5310)

INSM. LOOP CONTAINING 1 LDIT/P200 1 1--

INSTR, LOOP CONTAINING 1 LOPT/PS/PG5220: 1 LDPT/PS5230; & 1 LDPS5500 (5240, 5250. -)

I_____

INSTR. LOOP CONTAINING 1 LDTT/PS5270.

INSTR. LOOP CONTAINING 1LDPT/PS5400 (5420)

INSTR. LOOP CONTAINING 1LDPG5410 (5430) 1 I

INSTR. LOOP CONTAINING 1VGPS/PG5-500 & 1VGPS5101, 5102 (5250 & 525).5252)

INSTR. LOOP CONTAINING IVGPS/PG5120 & 1 VGPS5121, 5122 (5270 & 5271. 5272)

Included in SUPPORT FOR FW SYSTEM i

Seismic PRA 600V AC MCC 1EMXA (1EMXB)

INSTR. LOOP CONTAINING 1FWLT/P 5000 INSTR. LOOP CONTAINING IFWLT/P 5010i INSTR, LOOP CONTAINING 1 FWLT/P 5020 INSTR. LOOP CONTAINING IFWLT/P 5130 FOR KC SYSTEMIncluded In SUPPORT FOR KC SYSTEM Seismic PRA 4160V AC SWITCHGEAR 1ETA (1ETB)

I x

600V AC MCC iEMXA (1EMXJ) x*

00V AC MCC 1EMXI (IEMXJ)

___x__X 600V AC LOAD CONTROL CENTER 1ELXA (1ELXB)

X 125V DC PANELBOARD ]EPA (1EPB)

_x 125V DC DISTRIBUTION CENTER 1 EDE

+

-X Page 2 Page 26 of 36

CNC-1206.03-00-0203 Rev 0 A Page 27 of 36

/

TABLE 3 -

N 1 022

_Included In SUPPORT FOR KC SYSTEM (CONT.)

_Seism.c PRA INSTR LOOP CONTAINING 1KCFE/Fr/PS/P 5530 (5540)

INSTR. LOOP CONTAINING 1KCLS/LT/P 5630 (5640)

Included In SUPPORT FOR NC SYSTEM Seismic PRA 6900V AC SWITCHGEAR 1TD 4160V AC SWITCHGEAR 1ETB

_x MAIN TRANSFORMED 1 B AND BUS TRANSFORMER 1ATD TRANSFORMER 1 ETXB AUXILIARY POWER TRANSFORMER IT1A AUXILIARY POWER TRANSFORMER IT1B 6WV AC MCC I EMXC x

600V AC MCC 1 EMXD x

600V AC LOAD CENTER 1ELXB X

120V AC PANELBOARD 1ERPA

-_x 120V AC PANELBOARD IERPD X

120V AC VITAL POWER INVERTER tEID 125V DC VITAL I&C SPARE BATTERY CHARGER IEBD 125V DC VITAL I&C SPARE BATTERY CHARGER 1ECD 125V DC VITAL I&C SPARE BATTERY CHARGER IECS 125V DC DISTRIBUTION CENTER 1EDD II INSTR. LOOP CONTAINING 1NCSV/LL0320, 1NCSV0321, & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0340, INCSVO341, & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0360, 1NCSV0361, & RCPS INSTR. LOOP CONTAINING 1NCLT/PT/P 5150

]

[. "L INSTR. LOOP CONTAINING 1NCLT/PT/SS.5160 & 1NCP 5161

[....

INSTR. LOOP CONTAINING I NCLT/PT/P 5170; 1 NCLT/PT/P 517 1 NCP 5173; & INCP 5174 INSTR. LOOP CONTAINING I NCRD/P 5940 I __....

INSTR. LOOP CONTAINING INCRD/P 5970 9

INSTR. LOOP CONTAINING 1 NCRD/P 5960 INADEQUATE CORE COOLING MONITOR

_Included in SUPPORT FOR ND SYSTEM i.__Seismic PRA 4160V AC SWITCHGEAR IETA (1ETB)

____X 600V AC MCC 1EMXA (1EMXJ)__x 600V AC MCC 1EMXC X

600V AC MCC 1EMXD X

600V AC MCC IEMXS (IEMXL) x 125V DC DISTRIBUTION CENTER )EDE (1EDF) x INSTR. LOOP CONTAINING 1NDFE/PG5040 & 1NDPG5041 (5050,5051)

..,I

)

9 Page 3 Attachment I Page 27 of 36

CNC-1206.03-00-0203 Rev 0 A Page 28 of 36 TABLE 3 -

N 023

-Included In SUPPORT FOR NI SYSTEM Seismic PRA 4160V AC SWITCHGEAR 1ETA (1ETB) 1 600V AC MCC 1EMXA (1EMXB) (1EMXJ) xijX 125V DC DISTRIBUTION CENTER IEDE (1EDF)

X INSTR. LOOP CONTAINING INILT/P 5260 INSTR. LOOP CONTAINING INILT/P 5270

_____Included in SUPPORT FOR NV SYSTEM Seismic PRA 4160V AC SW1TCHGEAR IETA (1ETB) x 600V AC MCC 1EMXA x

600V AC MCC 1EMXJ x

600V AC MCC 1EMXL x

125V DC DISTRIBUTION CENTER ]EDE (OEDF)

X 120V DC PANELBOARD I ERPC X

INSTR. LOOP CONTAINING 1NVFE/Fr/CR5120 & I NVFT/CR5121 INSMTR LOOP CONTAINING 1NVFE/FT5130 & 1NVFT5131I INSTR. LOOP CONTAINING 1NVFE/FT/CR5140 & INVFT/CR5141 INSTR. LOOP CONTAINING 1NVFE/FT5150 & 1NVFT5W11 INST.

LOOP CONTAINING INVFE/FT/P 5300 & INVP5301 INSHTR. LOOP CONTAINING INVFE/FT/P 5310 & INVP 5311 INSTR. LOOP CONTAINING 1NVFE/FT/P 5320 & INVP 5321 INSTR. LOOP CONTAINING INVFE/FT/P 5330 & 1NVP 5331 I

INSTR. LOOP CONTAINING 1 NVPT/P 5620 & I NVP 5621 INSTR. LOOP CONTAINING 1 NVFE/FT/P 6080 Included In SUPPORT FOR RN SYSTEM Seismic PRA 4160V AC SWITCHGEAR IETA (IETB) x 600V AC MCC 1EMXA

_X 600V AC MCC IEMXE (IEMXF)

_x 600V AC MCC IEMXG x

600V AC MCC 1EMXJ x

600V AC MCC IEMXO x

600V AC MCC IEMXQ (1EMXR)

X I

600V AC MCC 2EMXH x

600V AC MCC 2EMXP_

x 600V AC LOAD CENTER IELXA x

125V DC DISTRIBUTION CENTER IEDE (IEDF)

X 120V DC PANELBOARD IERPA xi_

INSTR. LOOP CONTAINING ORNLT/P 7350 9 INSTR. LOOP CONTAINING ORNLT/P 7380 INSTR. LOOP CONTAINING ORNTT/P 8130 Page 4 Page 28 of 36

CNC-1 206.03-00-0203 Rev 0 A Page 29 of 36 TABLE 3 -

U 024

,J

)

Included In,

SUPPORT FOR RN SYSTEM (CONT,)_

Seismic PRA INSTR. LOOP CONTAINING 1RNTE/IT/P 5000 (5010)

INSTR. LOOP CONTAINING 1 RNPT/PS/P 5020 (5030)

INSTR. LOOP CONTAINING 1RNFE/FT/P 5800 (5850)

INSTR. LOOP CONTAINING 1RNFE/FT/P 5930 (5980)

INSTR. LOOP CONTAINING 1RNFE/FT/P 6290 (6340)

INSTR. LOOP CONTAINING IRNLT/P 7400 (7370)

INSTR. LOOP CONTAINING 1 PNTE/T/..P 7460 (7430)

INSTR. LOOP CONTAINING I RNPT/PS/P 7480 (7470)

INSTR. LOOP CONTAINING IRNFE/FT/P 7520 (75 1O) iNSTR. LOOP CONTAINING 2RNLT/P 7400 (7370 Included In REACTOR PROTECTION SYSTEM Seismic PRA REACTOR TRIP BREAKER A (B)

REACTOR TRIP BYPASS BREAKER A (B)

Included In SUPPORT FOR SA, SM. SV SYSTEMS Seismfc PRA 600V AC MCC IEMXC x

600V AC MCC IEMXD x

600V AC MCC IEMXK x

600V AC MCC IEMXL X

125V DC PANELBOARD 1EPA X

125V DC PANELBOARD IEPD x

120V AC PANELBOARD IERPA x

120V AC PANELBOARD IERPD x

INSTR. LOOP CONTAINING ISALL/SVX02O & ISALL/SVOO2i INSTR. LOOP CONTAINING ISMLLOO)0 thru 0015 & ISMSV00lOOfhru 0013 INSTR. LOOP CONTAINING ISMLL0030 Ihnu 0035 & ISMSVOO30 fhru 0033 INSTR. LOOP CONTAINING ISMLLOU5O thru 0055 & ISMSVO050 thru 0053 tNSTR. LOOP CONTAINING ISMLL0070 thru 0075 & 1SMSVO070 thru 0073 iNSTR. LOOP CONTAINING ISMLL/SV/MLOO90 & ISVLL/SVOO91 INSTR. LOOP CONTAINING ISMLL/SV/MLO0O0

& ISVLL/SVO110 1 INSTR. LOOP CONTAINING ISMLL/SV/ML0O1

& ISVLL/SVO 111 INSTR. LOOP CONTAINING 1SMLL/SV/ML0120 & I.SVLL/SV0121 INSTR. LOOP CONTAINING ISMFE/FT/P 5000 & 1SMFT/P 5010 INSTR. LOOP CONTAINING ISMFE/FT/P 5020 & ISMFT/P 5030 INSTR. LOOP CONTAINING 1SMFE/FT/P 5040 & 1SMFT/P 5050 INSTR. LOOP CONTAINING I SMFE/FT/P 5060 & I SMFT/P 5070 INSTR. LOOP CONTAINING ISMPT/CR/P 6080 1 INSTR. LOOP CONTAINING.ISMPT/P 5090 M_

I INSTR, LOOP CONTAINING 1SMPT/P 5T00 Page 5 Page 29 of 36

CNC-1206.03-00-0203 Rev 0 A Page 30 of 36 TABLE 3 -

1 025

-Included In SUPPORT FOR SA, SM, SV SYSTEMS (cont.)

Seismic PRA INSTR. LOOP CONTAINING ISMPT/P 5110 INSTR. LOOP CONTAINING 1SMPT/P 5120 & ISMCR5800 D_

INSTR. LOOP CONTAINING 1SMPT/P 5130 INSTR. LOOP CONTAINING 1SMPT/P 5140 INSTR. LOOP CONTAINING ISMPT/P 5150 INSTR. LOOP CONTAINING 1SMPT/P 5160 i

INSTR. LOOP CONTAINING ISMPT/P 5170 INSTR, LOOP CONTAINING ISMPT/P 5180 INSTR. LOOP CONTAINING 1SMP1/P 5190 INSTR. LOOP CONTAINING ISVEP/MLO010; & 1SVSVOOI 1 thru 0017 INSTR. LOOP CONTAINING ISVEP/MLOO70; & ISVSV071 thru 0077 INSTR. LOOP CONTAINING 1ISVEP/MLO 130; & ISVSVOI31 thru 0137 INSTR. LOOP CONTAINING 1SVEP/ML0190; & 1SVSVO191 thru 0197 Included In

___Seismic PRA SOLID STATE PROTECTION SYSTEM

_x Included In SUPPORT FOR VA SYSTEM Seismic PRA POWER SUPPLY FOR VA SYSTEM INSTR. LOOP CONTAINING 1VAPT/P 5000 (5020)

X INSTR. LOOP CONTAINING 1 VAFE/P 5280 Included in SUPPORT FOR VC SYSTEM Seismic PRA 4160V AC SWIWCHGEAR IETA (2ETB) 60DV AC MCC 1EMXG (2EMXH) 120V AC PANELBOARD IEKPG (2EKPH) 600/120V AC TRANSFORMER IEKTG INSTR, LOOP CONTAINING IVCPT/P 5160 x

/_

Included in SUPPORT FOR YC SYSTEM Seismic PRA 600V AC MCC 1EMXG INSTR. LOOP CONTAINING 0YCFE/ff/P 5000 (5010)

Page 6 Page 30 of 36

CNC-1206.03-00-0203 Rev 0 A Page 31 of 36 TABLE 4 -

N 026 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNITI IPEEE WALKDOWN CONTAINMENT ISOLATION VALVES Penetr.

l

_Valve Position AND PENETRATIONS No.

Valve No.

Line Size (in.) Norm Fall I Shut.

Post UPPER COMPARTMENr PURGE INLET M456 1VPIB 24 C

C C

C UPPER COMPARTMENT PURGE INLET M456 1VP2A' 24 CC C

C UPPER COMPARTMENT PURGE INLET WM432 1VP3B 24 C

C C

C UPPER COMPARTMENT PURGE INLET M432 I VP4A 24 C

C C

C LOWER COMPARTMENT PURGE INLET M357 1 VP6B 24 I._

C C

C C

LOWER COMPARTMENT PURGE INLET M357 lVPTA 24 C

C C

C LOWER COMPARTMENT PURGE INLET M434 IVP8B 24 LC C

C C

LOWER COMPARTMENT PURGE INLET M434 I VP9A 24 C

C C

C CONT. PURGE EXHAUST M368 IVP10A 24 C

C C

C CONT. PURGE EXHAUST M368 1VP11B 24 C

C C

C CONT. PURGE EXHAUST M433 1VP12A 24 C

C C

C CONT. PURGE EXHAUST M433 IVP13B 24 C

C C

C CONT. PURGE EXHAUST M119 1VPISA 24 C

C C

C CONT. PURGE EXHAUST MI 19 1VP16B 24 LC C

C C

INCORE INSTR. ROOM PURGE IN M213 IVP17A 12 C

C C

C INCORE INSTR. ROOM PURGE IN M213 1VP18B 12 LC C

C C

)WRE INSTR. ROOM PURGE OUT M140 IVP19A 12 1C C

C C

RE INSTR. ROOM PURGE OUT M140 1VP20B 12 LC C

C C

CONT. AIR RELEASE M386 1VQ2A 4

C C

C C

CONT. AIR RELEASE M386 1VQ3B 4

C Al C

C CONT. AIR ADDITION M204 1VQ]5B 4

C At C

C CONT. AIR ADDITION M204 1VQ16A 4

C C

C C

CONT. HYDROGEN PURGE OUTLET LINE M346 1VY17A 4

C Al C

C CONT. HYDROGEN PURGE OUTLET LINE M346 WV18B 4

C Al C

C VENT. UNIT CONDENSATE DRAIN HDR.

M221 IWL867A 4

0 Al 0

C VENT. UNIT CONDENSATE DRAIN HDR.

M221 1WL869B 4

0 A-Ad 0

C EQUIPMENT HATCH 240 C

_C C

PERSONNEL HATCH

.... ___115 C_**_C C

LOWER PERSONNEL AIR LOCK C100 UPPER PERSONNEL AIR LOCK C300......

PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)

PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 6XOV AC MCC I EMXC: (I EMXD)_______

600V AC MCC 1 EMXK (I1EMXB)____

60XV AC MCC I MXM____

600V AC MCC IMXO 600V AC MCC 1MXR p

I!-

Page 1 j2 Page 31 of 36

CNC-1206.03-00-0203 Rev 0 A Page 32 of 36 TABLE 4 -

EI 0

I?

.Una..

Included In Press. bndry.

U&

HYDROGEN MITIGATION SYSTEM bize (In.)

Seismic PRA integrry only GLOW PLUG IGNITERS 600V AC MCC IEMXI (QEMXB) 600/V20V ACTRANSFORMER XFMR0013 (14)

ICE BASKETS & DOORS__

Une Included in Press. bndry.

NS SYSTEM Size (in.)

Seismic PRA Integrity only_..

NS PUMP 1A (1B)

NS HX IA (18),!

MOV 1NS18A 12 MOV 1NS29A (32A) 8 4160V AC SWITCHGEAR 1ETA (0ETB)

AC MCC IEMXA

.I"DCPANELBOARD )EIDE (IEDF]

Une Included in Press, bndry, VX SYSTEM Size (in.)

Seismic PRA Integrity only AIR-OP. DAMPER 1ARF-D-5 (-8)

AIR-OP. DAMPER 1ARF-D-6 (-9)

AIR-OP. DAMPER 1ARF-D-7 (-10)

MOTOR-OP. DAMPER IARF-D-2 (-4)

I CONTAINMENT AIR RETURN FAN I A ()I B--

600V AC MCC I EMXK ( EMXL) 120V AC PANELBOARD 1EKPI (IEKPB) 9 Page 2 Page 32 of 36

CNC-1206.03-00-0203 Rev 0 A Page 33 of 36 TABLE 5 -

~I 02s CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2 IPEEE WALKDOWN CONTAINMENT ISOLATION VALVES

Penetr, Valve Posliiorn AND PENETRATIONS No.

Volve No.

Une Size (in.) Norm Foil Shut.

Post UPPER COMPARTMENT PURGE INLET M

-4 2VPIB

.24 C

C C

c-UPPER COMPARTMENT PURGE INLET M456 2VP2A 24 c

C C

C UPPER COMPARTMENT PURGE INLET M432 2VP3B 24 C

C C

C UPPER COMPARTMENT PURGE INLET M432 2VP4A 24 C

-- C C__

C LOWER COMPARTMENT PURGE INLET M357 2VP6B 24 LC C

C C

LOWER COMPARTMENT PURGE INLET M357 2VP7A 24 LC C

C C

LOWER COMPARTMENT PURGE INLET M434 2VP8B 24

-LC 6

C C

LOWER COMPARTMENT PURGE INLET M434 2VPgA 24 IC C

C C

CONT. PURGE EXHAUST M434 2VP10A O

24 C

C C

C CONT. PURGE EXHAUST M368 2VPIOB 24 C

C C

C CONT. PURGE EXHAUST M433 2VP) 2A 24 C

C C

C CONT. PURGE EXHAUST M433 2VP13B 24 C

CC C

-CONT. PURGE EXHAUST Ml19 2VPI5A 24 C

C C

C CONT. PURGE EXHAUST M1 19 2VP16B 24 LC C

C C

INCORE INSTR. ROOM PURGE IN M213 2VPI7A 12 C

C C

C INCORE INSTR. ROOM PURGE IN M213 2VP18B 12 LC C

C C

-1IRE INSTR. ROOM PURGE OUT M14D 2VPI9A 12 C

C

  • C C

RE INSTR. ROOM PURGE OUT M140 2VP20B 12 LC C

C-C CONT. AIR RELEASE M386 2VQ2A 4

C C

C C

CONT. AIR RELEASE M386 2VQ3B 1

4 C

Al C

C CONT. AIR ADDMON M204 2VQ 158 4

C Al C C CONT. AIR ADDmON M204 I

2VQ16A 4

C C

C C

CONT. HYDROGEN PURGE OUTLET LINE M346 2w17A 4

C Al C

C CONT. HYDROGEN PURGE OUTLET LINE M346 2VY18B 4

C Al C

C VENT. UNIT CONDENSATE DRAIN HDR.

M221 2WL867A 4

0 Al 0

C VENrT. UNIT CONDENSATE DRAIN HDR.

M221 2WL869B 4

0 Al 0

C EQUIPMENT HATCH 240 C

_C-PERSONNEL HATCH 115 C

C C

LOWER PERSONNEL AIR LOCK j C 10 UPPER PERSONNEL AIR LOCK PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)

PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC (2EMXD) 60OV AC MCC 2EMXK (2EMXB) 600 VAC MCC 2MXM 600 VAC MCC 2MXO 600 VAC MCC 2MXR 9

Page 1 D:

Page 33 of 36

CNC-1206.03-00-0203 Rev 0 A Page 34 of 36 TAgLE 5 -

O 29 line Included In Press. bndry.

_,*" HYDROGEN MITIGATION SYSEM Size (In.)

Seismic PRA integrity only_

GLOW PLUG IGNITERS 600V AC MCC 2EMXI (2EMXB) 600/120V AC TRANSFORMER 2XFMROO] 3 (14)

ICE BASKETS & DOORS Une Included In Press. bndry, NS SYSTEM Size (in,)

Seismic PRA Integrity only" NS PUMP 2A (28)

NS HX 2A (2B)

MOV 2NS18A 12 MOV 2NS29A (32A) 8 4160V AC SWlTCHGEAR 2ETA (2ETB)

"N,' AC MCC 2EMXA DC PANELBOARD 2EDE (2EDF)

Une Included In Press. bndry. :

VX SYSTEM Size (in.)

Seismic PRA integrity only_

AIR-OP. DAMPER 2ARF-D-5 (-8)

AIR-OP. DAMPER 2ARF-D-6 (-9).

AIR-OP. DAMPER 2ARF-D-7 (-10)

MOTOR-OP. DAMPER 2ARF-D-2 (-4)

CONTAINMENT AIR RETURN FAN 2A (28)

'.I

,600V AC MCIC 2EMXK (2EMXL)-

1-20V AC PANELBOARD 2EKPI (2EKPB)

Page 2 D ID 1-ID

11 Page 34 of 36

CNC-1206.03-00-0203 Rev 0 A Page 35 of 36 TABLE 5 -

9 030 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2 A-101D WAII YnfNfWMi7 U I ~ ~ ~ V.

CONTAINMENT ISOLATION VALVES Penelt.

Valve Position_

AND PENETRATIONS No.

Valve No.

Line Size (In.) Norm Fall Shut.

Post UPPER COMPARTMENT PURGE INLET M456 2VP1B 24 C

CC--

UPPER COMPARTMENT PURGE INLET M456 2VP2A 24 C

C C

C UPPER COMPARTMENT PURGE INLET M432 2VP38 24 C

C C

C UPPER COMPARTMENT PURGE INLET M432 2VP4A 24 C

C C

C LOWER COMPARTMENT PURGE INLET M357 2VP6B 24 IC C

C

-C LOWER COMPARTMENT PURGE INLET M357 2VP7A.

24

_C C

C C

LOWER COMPARTMENT PURGE INLET M434 2VP8..

24 LC C

C C

LOWER COMPARTMENT PURGE INLET M434 2VP9A 24 C

C C

C CONT. PURGE EXHAUST M368 2VP1OA 24 C

C C

C CONT. PURGE EXHAUST M368 2VP1 1B 24 C

C CONT. PURGE EXHAUST M433

._2VP12A 24 C

C C

C CONT. PURGE EXHAUST M433 2VP 13B

-C

-(

C C

CONT. PURGE EXHAUST M 119 2VP 15A 24 C

C C

C CONT. PURGE EXHAUST Ml 19 2VP168 24 LC C

C C

INCORE INSTR. ROOM PURGE IN M213 2VP17A 12 C

C C

C INCORE INSTR. ROOM PURGE IN M213 2VPI8 8 12 LC C

C C

INrr'"INSTR. ROOM PURGE OUT M140 2VP19A 12 C

C C

C

  • INSTR. ROOM PURGEOUT

-MM140 2VP20B 12 LC C

C C

CuNI' AIR RELEASE M386 2VQ2A.

4 C

C C

C CONT. AIR RELEASE M386 2VQ38 4

C

-W C

CONT. AIR ADDITION M204 2VQ15B 4

C Al C

C CONT. AIR ADDITION M204 2VQ16A 4

C C

C C

CONT. HYDROGEN PURGE OUTLET LINE M346 2_

7A 4

C Al C

CONT. HYDROGEN PURGE OUTLET LINE M346 2VY8B 4

C I

C VENT. UNIT CONDENSATE DRAIN HDR.

M221 2WL867A 4

0 Al 0

C VENT. UNIT CONDENSATE DRAIN HDR.

M221 2WL8698 1

4 0

Al 0

C EQUIPMENT HATCH to..

240 c

C c PERSONNEL HATCH.......

116 C

G C

LOWER PERSONNEL AIR LOCK C_100 so*...._...

UPPER PERSONNEL AIR LOCK C300 too.

PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)--

PERSONNEL AIR LOCK 208 V LINEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC (2EMXD) 600V AC MCC 2EMXI< C2EMXB)-

600 VAC MCC 2MXM 600 VAC MCC 2MXO 600 VAC MCC 2MXR Y

Page )

ii If

1.

Page 35 of 36

CNC-1206.03-00-0203 Rev 0 A Page 36 of 36 TABLE 5 -

11 031

-t.

Line Includedin MPress.

bndrj.

kDROGEN MITIGATION SYSTEM Size(in.)

Seismic PRA i ntegil*l O

GLOW PLUG IGNITERS 600V AC MCC 2EMXI (2EMXB) 50/120V AC TRANSFORMER 2XFMR0013 (14)

ICE BASKETS & DOORS iUne Included in

-Press. bndy.

NS SYSTEM Size (in.)

Seismic PRA Integrity only.

NIS PUMP2A (2B).

\\JS HX 2A (.2_

8) vlOV 2NS18A 8-12 OV 2NS29A

..A) 8 160V AC SWITCHGEAR 2ETA (2ETB)

JOV AC MCC 2EMXA

ýý- ).

PANELBOARD 2EDE (2EDF) iUne Included in Press. bndy.

VX SYSTEM Size (in.)

Seismic PRA integrity only.

AI R-OP. DAMPER 2ARF-D-5 (-8) aIR-OP. DAM 2ARF-D-6 (-9)

AIR-OP. DAMW.... 2ARF-D-7 (-10)

MOTOP-OP. DAMPER 2ARi-D-2 (-4)

CONTAINMENT AIR RETURN FAN 2A (2B)I

]

600V AC MCC 2EMXK (2EMXL) 120V AC PANELBOARD 2E(PI (2EKPB) 9 Page 2 Page 36 of 36

Sheet I of 4 Status: Y[D No U0 Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 557 Room, Area, DEG 58 RIAD 40 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID INV52A Description IA NC Pump Seal Return Column Line or Other Location Info El 557, 58 deg. Radius 40 ft.

Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y0 NO UO N/A[]

2. Does anchorage of equipment in the area appear to be free of significant YZ No U0 N/AD]

degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YE* NO U[

N/ALl

'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC. INV52A.DOC CNC-1206.03-00-0203 Rev 1 A Page 11 of 105

Sheet 2 of 4 Status: YR NF-I UZ' Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 557

. Room, Area, DEG 58 RAD 40

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is firee of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YZ NO UO N/Al]

YZ ND U1I N/AD YZ ND UO N/AD YE* ND UD: N/AD

8. Have you looked for and found no other seismic conditions that could Y0 ND UD1 adversely affect the safety functions of the equipment in the area?

Near Azimuth 63, radius 30, elevation 563, there is a empty piece of 4" electray hanging almost vertically with very few attachments. This component does not appear to be a seismic threat currently due to its low mass, and lack of sensitive targets below, but it does not appear to be serving any purpose, and it would be a good practice to remove it.

Comments (Additional pages may be added as necessary)

AWC - uNV52A.DOC CNC-1206.03-00-0203 Rev 1 A Page 12 of 105

Sheet 3 of 4 Status: YZ NEI U-Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 557 Room, Area, DEG 58 R_4D 40 Evaluated by: Thomas R Leich,

?--/'

Date:

2

,..r2,3 Ralp11017( F-11MI?~~~A>_Ž_

Date:

2__2 (2 AWC - INV52A.DOC CNC-1206.03-00-0203 Rev 1 A Page 13 of 105

Sheet 4 of 4 Status: YZ N-' UD Area Walk-By Checklist (AWC)

Location: Bldg. CV1 Floor El. 557 Room, Area, DEG 58 RAD 40 71 npty hanging piece of electray. (see 8)

Note:

Note:

Note:

AWC-I NV52A. DOC CNC-1206.03-00-0203 Rev I A Page 14 of 105

_j.

I

Sheet I of 3 Status: YE NI-U-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. INV52A Equip. Class, 7 (AOV)

Equipment Description 1A NC Puma Seal Return Location: Bldg. CV1 Floor El. 557 Room, Area DEG 58 RAD 40 Manufacturer, Model, Etc. (optional but recommended)

Kerotest Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YO NED

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete near the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YE] NE UOE N/AZ YE NE UD-N/AZ YE NE UE N/AE YE NE UE N/AZ YED NEI UE I ntc)r the equipment class 11nac fromt Appendix 13: Classcs of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 15 of 105

Sheet 2 of 3 Status: YZ NE] U]-

Seismic Walkdown Checklist (SWC)

Equipment ID No.

INV52A Equip. Class' 7 (AOV)

Equipment Description IA NC Pump Seal Return Interaction Effects

7. Are soft targets fiee from impact by nearby equipment or structures?

YZ NEI UD N/AO

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ' NEI UI-N/AI]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y[l NI UDI N/AUI YN NO UO Other Adverse Conditions 1I.

Have you looked for and found no other seismic conditions that could YZ NO] UF-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

There is a 2" line that will interact with the supporl steel for 1NV52A, But it is not massive enough to cause any damage. The support steel (Rigid) was originally cut to make room for the 2" line, so this condition was considered in the original design. The 2" line is a VB (Breathing Air) system line, and the interaction point is nol vety far from valve IVB1O. - See photo.

ý,

e,. Z Evaluated by:

., RZe-,'1cXDate:

/

/ -P, (2- ~-

~o IZ.

J CNC-1206.03-00-0203 Rev 1 A Page 16 of 105

Sheet 3 of 3 Status: YZ N[-

UE-Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NV52A Equip. Class1 Equipment Description 1A NC Pump Seal Return Photographs Note: 2" VB line close to steel for 1NV52A.

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 17 of 105

Sheet 1 of 4 Status: YER NM UD Area Walk-By Checklist (AWC)

Location: Bldg. CVJ Floor El. 560 Room, Area' DEG 46 RAD 47 PCHA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID IN154A Description Column Line or Other Location Info C-Leg Accum A Dischg. Isol 46 Deg, Rad 47 Elev 560 I. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y(E ND--

U[D N/AD

2. Does anchorage of equipment in the area appear to be free of significant YO NO UD N/AD degraded conditions?
3. Based on a visual inspection fiorn the floor, do the cable/conduit raceways and 1-VAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YZ ND UD N/AD]

I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC - INI0054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 18 of 105

Sheet 2 of 4 Status: YN NO U7 Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor UL. 560 Room, Area' DEG 46 RAD 47 PCH-IA

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YO ND UD N/AD YN ND UD N/AD YC ND UD N/AD YZ ND U[-D N/AD

8. Have you looked for and found no other seismic conditions that could YO NZ UD adversely affect the safety functions of the equipment in the area?

Found loose locknut on pipe support for 1 WL820. If not corrected, this had potential to allow support to work loose during operation, See comments section.

Comments (Additional pages may be added as necessary)

Some cable trays in area are full but acceptable. Noticed loose locknut on rod supporting I WL820. Wrote Work Request to get it fixed. One small 6" electray has an empty section that is very flexible, but it is not close or heavy enough to interact seismically with other components, AWC-I N10054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 19 of 105

Sheet 3 of 4 Status: Y[* NF U-Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 560 Room, Area1 DEG 46 RAD 47PCHA Evaluated by: Thomas R Leitch

.Date:

__/__________--_

Ravniond C Fung

,7 Date:

2 7 211 2I3 AWC - I NI0054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 20 of 105

Sheet 4 of 4 Status: YZ NF' U[']

Area Walk-By Checklist (AWC)

Location: Bldg. CV1 Floor El. 560 Room, Area, DEG 46 RAD 47 PCHA Note: Full tray with well restrained cables. See Comments.

Note:

Note:

LI~Uo: LUUOO LU*nIUL Uin ra supporting I VVL See Comments.

AWC - I N10054A.DOC CNC-1206.03-00-0203 Rev 1 A Page 21 of 105

Sheet i of 3 Status: Y[

Nn U-Seismic Walkdown Checklist (SWC)

Equipment ID No. INIOO54A Equip. Class, 8 (MOV/SOV)

Equipment Description C-Lee Accum A Discharge Isol.

Location: Bldg. CVI Floor El. 560 Room, Area DEG 46 RAD 47 PCHA Manufacturer, Model, Etc. (optional but recommended)

Westinghouse 09J-2-09 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage I. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YO NO

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YOi NEI UE N/AM YED N[E UL N/AZ

4. Is the anchorage free of visible cracks in the concrete near the anchors?

YE NEI U-N/AO

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YO-NEI UO-N/AN!

YE NE UE IE nter the equipment class name from Appendix B: Classes of E.quipment.

CNC-1206.03-00-0203 Rev 1 A Page 22 of 105

Sheet 2 of 3 Status: YE NEI ULI Seismic Walkdown Checklist (SWC)

Equipment ID No.

1NIO054A Equip. Class, 8 (MOV/SOV)

Equipment Description C-Leg Accum A Discharqe Isol.

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YZ ND UD N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?

YN ND UD N/AD

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YE NDI UD adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

No problems observed, See drawing CN-1041-02 for plan view. Also, see CN-1491-NI.O0-043.

Evaluated by:

7-I-amy s

4?

d,,'YcA

.t-hez Date:

o Z* z o/3.

-1~~'

2.;

ct3

.___j CNC-1206.03-00-0203 Rev 1 A Page 23 of 105

Sheet 3 of 3 Status: Y S[] CRU-Seismic Walkdown Checklist (SWC)

Equipment ID No. 1N0054A Equip. Class' 8 (MOV/SOV)

Equipment Description C-Leg Accum A Discharge Isol.

INOte:

WV104A.

Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 24 of 105

Sheet I of 4 Status: YZ ND-1 UQ1 Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 562 Room, Area' DEG 40 RAD 55 ACLA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID IN1438A Description Column Line or Other Location Info Emer N2 From CLA A to INC-34A Deg 40 Rad 55 ACLA

1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

YZ NO U[] N/All]

2. Does anchorage of equipment in the area appear to be free of significant YN Nil Ut] N/At degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

All cables appear adequately anchored and supported.

YN NEI Ut N/AL

'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC - IN)438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 25 of 105

Sheet 2 of 4 Status: YZI N---] U-Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 562 Room, Area, DEG 40 RAD 55 ACLA

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YNJ NE] U[

N/AD YZ NEI U-N/AD:1 Y[3 ND UD N/AD YN ND UM N/AD

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

YN ND U Comments (Additional pages may be added as necessary)

Some boron deposits were noted on tubing connected to INIPT5050, about 10' above floor, near an elbow. Not a seismic issue, but wrote work request to clean / repair as needed.

AWC - IN1438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 26 of 105

Sheet 3 of 4 Status: YN NF U-Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 562 Room, Area, DEG 40 ]?AD 55 ACLA Evaluated by: Thoas R Leitch 4227-,

Z6 Date:

7__

/;___ n/_,

Ravinond Fzung Date:

Z/z7/- 13 AWC - I N1438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 27 of 105

Sheet 4 of 4 Status: YM N-- U[-

Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 562 Room, Area, DEG 40 RAD 55 ACLA P

Note: Boron deposits on tube attached to 1N!PT5050, See Comments.

Note:

Note:

AWC-IN1438A.DOC CNC-1206.03-00-0203 Rev 1 A Page 28 of 105

Sheet I of 3 Status: YZ Nf-- U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 1N1438A Equip. Class' 8 (MOV/SOV)

Equipment Description Emer N2 From CLA A to 1NC-34A Location: Bldg. CV1 Floor El. 562 Room, Area DEG 40 RAD 55 ACLA Manufacturer, Model, Etc. (optional but recommended)

Kerotest 09J-510 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage I. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YE-NO

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YD NE UED N/A0 YD NEI UEI N/AS

4. Is the anchorage free of visible cracks in the concrete near the anchors?

YE] NEi U[3 N/AZ

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YEJ NEK UV1 N/AO YZ NEI U-I Enter the equipment class name from Appendix B: Classes of Equipment.

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Sheet 2 of 3 Status: YZ N-- UEZ Seismic Walkdown Checklist (SWC)

Equipment ID No.

1N1438A Equip. Class' 8 (MOV/SOV)

Equipment Description Emer N2 From CLA A to INC-34A Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YIZ NEI UD N/ADI

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UD N/AD and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YE NDI UD N/ADl YZ NEI UE-Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YED NDI UDJ adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference CN-149"1-NI102 Evaluated by: 7-Xomnao. 9 LeYe~A 7/-,i~.~

Date:

/2//1/3*/ Z N

1ZAY'4('6 (Ii.b f"_- /_j r-[

/ y 2 ~ C)//;

4 ~ / ~

CNC-1206.03-00-0203 Rev 1 A Page 30 of 105

Sheet 3 of 3 Status: YZ NR-1 Uf']

Seismic Walkdown Checklist (SWC)

Equipment ID No. 1N1438A Equip. Class' 8 (MOV/SOV)

Equipment Description Erner N2 From CLA A to 1NC-34A Photographs Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 31 of 105

Sheet I of 4 Status: YS ND UD Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 567 Room, Areal DEG 176 RAD 50 -Room FA'BC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID IND2A Description Column Line or Other Location Info ND Pump 1 A Suction From LOOP B Deg 176 Rad 50 I. Does anchorage of equipment in the area appear to be fiee of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y2 ND UD N/AD

2. Does anchorage of equipment in the area appear to be free of significant YZ ND UD-N/AD]

degraded conditions?

3. Based on a visual inspection friom the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

There are two cables that run from 1ND37A and go thru an electray marked 440722. This electray has missing or loose fasteners that need resecurement to existing unistrut to restore compliance with the electrical mounting spec. Also the cables in the tray need inspection and reattachment of tray tie wires in a few locations. The condition as found is capable of performing its design function, because the cable connections are still intact and not currently in a position that will cause their integrity to be compromised. A work request has been generated requesting repair to install/replace the fastener as necessary to restore compliance with the spec.

YD N[

UD N/AD I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC-IND2A.DOC CNC-1206.03-00-0203 Rev 1 A Page 32 of 105

Sheet 2 of 4 Status: YZ N[D UD Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 567 Room, Area, DEG 176 RAD 50 -Room FNBC

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YN NI Ui-I N/AD YZ ND U[D N/AD]

YZ ND UO N/AD YZ ND UO N/AD

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

YZ NDI Un Comments (Additional pages may be added as necessary)

See item 3 above. Similar condition found on valve IND2A is described in SWC for that component.

Repair called for in item 3 above was completed on 12/11/2012 per work order 02070453.

AWC-I ND2A.DOC CNC-1206.03-00-0203 Rev 1 A Page 33 of 105

Sheet 3 of 4 Status: YZ NE] U[]l Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 567 Room, Area' DEG 176 R4D 50 -Room FNBC Evaluated by: Thomas R Leilch Date:

2e'/- 3 Tl cn6 }

V AWC-I ND2A.DOC CNC-1206.03-00-0203 Rev 1 A Page 34 of 105

Sheet 4 of 4 Status: YZ NM U[-I Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 567 Room, Area' DEG 176 RAID 50 -Room FNBC Phol Note:

Note:

Note:

AWC-I ND2A.DOC CNC-1206.03-00-0203 Rev 1 A PFa2ge35 of 105

Sheet I of 4 Status: Y¥ N-- U-Seismic Walkdown Checklist (SWC)

Equipment ID No. IND2A Equip. Class' 8 (MOV/SOV)

Equipment Description ND Pump 1A Suction from LOOP B Location: Bldg. CVI Floor El. 567 Room, Area DEG 176 RAD 50 -RM FNBC Manufacturer, Model, Etc. (optional but recommended)

Borg Warner 09J-201 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchora2e

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YO NZ

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete near the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YE NEI U[

N/AZ YE NE-) U-N/AZ YO N-UEi N/AZ YE NEI UE N/AN Y9 NO Un I Enter the equipment class name from Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 36 of 105

Sheet 2 of 4 Status: Y[D ND UD Seismic Walkdown Checklist (SWC)

Equipment ID No. 1ND2A Equip. Class, 8 (MOV/SOVJ Equipment Description ND Pump IA Suction from LOOP B Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YE NED UI N/ADI

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID ND UD-I N/ADI and masonry block walls not like]y to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?

1 0. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y[l NDI UD[ N/A[D YZ NEI UEI Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YNI ND UD adversely affect the safety functions of the equipment?

There are Nuclear Safety Related cables that run from the valve operator then thru an electray and into a junction box. The box was originally fastened to a piece of unistrut that goes to an embedment in the wall. These fasteners have come loose. As a result the electray is also loose, and the cables would be the support for the box if it tried to fall off the unistrut.

Comments (Additional pages may be added as necessary)

See item 11. The box weighs less than 20# and the cables all have metal jackets that are robust and undamaged. A work request was written to repair these items before the end of the outage, but the condition as found was judged capable of performing its design function. (supply of power to the valve operator). Repair was completed on 12/11/2012 per work order 02070468.

CNC-1206.03-00-0203 Rev 1 A Page 37 of 105

Sheet 3 of 4 Status: YZ N[-] UD-Seismic Walkdown Checklist (SWC)

Equipment ID No. IND2A Equip. Class' 8 (MOV/SOV)

Equipment Description ND Pump IA Suction from LOOP B Evaluated by:

-s Date:

i/27/,z/z z.

  • .Jb r0

'-,2,&/3 CNC-1206.03-00-0203 Rev I A Page 38 of 105

Sheet 4 of 4 Status: Y[

NE] UD-Seismic Walkdown Checklist (SWC)

Equipment ID No. IND2A Equip. Class, 8 (MOV/SOV)

Equipment Description ND Putmp 1A Suction from LOOP B Note: Box needing reattachment to unistrut.

Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 39 of 105

Sheet I of 4 Status: YZ N[] U0 Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID Description INDIB ND Pump IA Suction from Lp B Column Line or Other Location Info DEG 176 Rad 25 El 568 I. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y0 NE UD N/AD

2. Does anchorage of equipment in the area appear to be free of significant YN ND U-N/AD degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YE NO UO N/AD I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC-INDIB.DOC CNC-1206.03-00-0203 Rev 1 A Page 40 of 105

Sheet 2 of 4 Status: YN NEI U]

Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC

4. Does it appear that the area is free of potentially adverse seismic spatial YZ N[

UD N/A[

interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YZ Ni7 U[I-N/AD YZ NO UI N/AD Y[

NED UJ[

N/AD1

8. Have you looked for and found no other seismic conditions that could Y[D N[D UDM adversely affect the safety functions of the equipment in the area?

Noted some small tubing that may have been disturbed from original position. Condition is fine, no kinks or tight bends noted, seismic function is maintained.

Comments (Additional pages may be added as necessary)

Temporary lead shielding appears to be well secured in place.

AWC-IND]B.DOC CNC-1206.03-00-0203 Rev 1 A Page 41 of 105

Sheet 3 of 4 Status: YZ NM UD Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Evaluated by: Thomas R Leitch Date:

Z12 7/z/--

Rciwvnond Funs Date:

-7 AWC-I NDIB.DOC CNC-1206.03-00-0203 Rev 1 A Page 42 of 105 44

Sheet 4 of 4 Status-YZ ND]U tJ-Area Walk-By Checklist (AWC)

Location: Bldg. CV1 Floor El. 568 Room, Area, DEG 176 RAD 25 -Room LC Pho Note:

Note:

Note:

AWC-INDIB.DOC CNC-1206.03-00-0203 Rev 1 A Page 43 of 105

Sheet I of 3 Status: YN NEI U-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NDIB Equip. Class, 8 (MOVISOV)

Equipment Description ND Pump 1A Suction from LOOP B Location: Bldg. CV1 Floor El. 568 Room, Area DEG 176 RAD 25

-Room LC Manufacturer, Model, Etc. (optional but recommended)

Borg Warner 09J-201 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorae I. Is the anchorage configuration verification required (i.e., is the item one YE No of the 50% of SWEL items requiring such verification)?

2..s the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YEI NE UlE N/AZ YE[ NE UD N/AZ

4. Is the anchorage free of visible cracks in the concrete near the anchors?

YE NEI UE-N/A[D

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage fiee of potentially adverse seismic conditions?

YE NEI UE[

NWAN YN NE U-E Enter the cquipmenl class name from Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 44 of 105

Sheet 2 of 3 Status: Y[N Nn-] Ul-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. INDIB Equip. Class' 8 (MOV/SOV)

Equipment Description ND Pump 1A Suction from LOOP B Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YU NO UL-] N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ N[D UEL N/AEl and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of lpotentially adverse seismic interaction effects?

Y[E N[-I U0 N/A[D Y19 NE UE3 Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ NW UD adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Congested area. Radiation Shielding blocked direct view of piping. All items going to the valve looked secure. Ref CN-1491-ND.O0-003.

Evaluated by: Thomas R Leitch ID Date:

/,2Z/,,,2-/Z..

CNC-1206.03-00-0203 Rev 1 A Page 45 of 105

--- 4

Sheet 3 of 3 Status: Y[

NF-U-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. tNDIB Equip. Class, 8 (MOV/SOV)

Equipment Description ND Pump IA Suction from LOOP B Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 46 of 105

Sheet I of 4 Status: YN NF U[.

Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 635 Room, AreaI DEG 105 RAD R37 - Top Of PZR Cavit, Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID INC34A INC32B INC36B Description PZRPORV PZR PORV PZR PORV Column Line or Other Location Info Deg 105 Rad37 El 635 Deg 107 Rad 38 El 635 Deg 101 Rad37 El 635

1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y9 N(: U(:] N/AEZ)

2. Does anchorage of equipment in the area appear to be fiee of significant Y,

NZ) UDI N/Ac.

degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YO N-- UED N/A[Z I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC - I NC4A.DOC CNC-1206.03-00-0203 Rev 1 A Page 47 of 105

Sheet 2 of 4 Status: YZ NM UD Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 635 Room, Area' DEG 105 RAD R37-Ton of PZR Cavity

4. Does it appear that the area is free of potentially adverse seismic spatial YO NO U-N/A[9 interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

No Tiles or lighting

5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is fl'ee of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YZ ND UD NJAO YZ ND UD N/AD YO NO UD N/AD

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

YZ No UD Comments (Additional pages may be added as necessary)

Area is very congested, but system clearances are maintained, and all anchorage, cabling, and tubing appears in good condition and properly supported.

AWC - INC34A.DOC CNC-1206.03-00-0203 Rev 1 A Page 48 of 105

Sheet 3 of 4 Status: YM ND--

U[D Area Walk-By Checklist (AWC)

Location: Bldg. CV1 Floor El. 635 Room, AreaI DEG 105 RAD R37-Top of PZR Ca'ity Evaluated by: Thomas R Leitch "7/

Date:

'/2 "b/-

Ravmond Fvn~

iýW Date:2 j AWC - I NC34A.DOC CNC-1206.03-00-0203 Rev 1 A Page 49 of 105

Sheet 4 of 4 Status: YE N-] UM-]

Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 635 Room, Area, DEG 105 RAD R37 - Top of PZR Cavity Photographs Note:

AWC-INC34ADOC CNC-1206.03-00-0203 Rev 1 A Page 50 of 105

Sheet I of 3 Status: YZ ND-UD--

Seismic Walkdown Checklist (SWC)

Equipment ID No. INC34A Equip. Class, Equipment Description PZR PORV Location: Bldg. CV1 Floor El. 635 Room, Area DEG 105 RAD R37-Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)

CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YED NZ

2. Is the anchorage fiee of bent, broken, missing or loose hardware?
3. Is the anchorage fiee of corrosion that is more than mild surface oxidation?
4. ]s the anchorage free of visible cracks in the concrete near the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YE] NED UE] N/A[]

Y0 NE] UD N/AZ YE] NEI UtD N/AZ YE] NED UE] N/AZ YM NE] UE Enler the equipment class name from Appendix 13: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 51 of 105

Sheet 2 of 3 Status: Y[

NEI U-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. INC34A Equip. Class' Equipment Description PZR PORV Interaction Effects

7. Are sofi targets free from impact by nearby equipment or structures?

YZ NDI U0 N/A[]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN ND-UD] N/AD and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y0 NDI UD-N/AD YZ NED Un Other Adverse Conditions 1I.

Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

YE NEIUn Comments.(Additional pages may be added as necessary)

This component is removed/rebuilt on a regular schedule. Also, ref drawing CN-1491-07.00-30.

Evaluated by: ;

-7"* -

, /, l Date:

/ LŽ3 Z7kZ/.

fj 2 3 2o(Z-~

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Sheet 3 of 3 Status: YV N[- Ul-I Seismic Walkdown Checklist (SWC)

Equipment ED No. 1NC34A Equip. Class' 7 (AOV)

Equipment Description PZR PORV Photo ra hA Note: INC34A Note:

Note:

Note:

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Sheet 3 of 3 Status: YN NDI U[-D Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NC32B Equip. Class, 7 (AOV)

Equipment Description PZR PORV Location: Bldg. CV1 Floor El. 635 Room, Area DEG 107 RAD R38 - Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)

CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage I. Is the anchorage configuration verification required (i.e., is the item one YO No of the 50% of SWEL items requiring such verification)?

Line mounted item.

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free ofcorrosion that is more than mild surface oxidation?

YE] NE UE N/AZ YE NO U[

N/AlZ

4. Is the anchorage free of visible cracks in the concrete near the anchors?

YE NEI UD N/A12

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YEI NEI UD3 N/AZ YZ NO U-SEnter the equipmeni class name from Appendix B: Classes of Equipment.

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Sheet 2 of 3 Status: YF ND U[

Seismic Walkdown Checklist (SWC)

Equipment ID No.

INC32B sEquip Class Equipment Description PZR PORV Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YlZ NEI Ut] N/AEl

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NE] Ut1 N/AtI and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YN[

NE] Ut] N/At]

YE NE] UE Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ NEI Ut]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: 7-IOna-s-Al -- k&/4*

~4:9 A?~<

Date:

,3~~

2 CNC-1206.03-00-0203 Rev 1 A Page 55 of 105 I

Sheet 3 of 3 Status: Y[

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Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NC32B Equip. Class, 7 (AOV)

Equipment Description PZR PORV Photo2raphs Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 56 of 105

Sheet i of 3 Status: YM N[-- U-Seismic Walkdown Checklist (SWC)

Equipment IDNo. 1NC36B Equip. Class' 7 (AOV)

Equipment Description PZR PORV Location: Bldg. CVI Floor El. 635 Room, Area DEG 101 RAD R37 - Top of PZR Cavity Manufacturer, Model, Etc. (optional but recommended)

CCI Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Line mounted item.

2. Is the anchorage free of bent, broken, missing or loose hardware?

Studs and nuts attaching valve assembly to line mounted portion of valve are all there and in excellent condition.

3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete near the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YO NO YE-NO UE N/AO YE NEI UE NIAZ YE NE JIE N/AZ YE NE UE N/As YN NE UEý Enter the equipmenl class name fromn Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 57 of 105

Sheet 2 of 3 Status: Y1Z ND UM Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NC36B Equip. Class, Equipment Description PZR PORV Interaction Effects

7. Are soft targets free fiom impact by nearby equipment or structures?

YZ ND UD N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD) and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment flee of potentially adverse seismic interaction effects?

YER ND UD1 N/AD YZ NO UO Other Adverse Conditions

1. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

YZ ND UED Comments (Additional pages may be added as necessary)

Congested area. All items in good condition and installed correctly. This component is worked on/rebuilt regularly.

Evaluated by: 7-/oi,..

, A rL/{6'p 7,

Date:

/

CNC-1206.03-00-0203 Rev 1 A Page 58 of 105

Sheet 3 of 3 Status: Y[

NE-UE]

Seismic Walkdown Checklist (SWC)

Equipment ID No. INC36B Equip. Class' Equipment Description PZR PORV Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 59 of 105

Sheet I o14 Status: YN N7 UM Area Walk-By Checklist (AWC)

Location: Bldg. CV1 Floor El. 568 Room, Area, DEG 244 RAD 47 - Room PCHA Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID Description I FW8 Refueling Cavity Drain Column Line or Other Location Info Deg 244 Rad 47 El 568 I. Does anchorage of equipment in the area appear to be fiee of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

YZ NE UD N/AD

2. Does anchorage of equipment in the area appear to be free of significant YN ND] UD N/AD-degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YZ ND UD N/AO

' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC-

-FW8.DOC CNC-1206.03-00-0203 Rev 1 A Page 60 of 105

Sheet 2 of 4 Status: Y[

N[] UD Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 568 Room, Area1 DLG' 244 RIAD 47 -.Room PCHA

4. Does it appear that the area is free of potentially adverse seismic spatial YZ NDI UD N/AD interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?

YZ ND UD N/AD

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of poltable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YN NDI U0 N/AD]

YE, ND UDI N/ADl

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

YZ ND U0 AWC-I FWS.DOC CNC-1206.03-00-0203 Rev 1 A Page 61 of 105

Sheet 3 of 4 Status: YZ NE-* UD)

Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 568 Room, Area' DEG 244 RID 47 - Room PCHA Conirnents (Additional pages may be added as necessary)

Noted I VP7A -- First tubing clamp off operator is loose-see pictures. This is a VI tubing clamp on the line attached to 1V13690. Tubing is still supported by clamp. Wrote work request #01075428 to tighten/repair.

1 VYI 7A - 4 inch VY (H2 sample and purge) pipe elbow is close to a Nuclear Safety Related cable junction box. Pipe seems rigid, and cable junction box could tolerate some contact, as it can flex somewhat. There is approx. 'A" clear currently. There is some slack in the cables, and the junction box is mounted on 4" electray that is mounted on unistrut.

This electric junction box assembly is not very massive, and seismic movement would be minimal due to stiffniess of unistrut support. The piping is restrained in the lateral direction by two supports, I-A-VY-4008 and I -A-VY-4234, so lateral seismic motion of the piping should be negligible. See Photo.

Evaluated by: Thomas R Leitch Date: 02/18/2013 Y~2J~

hj 22 U. -1:3 AWC-IFWS.DOC CNC-1206.03-00-0203 Rev 1 A Page 62 of 105

Sheet 4 of 4 Status: YN N[] Ur-Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 568 Room, Area, DEG 244 RAD 47 - Room PCHA Photographs iNote: inis vaive is near 4 in elDOW ShOWn DelOW trote: t-irst tuDing ciamp on' ntos operator is loose.

Note: Loose Tubing clamp is attached to support shown on right.

AWC-I FWS.DOC CNC-1206.03-00-0203 Rev 1 A Page 63 of 105

Sheet I of 3 Status: YN NR U[]

Seismic Walkdown Checklist (SWC)

Equipment ID No. IFW8 Equip. Class' 00 (Other)

Equipment Description Refueling Cavity Drain Location: Bldg. CV1 Floor El. 568 Room, Area DEG 244 RAD 47 - Room PCHA Manufacturer, Model, Etc. (optional but recommended)

Westinghouse 09D-210 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWt.L. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y F-1 N 9

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. ls the anchorage free of visible cracks in the concrete near the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage flee of potentially adverse seismic conditions?

YE NE UD N/Az YE-NE UrI N/A[D YE NE UE N/AZ YE NE UO N/AN YX NO UE-Enter the equipmcnt class name from Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 64 of 105

Sheet 2 of 3 Status: YM ND Ul--

Seismic Walkdown Checklist (SWC)

Equipment ID No.

1FW8 Equip. Class, 00 (Other)

Equipment Description Refueling Cavity Drain Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YN NI U-i N/AO

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YEK ND ur-N/AD-and masonry block walls not likely to collapse onto the equipment?

No ceiling tiles

9. Do attached lines have adequate flexibility to avoid damage?

No attached lines, this is a manual valve 1 0. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YO NO UD N/An Y[K NO U-Other Adverse Conditions I1. I-lave you looked for and found no other seismic conditions that could Y E N -1 Ui0 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as mecessary)

See Picture. Also ref CN-1491-FWO07 Evaluated by: 71-//4,ew"

/F 4r'7-a Z

1 6

Date: 12//3 /40 / Ze-

-7 J e, 09

,~

CNC-1206.03-00-0203 Rev 1 A Page 65 of 105

Sheet 3 of 3 Status: YZ NM] U[]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 1FW8 Equip. ClassW 00 (Other)

Equipment Description Refueling Cavity Drain Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 66 of 105

Sheet I of 4 Status: YZ N[D U-Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID IFW46 Description Refueling Cavity Drain Column Line or Other Location Info Deg300 Rad 33 El 563

1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

YZ N: UD-N/AO

2. Does anchorage of equipment in the area appear to be free of significant YN ND UD-N/AF-1 degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YZ NED UD N/AD

' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC-I FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 67 of 105

Sheet 2 of 4 Status: YZ N7 U[]

Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YE NEI UED N/A-1 Y9* NO UD N/AD Y&* ND U-N/AD YZ NO U-N/AD

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

YE NEIUM Comments (Additional pages may be added as necessary)

Noted some small flexible VS lines in the area. This is not a problem due to adequate clearance and low mass.

AWC-I FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 68 of 105

Sheet 3 of 4 Status: Y[

ND-U-Area Walk-By Checklist (AWC)

Location: Bldg. CV]

Floor E[. 563 Room, Area' DEG 300 RAD 33 - Room LC Evaluated by: Thomas]? Leilch Date:

~

721 Ra 'mond Fun Date:

11 AWC-I FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 69 of 105

Sheet 4 of 4 Status: Y:'] ND U[3 Area Walk-By Checklist (AWC)

Location: Bldg. CVI Floor El. 563 Room, Area' DEG 300 RAD 33 - Room LC Photographs Note:

Note:

Note:

Note:

AWC - 1FW46.DOC CNC-1206.03-00-0203 Rev 1 A Page 70 of 105

Sheet 1 of 3 Status: Y[

NEI UW Seismic Walkdown Checklist (SWC)

Equipment ID No. 1FW46 Equip. Class, 00 (Other)

Equipment Description Refueling Cavity Drain Location: Bldg. CV1 Floor El. 563 Room, Area DEG 300 RAD 33-Room LC Manufacturer, Model, Etc. (optional but recommended)

Westinghouse 09D-210 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL, The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one YE N[9 of the 50% of SWEL items requiring such verification)?

Line mounted item.

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YD NE UE N/AN YE NEI UL] N/AH

4. Is the anchorage free of visible cracks in the concrete near the anchors?

YE NEi UE N/AZ

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YE NE UD N/As Y9 NEI UE-Enter the equipment class name fIom Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 71 of 105

Sheet 2 of 3 Status: YE ND UR Seismic Walkdown Checklist (SWC)

Equipment ID No.

1FW46 Equip. Class, 00 (Other)

Equipment Description Refueling Cavity Drain Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

Y 0 ND UD N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YFJ ND-UD-N/AD and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?

Manual valve. No attached lines

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YD1 NDI U-N/AN YZ ND) UD Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could Y[

ND UD adversely affect the safety functions of the equipment?

Cominents (Additional pages may be added as necessary)

Ref CN-1491-FW.00-004 Evaluated by: Thomas R Leitch De/./

  • ,,Iq I-,

F-A (2-.v, 22Z CNC-1206.03-00-0203 Rev 1 A Page 72 of 105

Sheet 3 of 3 Status: YN ND UD Seismic Walkdown Checklist (SWC)

Equipment ID No, 1FW46 Equip. Class, 00 (Other)

Equipment Description Refueling Cavity Drain Photo rahs Note: 1FW46 Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 73 of 105

Sheet I of 4 Status: YN NEI U[-

Area Walk-By Checklist (AWC)

Location: Bldg. RXI Floor El. 557 Room, Areal DEG 280 REG60R Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equjpment ID I NVPDO042 INV865A INVPUSB Description Column Line or Other Location Info Stnby M/U Disch Pulsa Damp Deg 278 Rad 58 El 558 Stnby M/U Pump Suct fi'om XFR Tube Deg 266 Rad 61 El 578 Standby Makeup Pump Deg 280 Rad 64 El 557 I. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

YZ NEI UD N/AR

2. Does anchorage of equipment in the area appear to be free of significant Y[D NDI UD N/AD-degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YZ NDI UD N/AD If the room in which the SWEL item is located is vei) large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC - I NVPUSB.DOC CNC-1206.03-00-0203 Rev I A Page 74 of 105

Sheet 2 of 4 Status: Y[

NfI-UE]

Area Walk-By Checklist (AWC)

Location: Bldg. RXI Floor El..5.57_

Room, Area' DEG. 280 REG60R

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YZ NDI U-N/AD YO NO U7 N/AD[

YZ NDI UD N/AD-Y[

NDI U[D N/ADI

8. Have you looked for and found no other seismic conditions that could Y[E ND1 UD-1 adversely affect the safety functions of the equipment in the area?

AWC - I NV1)USB.DOC CNC-1206.03-00-0203 Rev 1 A Page 75 of 105

Sheet 3 of 4 Status: YZ N[

U[D Area Walk-By Checklist (AWC)

Location: Bldg. RXI Floor El. 557 Room, Area' DEG 280 REG6OR Comments (Additional pages may be added as necessary)

Noted lighting on Poles attached to railing on elev. 575. These items are very flexible and not likely to survive a seismic event, however, they are not heavy or massive, and no targets were identified in the area that they would impact, so this is not an issue of concern.

Also noted that minimum 2" NV system clearance standard between 2 inch NV line and unistrut supporting a small electray is not met. The NV line is on CN-1491-NV.00-117, elev 562'-9", and is almost directly above the pulsation dampener. (Approx Az 277, rad 59'-4"). This is not a QA I line, so this 2" clearance is a good practice rather than a requirement. This clearance can be achieved by removing enough material from the unistrut to achieve the system clearance. See Photo.

Evaluated by: Thomas R Leitch :ý 4

?aAlh~

~

Date:

/

/z-

/20/20

/o1Ž..

6 YA 0 A~p F14 -)67 AWC. INVPUS[3.DOC CNC-1206.03-00-0203 Rev 1 A Page 76 of 105

Sheet 4 of 4 Status: YZ ND-U-]

Area Walk-By Checklist (AWC)

Location: Bldg. RXI Floor El. 557 Room, Area' DEG 280 REG60R Photographs Note: NV System Clearance not met. Per Note:

MP/O/A/7650/153, good practice clearance for 250 degree NV line is 2" (Not required, since line is not QA 1, just good practice)

Note:

Note:

AWC-INVPUSB.DOC CNC-1206.03-00-0203 Rev 1 A Page 77 of 105

Sheet I of 4 Status: YN Nn U-Seismic Walkdown Checklist (SWC)

Equipment ID No.

1NVPDO042 Equip. Class, 00 (Other)

Equipment Description Standby Makeup Discharge Pulsation Dampener Location: Bldg. RXI Floor El. 558 Room, Area DEG 278 RAD 58 Manufacturer, Model, Etc. (optional but recommended)

Metal Bellows Div Senior 76016 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YO NZ

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete neatr the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YE-NEi UED N/AZ YI[] N.,

UE-N/AZ YE] NED UE] N/AZ YEO NEI UE] N/AZ YR Nn U[1

' Enter the equipment class name from Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 78 of 105

Sheet 2 of 4 Status: YN ND-U-Seismic Walkdown Checklist (SWC)

Equipment ID No.

INVPDO042 Equip. Class, 00 (Other)

Equipment Description Standby Makeup Discharoe Pulsation Dampener Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

Y(9 ND U[ N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND UD N/AD]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YZ ND UD1 N/A[]

YZ NO UD Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

Noted one spring can from vertical trapeze support that is supporting the pulsation dampener is almost touching the metal belt guard on the PD pump. There are two Type A B268 spring cans, and one is only 1/8" clear of the metal belt guard for the PD pump. The can weights no more than 15# and it is a vertical support, so its horizontal seismic motion is limited by rod tension and restraint at the top and bottom of the can. Some limited minor seismic interaction with the belt guard is possible, but the potential unrestrained (no interaction) horizontal motion would not be likely to exceed X" since the seismic driving force involved should be less than one G. This could result in minimal seismic interaction with the metal belt guard, but the guard appears robust enough to withstand the small forces involved without significant damage. Also, the pump is radwaste related (QA2) but it is not designed as seismically supported, and the piping supported by the spring cans is class E and supported per Construction requirements, which are also non seismic. These items are both part of SWEL 2, not SWEL 1. See photo.

YN ND UD CNC-1206.03-00-0203 Rev 1 A Page 79 of 105

Sheet 3 of 4 Status: YZ NT-D UWE Seismic Walkdown Checklist (SWC)

Equipment ID No.

1NVPDO042 Equip. Class2 00 (Other)

Equipment Description Standby Makeup DischarLe Pulsation Dampener Comments (Additional pages may be added as necessary)

Ref Drwgs CNM-1201.04-0174.001 and CN-1491-NV.00-117. Pulsation dampener was recently replaced by mod EC 102855.

Evaluated by: Thomas R Leitch Date:

6,//9/A0/3 2 21 ~-~i CNC-1206.03-00-0203 Rev 1 A Page 80 of 105

Sheet 4 of 4 Status: YO ND U-Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NVPDO042 Equip. Class' 00 (Other)

Equipment Description Standby Makeup Discharge Pulsation Dampener P

Note: PD support and left spring.

fNote:

L At Note: Right spring close to belt guard.

Note:

CNC-1206.03-00-0203 Rev 1 A Page 81 of 105

Sheet I of 3 Status: Y19 NEI UD Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NV865A Equip. Class, 8 (MOVI Equipment Description Standby M/U Pump Suction from XFR Tube Location*: Bldg. AN1 Floor El. 578 Room, Area DEG 266 RAD 61 Manufacturer, Model, Etc. (optional but recommended)

Borg Warner 05B-262 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorape I. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YD NZ

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YEI NE] UE-N/AZ YE] NE] UD N/AED

4. Is the anchorage free of visible cracks in the concrete near the anchors?

Yn NEI-UiC N/A9

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YD-N[-I UI-1 N/AZ]

YE] NE UE]

Enter the equipment class name from Appendix 13: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 82 of 105

Sheet 2 of 3 Status: YN ND UM Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NV865A Equip. Class, 8 (MOV)

Equipment Description Standby M/U Pump Suction from XFR Tube Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?
8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YZ ND UD N/AL Y0 ND UD N/ALl YN ND UD N/AD YN NEI U-Other Adverse Conditions I 1. Have you looked for and found no other seismic conditions that could YZ ND UD adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Ref drawing CN-]491-N]

/ 16.

Evaluated by: */o.at'71a.

Z? L& L Date:

(,4~ 6/~

7J~((J4____

CNC-1206.03-00-0203 Rev 1 A Page 83 of 105

I-Sheet 3 of 3 Status: Y[D NE UF Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NV865A Equip. Class1 8 (MOVW Equipment Description Standby M/U Pum" Suction from XFR Tube Photozraphs Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 84 of 105

Seismic Walkdown Checklist (SWC)

Sheet 1 of 4 Status: YZ' N-1 ULD Equipment ID No.

1NVPUSB Equip. Class, 5 (Horizontal Pump)

Equipment Description Standby Makeup Pump Location: Bldg. RXI Floor El. 557 Room, Area DEG 280 RAD 064 Manufacturer, Model, Etc. (optional but recommended)

Whealley S/N 5P1510 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is (lte anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YE NO

2. Is the anchorage free of bent, broken, missing or loose hardwaare?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete near the anchors?
5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Y[Z ND i U N/AD--

YO NED UD N/AEZ YZ ND U-N/AD YlZ NI ULD N/AD1 YZ NEI UD

' Enter the equipment class name from Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 85 of 105

Sheet 2 of 4 Status: YZ NF[

UZ-Seismic Walkdown Checklist (SWC)

Equipment ID No. 1NVPUSB Equip. Class, 5 (Horizontal Pump)

Equipment Description Standby Makeup Pump Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

Y Z NO UD N/AM

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ No UD N/AD and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YZ NDI UD N/AD YE NO UD Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

YZ NO UE Comments (Additional pages may be added as necessary)

Note that Standby makeup pump support is not safety related, although it is well built and appears to be quite sturdy. The Standby makeup pump and the piping leading into and out of it are class E, radwaste related, and are not seismic category 1. They were never intended to be seismically designed. This is acceptable due to the system design. These components were selected for walk down as part of the SWEL 2 list, which does not have to be seismic category 1.

Ref CNM-1203.03-0080, CN-1080-22, CN-1491-07.00-08, CNC-1206.03-00-0203 Rev 1 A Page 86 of 105

Seismic Walkdown Checklist (SWC)

Equipment ID No.

INVPUSB Equip. Class, 5 (Horizontal Pump)

Equipment Description Standby Makeup Pump Sheet 3 of 4 Status: YZ N-I UM Evaluated by: Thomas R. Leitch "7"-li le Raymond C Fung Date:

0

/,

/*.z,/-3 2

z2o-l, CNC-1206.03-00-0203 Rev 1 A Page 87 of 105

Seismic Walkdown Checklist (SWC)

Equipment ID No.

INVPUSB Equip. Class' 5 (Horizontal Pump)

Equipment Description Standby Makeuo Pump Sheet 4 of 4 Status: YZ NF U[D]

Note: Anchorage in good condition.

Note:

CNC-1206.03-00-0203 Rev 1 A Page 88 of 105

Sheet I of 4 Status: YN ND UD Area Walk-By Checklist (AWC)

Location: Bldg. A UX Floor El. 594 Room, Area, CC-55 (Control Room)

Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID Description Column Line oi-Other Location Info I SSPSA Solid State Protection Syst, Train A CC-56 (Control Room)

I Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

1SSPSA anchorage was visible when cabinet was opened, and one other cabinet (IELCCO058) had anchorage that was visible when cabinet was closed. No other cabinets in the walk-by area were available to be opened. Anchors that were visible were free of potentially adverse seismic conditions. (see photo)

YZ ND UD N/AD

2. Does anchorage of equipment in the area appear to be free of significant YN ND] UD) N/AD degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

Initially, these items were not visible from the floor due to lightweight ceiling material. A subsequent walk by was performed to remove a sample of ceiling material to allow visual inspection of the cable conduit raceways and HVAC ducting in the walk by area ceiling. The HVAC Ducting and supports were in excellent condition. There are only a few cable Iconduit raceways, they are not overfilled and are adequately supported.

YZ NDI UD N/AD1

'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC-I SSPSA.DOC CNC-1206.03-00-0203 Rev 1 A Page 89 of 105

Sheet 2 of 4 Status: Y[* NM U--

Area Walk-By Checklist (AWC)

Location: Bldg. A UX Floor El. 594 Room, Area3 CC-55 (Control Room)

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Ceiling material is very light weight and would not adversely interact due to low mass. Lighting appears to be well secured to prevent failure during a seismic event. The lighting fixtures are also tethered with light chains to prevent them from falling.

5. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is fiee of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YN ND UD N/ADI Y1Z NDI UD3 N/ADI YS ND UD N/AD Y0 ND UD N/AD1

8. Have you looked for and found no other seismic conditions that could YN NDI UDI adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

AWC-ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 A Page 90 of 105

Sheet 3 of 4 Status: Y[

ND Ui-]

Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. 594 Room, Area' CC-55 LControl Room)

Evaluated by: Thomas R Leitch 1

Date: 02/20/2013 Ra 'mond C FII)7g Y22, 1121V 13 AWC-ISSI'SA.DOC CNC-1206.03-00-0203 Rev 1 A Page 91 of 105

Sheet 4 of 4 Status: Y[

NO U[-

Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. 594 Room, Area, CC-55 (.Control Room)

Photo2ravhs INote: ivo aaverse Interacrions.

iN ote: lignrweignh ceuiing mareriat i

Note: Lighting Fixture chain tether.

AWC-ISSPSA.DOC CNC-1206.03-00-0203 Rev 1 A Page 92 of 105

Seismic Walkdown Checklist (SWC)

Sheet 1 Of 3 Status: YZ No U[

Equipment ED No.

ISSPSA Equip. Class, 18 (Equipment Rack)

Equipment Description Solid State Protection System Train A Location: Bldg. AUX Floor El. 594 Room, Area CC-55 Manufacturer, Model, Etc. (optional but recommended)

WestinO05678 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YZ NEI

2. Is the anchorage free of bent, broken, missing or loose hardware?
3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YE NEI UD" N/AD YZ NED UD) N/AD

4. Is the anchorage free of visible cracks in the concrete near the anchors?

YZ NEI U0 N/AD

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Y(3 NDl UD N/AD-YZ NEI U-Enter the equipment class name from Appendix B: Classes of Equipment.

CNC-1206.03-00-0203 Rev 1 A Page 93 of 105

Sheet 2 of 3 Status: Y[

ND-- U-Seismic Walkdown Checklist (SWC)

Equipment ID No. 1SSPSA Equip. Class' 18 (Equipment Rack)

Equipment Description Solid State Protection System Train A Interaction Effects

7. Are soft targets firee from impact by nearby equipment or structures?

Y[9 ND1 iJEI N/AE3

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y9 N.1 UD3 N/ADl and masonry block walls not likely to collapse onto the equipment?

Ceiling tiles appear in acceptable condition, and also are very light weight. If any were to fall, they would not have enough mass to cause damage or operate the equipment.

9. Do attached lines have adequate flexibility to avoid damage?

Attached lines are cables, and there is enough flexibility to avoid damage. See Photo.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YZI NDO ULI N/AD YZ NEI Ur Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YED NED UD adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

The cabinet is well anchored, and cables and fasteners are in good condition, with good sealing in floor penetration area. Reference CNC-1139.14-19-0001, CN-1200-10.04, CNM-1399.08-0039-005, CN-1214-01, CN-1224-05, CN-1227-05.

Evaluated by: ThomasRLeitch ei"r I

Ravmond C Funo Q

7-' -

"9 Date: 12/06/2012 1--j CNC-1206.03-00-0203 Rev 1 A Page 94 of 105

Seismic Walkdown Checklist (SWC)

Sheet 3 of 3 Status: Y[

NEI U-Equipment ID No. ISSPSA Equip. Class' 18 (Equipment Rack)

Equipment Description Solid State Protection System Train A Photographs Photographs r~ote: 7, Note: Cables well sealed with adequate flex.

Note: Load path.

CNC-1206.03-00-0203 Rev 1 A Page 95 of 105

Sheet I of 4 Status: YE) NR-U-Area Walk-By Checklist (AWC)

Location: Bldg. Aux Floor El. 560 Room, Area, Aux 560 Rm 372, AA-51 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

Components: Equipment ID 1ETXB I ETXD Description 4160/600 VAC Trans 4160/600 VAC Trans Column Line or Other Location Info AA-47 AA-46

1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

YE N[

U-I' N/AD

2. Does anchorage of equipment in the area appear to be free of significant YZ NE] UD N/An degraded conditions?
3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

YO NDI UD1 N/AD3

,If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

AWC - I,TXB-20120620.DOC CNC-1206.03-00-0203 Rev 1 A Page 96 of 105

Sheet 2 of 4 Status: YDý NDi UD-Area Walk-By Checklist (AWC)

Location: Bldg. Aux Floor El. 560 Room, Arca' I/ux 560 Rin 372, AA-S]

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?
5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?
6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?
7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YN ND UD N/AD' YE Nn U0 N/AD YZ ND UD N/AD Y{J N[D] UD N/ADI

8. Have you looked for and found no other seismic conditions that could YE1 ND UD adversely affect the safety functions of the equipment in the area?

AWC - IFIX~3-20120 620. DOC CNC-1206.03-00-0203 Rev 1 A Page 97 of 105

Sheet 3 of 4 Status: Y[

N7 U[]

Area Walk-By Checklist (AWC)

Location: Bldg. Aiux Floor El. 560 Room, Areal AJg 560 Rkn 372, AA-51 Comments (Additional pages may be added as necessary)

Area was very neat and clean. Noted 4 hand held fire extinguishers hanging on hooks fairly low on columns in the area.

These are not likely to come off hooks during event, because the vertical component of seismic acceleration in this area is less than Ig. Also, no significant spray targets were noted in the immediate vicinity of these devices.

A rigid cable tray support with approximately 3/8" clearance between the support and a lifting lug on I ETXF was noted. (see photo) This is acceptable by comparison, because rigid cabinets in this area will experience a lateral seismic movement of approx. 0.1 inches, and the transformer is at least as rigid as these cabinets. Similarly, the cable tray support frame is rigid, and seismic movements of approx 0.1 inches are expected. Therefore this clearance should be adequate to prevent interaction.

Evaluated by: Thomas R Leitch Date:

1-3"27 20--

Ravniond Fzmgw Date:

/-

/7 AWC - I CTXB-20120620.DOC CNC-1206.03-00-0203 Rev 1 A Page 98 of 105

Sheet 4 of 4 Status: YE NE] U-Area Walk-By Checklist (AWC)

Location: Bldg. Aux Floor El. 560 Room, Area, Aux 560 RnI 372, AA-51 i'iote: t.awie tray supporr ciose uo im iug on 7t: i At-Note:

Note:

Note:

AWC - IMTB-20120620.DOX7 CNC-1206.03-00-0203 Rev 1 A Page 99 of 105

Sheet I of 3 Status: YED N-- U-Seismic Walkdown Checklist (SWC)

Equipment ID No. 1ETXB Equip. Class' 4 (Transformers)

Equipment Description 4160/600 VAC Transformer Location: Bldg. Aux Floor El. 560 Room, Area Rm 372 Area AA-47 Manufacturer, Model, Etc. (optional but recommended)

Westing house 4160-600Y/346 Instructions for Completing Cheeldist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorae.

1. Is the anchorage configuration verification required (i.e., is the ilem one of the 50% of SWEL items requiring such verification)?

YZ NEI

2. Is the anchorage free of bent, broken, missing or loose hardware?

Transformer is welded to W section that is welded to steel plate which is welded to embedments. No broken welds or bent areas were observed..

3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete near the anchors?

There are no anchors, but the concrete is free of cracks.

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YN NED UIJ] N/AF!

YtN NEI U7-N/AD YDE NEI UW1 N/AZ Y5 NEI UD) N/A[U YE Nn UE1 Elner the equipment class name from Appendix B: Classes of Equipmein.

CNC-1206.03-00-0203 Rev 1 A Page 100 of 105

Sheet 2 of 3 Status: YN NO) UF]

Seismic Walkdown Checklist (SWC)

Equipment ID No.

1ETXB Equip. Class' 4 (Transformers)

Equipment Description 4160/600 VAC Transformer Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

YE ND U0- N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND U[] N/AD]

and mason'y block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y9 NDI UD1 N/A[I YO* ND U[D Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[9 ND UED adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Noted one cable tray support (rigid) has only minimal clearance (approx. 118') from transformer cooling fin support steel. Based on comparison with rigid cabinets in this area, this could result in minimal seismic interaction between the fin support steel and the cable tray support. This interaction would be in the order of 0. 1 inches or less, since the tray support could move approx.

0. 1 inches and the transformer could move approx. 0. 1 inches, which could result in some minor yielding and distortion, primarily in the cable tray support unistrut material.

Evaluated by: Thomas R Leitch Date:

,2 Date:

2/7 2.e/3 Raymond C Funa fi~&~

CNC-1206.03-00-0203 Rev 1 A Page 101 of 105

Sheet 3 of 3 Status: YN NR-UR Seismic Walkdown Checklist (SWC)

Equipment ID No. 1ETXB Equip. Class' 4 (Transformers)

Equipment Description 4160/600 VAC Transformer Ph, otographs Photographs Note: Minimal clearance between lug and cable tray support.

Note:

CNC-1206.03-00-0203 Rev 1 A Page 102 of 105

Sheet 1 of 3 Status: Y[K N-- UD Seismic Walkdown Checklist (SWC)

Equipment ID No.

IETXD Equip. Class' 4 (Transformers)

Equipment Description 4160/600 VAC Transformer Location: Bldg. Aux Floor El. 560 Room, Area Rm 372 Area AA-46 Manufacturer, Model, Etc. (optional but recommended)

Westing house 4160-600Y/346 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y[

NO

2. Is the anchorage free of bent, broken, missing or loose hardware?

Transformer is welded to Wsection that is welded to steel plate which is welded to embedments. No broken welds or bent areas were observed.

3. Is the anchorage free of corrosion that is more than mild surface oxidation?
4. Is the anchorage free of visible cracks in the concrete near the anchors?

The concrete is free of visible cracks near the embedded plates. The only anchors are the nelson studs that are welded to the underside of the embedded plates.

5. Is the anchorage configuration consistent with plant documentation?

(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on tlhe above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YN ND U0 N/AE]

YZ NDI-UDE N/AD YD ND UD N/AED YD ND UD-N/AD YZ ND UD I Enter the equipment class name from Appendix B: Classes of Equipmem.

CNC-1206.03-00-0203 Rev 1 A Page 103 of 105

Sheet 2 of 3 Status: Y[

Nn U-Seismic Walkdown Checklist (SWC)

Equipment ID No.

1ETXD Equip. Class, 4 (Transformers)

Equipment Description 4160/600 VAC Transformer Interaction Effects

7. Are soft targets free from impact, by nearby equipment or structures?

YID NI U-I N/ADl

8. Are overhead equipment, distribution systems., ceiling tiles and lighting, YN NDI UD1 N/AD1 and masonry block walls not likely to collapse onto the equipment?
9. Do attached lines have adequate flexibility to avoid damage?
10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

YZ NDI UD N/AD)

YE NDI UD1 Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YER ND-U[I adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Noted one cable tray support (rigid) has only X" clearance from large steel box attached to South end of transformer. This is acceptable because both items are rigid and Y1/4" gap will prevent any seismic interaction.

Evaluated by: Thomas R Leitch Raymond C Fung Date: 11/01/2012 i 111' /

Zv/

CNC-1206.03-00-0203 Rev 1 A Page 104 of 105

Sheet 3 of 3 Status: Y[

NE] UP-Seismic Walkdown Checklist (SWC)

Equipment ID No. IETXD Equip. Class' 4 (Transformers)

Equipment Description 4160/600 VAC Transformer Phiotogra pbs Note: No photographs.

Note:

Note:

Note:

CNC-1206.03-00-0203 Rev 1 A Page 105 of 105

.10 N~o.:

1,'15769030:3

  • Aohile A WO)kica" Ine, D~oc. No.:

1,157690:03 RA.l-M00001-()

Revision: 0-CA ThCHJN AL IMEPORT Clienlt:

D~ilkc I

~C ata 2nwba Uniit I N'TTV 2.3.. E]ISMIC' PEE~R REIU~EW StJPPIAEiVEN'ARV M)'TR (XI'AWHA NOCLEAR ýRTATJI)N UJNIT I Pre-pared lbr:

Duike F"Dergy Carolinas, LL.C PreparedI by: Stone & Webster, hic. and A RE'S Corp~orahion M~'arch Ill, 2013 QA CATEGORY III ARES Corporation Slone and Wiabsicr. lInc. (A CBMl Company)

Duike Vnetrty 311,112013 3/1-112013attc 3/1 4/2013 3/1,1/2013 3/14/2013 Dille CIMI Approval: Atilliony F, Fazio Date PtqiL!V.t Mallager ml

0) 2013 by Stone &- Webster, hic. All rights rewirvcet.

A i.

CNC-1206.03-00-0203 Rev 1 Attachment BA Page 1 of 15

N'l1'1F 2-.3 Si-,ismic 1 Ri-i.a

[vw~ St.jjpPI.E\\u-I\\'IETAR\\'

REPORT, CATAWBIA NUCLEAR STATION UNIT I Revision Description CNC-1206.03-00-0203 Rev 1 A Page 2 of 15

NTTFF2.3 Si-lsmic PiA.iR REV 113W SUPPLEU3MNTAR\\'

Rrpoiwr, CATAWBA NUCl'AR SiTATION UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013

'Fable of Contents

1.0 INTRODUCTION

I 2.0 S C O P E.............................................................................................................................................

1 3.0 M ETHODOLOGY..........................................................................................................................

1 4.0 P E R S O N N E L...................................................................................................................................

2 5.0 SELECTION OF THE SSCs INCLUDED ON THE SWEI........................

2 6.0 SEISM IC WALKDOW NS AND AREA W ALK-BYS............................................................

3 7.0 LICENSING BASIS REVIEW S................................................................................................

4 8.0 DECISIONS ON ENTERING POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCEISS.....................................................................................................

5 9.0 SUBM ITTAL REPORT..................................................................................... 5

10.0 CONCLUSION

S..............................................................................................................................

6

11.0 REFERENCES

6 Appendices Appendix A: Summary of Peer Review of Final SWCs and AWCs for Inaccessible Items............ 5 Pages (IlL>

Page iii CNC-1206.03-00-0203 Rev 1 A Page 3 of 15

N'1TF 2.3 SrEiSmIC P1EER REVII;W S U I[.LEM INTIt Y RI.TIORT, CATAWB'1A NUCLEAR STATION tiNII I' Report No. 1457690303-R-M-00004, Rev. 0 March 2013 Acronyms ARES AWC CAP CB&I CNS Duke Energy EPRI IPEEE NRC NTF Pil SQUG SSC SWC SWE SWEL ARES Corporation Area Walk-By Checklist Corrective Action Program CB&I Company Catawba Nuclear Station Duke Energy Carolinas, LLC Electric Power Research Institute Individual Plant Examination of External Events U.S. Nuclear Rcgulatory Commission Near-Term Task Force Problem Investigation Process Seismic Qualification Utility Group Structure, System and Component Seismic Walkdown Checklist Seismic Walkdown Engineer Seismic Walkdown Equipment List Page iv CNC-1 206.03-00-0203 Rev 1 Attachment BA Page 4 of 15

NTTF 2.3 SI~ISMIC PIiR Riw mw Surri.EN4ENIARY Report No. I 457690303-R-M-00004, Rev. 0 NT'-IF-2.3 Srlis.MIC" h;!

RimVm*

SUJPPLEME'NTARY Report No. 1457690303-R-M-00004, Rev. 0 RF'TORT, CATAWB*A N UCLEAR STATION UNIT I March 2013

1.0 INTRODUCTION

Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidance for Resolution qofFukushima Near-Term Task Force Reconmnendation 2.3: Seismic, was issued in,June 2012. This document provides guidance and procedures to perform seismic walkdowns as required by the U,S. Nuclear Regulatory Commission's (NRC's) 50.54(l) letter regarding Near-Term Task Force (N'T'TF) Recommendation 2.3: Seismic. The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components (SSCs) that represent diversity of component types and ensures inclusion of components from critical systems/functions; conduct of the walkdowns; evaluation of potentially adverse conditions against the plant seismic licensing basis; peer review; Individual Plant Examination of External Events (Ii1EEE) vulnerabilities; and reporting requirements. It was intended that all U.S. nuclear pOWCer plants utilize this guidance document in meeting the requirements of the NRC 50.54(f) letter.

D)uke Energy Carolinas, LLC (Duke Energy) contracted with Stone and Webster, Inc., a CB&I Company (CB&I) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). This report documents that peer review. A peer review of the NTTF 2.3 seismic walkdowns of Units I and 2 was conducted in September 2012 and documented in CB&!

/ARES Technical Report 1457690303-R-M-00003, NTTF 2.3 Seismic Peer Review Report, Catawba Nuclear Station Units I and 2. At that time, some items had not been walked down due to being inaccessible during plant operation. Walkdown of the Unit I inaccessible items were deferred to the Unit I l EOC20 refueling outage scheduled for November 2012. This report documents the supplementary peer review performed at Unit I in March 2013. The supplementary peer review covered the walkdown of inaccessible items at Unit I performed by Duke Energy during the Unit I refueling outage.

2.0 SCOPE The scope of this supplementary effort was to perform the NTTF 2.3 Seismic Peer Review of the walkdown of the inaccessible items at CNS Unit 1, in accordance with the guidelines in Section 6, Peer Review, of EPRI 1025286. It is intended that the information contained herein will be utilized by Duke Energy as part of its overall NT7F 2.3 final submittal report for Unit I to be delivered to the NRC in March 2013.

3.0 METHODOLOGY The CB&i/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the applicable activities. The Peer Review Team for the supplementary peer review consisted of the same individuals that performed the September 2012 peer review.

The peer review process for the Seismic Walkdown Equipment List (SWEL) development and seismic walkdowns was documented in CB&l / ARES Technical Report 1457690303-R-M-00003. Since the OPage 1

CNC-1206.03-00-0203 Rev 1 A Page 5 of 15

N'TI'T 2.3 SiI.sMi(: lcl.PER RRr.vNirW StJiIi,.IMENTARY Report No. 1457690303-R-M-00004, Rev. 0 RI.POt, CATAWBA NUCIEAR STATION UNIT I March 2013 SWEL did not change from the time of the September 2012 peer review, it was not part of the supplementary peer review.

The peer review process for the scismic walkdowns and walk-bys of the inaccessible items consisted of conducting a final review of the completed documentation. The other, in-process, steps in the review methodology described in CB&I / ARES Technical Report 1457690303-R-M-00003 were not considered necessary since the Duke Energy seismic walkdown engineers (SWEs) were included in the September 2012 peer review of in-process activities.

The peer review process Ibr the licensing basis evaluations and the decisions for entering potentially adverse conditions into the Corrective Action Program (CAP) consisted of reviewing all of the licensing basis reviews resulting f'rom the walkdown of 'the inaccessible items. The peer review process fbr the submittal report consisted of reviewing the draft submittal revision prepared by Catawba Design Engineering for licensing review.

4.0 PERSONNEL The CNS Peer Review Team fbr the supplemental peer review consisted of the following individuals.

As noted above, these are the same individuals who performed the September 2012 peer review.

Paid Baughman, P.E., ARES Corporation, Team Leader. Mr. Baughman is a licensed structural engineer with over 40 years of experience in seismic engineering fbr nuclear power stations.

Mr. Baughman is a subject matter expert and trainer for the Seismic Qualification Utility Group (SQUG). Mr. Baughman has performed seismic assessment activities for CNS and is familiar with the CNS seismic licensing basis. Mr. Baughman has performed many seismic margin assessments and seismic probabilistic risk assessments, and is familiar with systems modeling and development of safe shutdown equipment lists.

" George Bushnell, P.E., CB&I Power Group. Mr. Bushnell is a licensed mechanical engineer with over 40 years of experience in engineering qualification of electrical and mechanical equipment for nuclear power stations. Mr. Bushnell is a qualified SQUG Seismic Capability Engineer and company specialist for design and qualification of ASME. III components.

" Robert Keiser, P.E., Duke Energy. Mr. Keiser is a licensed professional engineer in North and South Carolina with over 20 years of experience in the seismic qualification of electrical equipment for Duke Energy's McGuire, Catawba, and Oconee Nuclear Stations. Mr. Keiser received training as a SQUG Seismic Capability Engineer and was involved with the SQUG effort at Oconee and the IPEEE efforts at all three stations.

5.0 SELECTION OF THE SSCs INCLUDED ON THE SWEL Peer review of the SWEL is described in CB&I /ARES Technical Report 1457690303-R-M-00003.

Since the SWEL did not change from September 2012 no further peer review was required.

Page 2 CNC-1206.03-00-0203 Rev 1 Attachment BA Page 6 of 15

NTTP 2. SESMI PHR R~vl~w SPPLM~i~hR ReortNo.I 4569003--M-000, Rv.I N"VIF 2.3 Si::ASMKi: liu.'1 RE.VllE.W SUPPL'EME"NTAR*Y Report No. 1457690303-R-M-00004, Rev. 0 REPORT, CATAWBA NUJCL.EAIR STATION UNIT I March 2013 6.0 SEISMIC WALKI)OWNS AND AREA WALK-BYS The inaccessible equipment items and areas to be walked down were listed in Appendix C of CB&I /

ARES Technical Report 1457690303-R-M-00001. The walkdowns consist of two parts: equipment-specific seismic walkdowns and area walk-bys. The specific instructions for each part are delineated in EPRI 1025286. The walkdowns were performed by Duke Energy.

Seismic walkdowns of specific items focused on identifying adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions that coulId challenge the seismic adequacy ofa SWEI item.

Anchorage was examined for degraded, nonconforming or unanalyzed conditions. This included visual inspection of the anchorage and verification of anchorage condition. 'Fhe visual inspections looked for bent, broken, missing or loose hardware; corrosion that is more than mild surface oxidation; visible cracks in the concrete near anchors; and other potentially adverse seismic conditions. This did not apply to line-mounted items.

Anchorage configuration was verified to be consistent with the existing plant documentation for a portion of the equipment with anchorage. The anchorage configuration verification mrust be done for at least 50% of the non-line-mounted SWEL items. As noted in CB&i / ARES Technical Report 1457690303-R-M-00001, the percentage for CNS Unit I exceeds the EPRI 1025286 requirement.

The area adjacent to and surrounding the SWEL item was inspected for nearby SSCs that could be seismic interaction hazards due to proximity, failure, and falling, or insufficient flexibility of attached lines and cables. Detailed guidance on seismic spatial interactions is given in Appendix D of EPRI 1025286.

The item was also examined to see if there were any other potentially adverse seismic conditions besides anchorage and seismic interaction. These could include other degraded conditions, loose or missing subcomponent fasteners, unusual large or heavy subcomponents, doors or panels not latched or fastened, or any other condition which might be seismically adverse. Where possible, cabinets and enclosures were opened for examination of internals.

Area walk-bys consisted of examining the general area surrounding the specific SWEL items for potentially adverse seismic conditions. The area examined included either the entire room enclosing the SWEL item or at least 35 feet in any direction. The examination looked for degraded anchorage conditions of equipment in the area; significantly degraded equipment; poorly supported cable/conduit raceways, IHVAC ducting, or piping; and unsecured temporary equipment that could cause seismic interactions (seismic housekeeping concerns). The area walk-by included looking for potential seismic interactions from flooding, spray, or fire. These potential seismic interactions are described in Section 4 of EPRI 1025286.

The Peer Review Team reviewed the qualifications of the Duke Energy engineers performing the walkdowns and verified that they meet the requirements for a SWE in EPRI 1025286. The Peer Review Team also conducted interviews with the engineers to confirm that they had a good understanding of the guidance in EPRI 1025286.

Page 3 CNC-1206.03-00-0203 Rev 1 A Page 7 of 15

NT`'/F 2.3 Si.isM. Pi.BR R1:Nvr-w SUPPILEiMENTARY Report No. 1457690303-R-M-00004, Rev. 0 REY'OR r, CATAWBA N UCI..IAR STATION UN IT ]

March 2013 The individuals interviewed were:

" T. R..Leitch - Duke Energy, Senior Walkdown Team Member

" R. C. Fung-Duke Energy, Walkdown 'learn Member

" J.D. Kennedy-Duke Enei'gy, Walkdown eam Member Interviews of walkdown personnel were jointly performed by the Duke Energy, ARES, and CB&I members of the Peer Review Teamr. Personnel were interviewed to assess their working synergy as well as individual capabilities/knowledge. All were verified to have attended the EPRI NTTF 2.3 Seismic Walkdown Training Course. Discussion provided positive indication that the walkdown personnel had adequate experience and training to perform walkdown and walk-by activities in compliance with the EP'RI Seismic Walkdown Guidance. They displayed knowledge of the primary objectives of the walkdowns, appropriate levels of dialog between themselves to reach common agreement without excessive discussion, and adequate objectivity in identification of significant discrepancies between as-designed and as-found conditions. Team member qualifications are included in the Duke Energy walkdown report.

The September 2012 peer review included review of in-process Area Walkdown Checklists (AWCs) and Seismic Walkdown Checklists (SWCs). Group meetings were held with the SWEs to address the peer review comments. The Duke Energy personnel who perlorned walkdowns of the inaccessible items attended these meetings.

The Peer Review Team reviewed 100% of the final SWCs and AWCs for the inaccessible items. This is more than the 10% sample that the EPRI guidance requires. The review is summarized in Appendix A of this report. The table in Appendix A lists the 16 SWCs and I I AWCs reviewed.

The Peer Review Team concluded that the walkdowns were conducted in accordance with the EPRI guidance.

The Peer Review Team has reviewed the Duke Energy walkdown report (Duke Energy Calculation CNC-i 206.03-00-0203, Futkushima Near-Term Task Force (7VTTb) Recommendation 2.3: NRC Submittal Report for Seismic Walk-downs, Attachment 7A, "Duke Portion of Walkdown.") The report describes the walkdown and summarizes the results. The report contains all of the information required by the EPRI guidance.

7.0 LICENSING BASIS REVIEWS All potentially adverse conditions require a licensing basis review in accordance with the EPRI guidance. For CNS, the licensing basis reviews were performed by Duke Energy Design Engineering personnel. Mr. Thomas Leitch performed most of the licensing basis reviews. He was assisted by Messrs. Raymond Fung, Robert Pryce, and David Kennedy. These individuals meet the personnel requirements in EPRI 1025286.

The walkdown of the inaccessible items identified four potentially adverse seismic conditions. As with the accessible items, each potentially adverse condition identified by the walkdown team was entered Page 4 CNC-1206.03-00-0203 Rev 1 A Page 8 of 15

NTF 2.3 SISMIc P-:ER REvII:Mw SUPII..EIMENTARY Report No. 1457690303-R-M-00004, Rev. 0 REPORT. CATAWBA NuCl-AR STATlON tJNrT I March 2013 into the CAP via the Problem Investigation Process (PIP) to enable tracking to closure. All of the items were entered into a single PIP, but they are listed separately. The Duke Energy Licensing Basis Reviewer stated that the licensing basis reviews were documented in the PIP associated with the potentially adverse conditions and no conditions were ibund to violate the CNS seismic licensing basis.

The potentially adverse seismic conditions identified by the wvalkdown of the inaccessible items are listed in Appendix B ofthe Duke Energy walkdown report. The peer reviewers verified that all of the potentially adverse seismic conditions listed in Appendix B of the walkdown report had licensing basis reviews documented in the referenced lI'll. The Peer Review Team reviewed the licensing basis evaluations fbr all of the potentially adverse seismic conditions and concluded that they were conducted in accordance with the EPRI guidance The peer reviewers also reviewed the licensing basis reviews for the items with comments provided to l)uke Energy during the September peer review. The Peer Review Team concluded that the comments were acceptably resolved.

8.0 DECISIONS ON ENTERING POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCESS All of the potentially adverse seismic conditions identified by the seismic walkdown of the inaccessible items were entered in the CAP for further evaluation. The Peer Review Team review of the seismic walkdowns determined that the identifications of potentially adverse seismic conditions were conservatively made. Thus, the decision to enter all of them into the CAP was likewise conservative.

The licensing basis reviews determined none of the potentially adverse seismic conditions violated the CNS licensing basis. Therefore, it was not necessary to perform any extent of condition evaluations.

The licensing basis evaluations of the potentially adverse seismic conditions identified enhancements, which were determined to improve the seismic condition of the plant. Work orders were assigned for implementation of the enhancements.

The Peer Review Team concludes that the decisions on entering potentially adverse conditions in the CAP process were in accordance with the EPRI guidance.

9.0 SUBMITTAL REPORT The Peer Review Team reviewed a draft of the revised submittal report for CNS Unit I provided by Mr. Thomas Leitch on March 12, 2013. The report contained the required sections and discussions.

Comments on the submittal were provided to Mr. Leitch on March 13, 2013.

The Peer Review Team concludes that the submittal report is in accordance with the EPRI guidance.

Page 5 CNC-1206.03-00-0203 Rev 1 A Page 9 of 15

N'PFF 2.3 Si-lsmic PiiizR Rvv.;vu

~

S.i'.IN1NI'ARY RFIrOiRT, CATAWBIA NUCLFAR STATION UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013

10.0 CONCLUSION

S The conclusion of the peer review is that the CNS NTTF 2.3 scismic walkdown for the inaccessible items has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the September 2012 peer review have been addressed satisfactorily.

11.0 REFERENCES

CB&I / ARES Technical Report 1457690303-R-M-00001, Seismic Wealkdowin Repoitijbr Duke Energy's Catawba Nuclear Station Unit I. Revision 2, November 14, 2012.

CB&J / ARES Technical Report 1457690303-R-M-00003, N77"F 2.3 Sei'inic Peer Review Report, Catawba Nuclear Station Units I and 2, Revision 0, November 18, 2012.

Duke Energy Calculation CNC-1206.03-00-0203, Fukutshima Near-T1erm Task Force (N7TF)

Recommendation 2.3: NRC Sitbmittal Reporl fior Seismic Walk-downs, Revision I, DRAFT, March 2013.

EPRI 1025286, Seismic Wclkdown Guidance/for Resolution of Fukushima Near-Term Task Force Recommendation 2.3. Seismic, June 2012, Electric Power Research Institute, Palo Alto, CA.

Letter, E. Leeds and M. Johnson (NRC) to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Tern Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3: Seismic," dated March 12, 2012.

Page 6 CNC-1206.03-00-0203 Rev 1 A Page 10 of 15

I Nil-E 2.3 Sf:'ISMlC P1iluI', RE-VIEW SuPi+/-LiiNENARY RiFio'oR CATAWBIA NUCLEAR STATION UN IT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013 APPENDIX A

SUMMARY

OF PEER REVIEW OF FINAL SWCs AND AWCs FOR INACCESSIBLE ITEMS Page A-I CNC-1206.03-00-0203 Rev i Attachment BA Page 11 of 15

NTTF 2.3 SEISMIC PEER REVIEW SUPPLEMENTARY REPORT Report No. 1457690303-R-M-00004, Rev. 0 CATAWBA NUCLEAR STATION UNIT 1 March 2013 Walkdown Team Members:

T. R. Leitch, Duke Energy R. C. Fung, Duke Energy J. D. Kennedy, Duke Energy Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID Equipment 50%

Non 50%

Line Overall Team Comments Class Anchorage Anchorage Mounted Status CVI El 557 Area Walkdown (De-58 Rad 40):

Reactor Bldg Leitch/

I.

WD centered around AOV INV52A Y

Funo

2.

No adverse conditions noted

n.

Apparently abandoned scgmcnt o01eCectray noted

4.

Photos included INV52A Leitch/

No adverse condition noted 7

L itc Minor interaction with air line: deemed insignificant Fung Photos provided CVI El 560 Area Walkdown (Deg 46 Rad 47)

Reactor Bldg I.

WD centered aroundlNI54A Leitch/

2.

No adverse condition noted Fung

3.

Loose locknut noted: Work Request generated (PIP 10589)

4.

Photos included INI0054A Leitcht No adverse condition noted 8

X Y

Lcth Documents referenced Fung__ _ _ _ _Photos provided CVI El 562 Area Walkdown (Deg 40 Rad 55)

Reactor Bldg Leitch/

I.

WD centered around IN1438A Y

Fung

2.

No seismically adverse condition noted

3.

Housekeeping: boron deposits noted on adjacent tubing:

work request initiated INI438A i

No adverse condition noted 8

Fling Documents referenced FIng Photos provided Page A-2 CNC-1206.03-00-0203 Rev 1 Attachment SA Page 12 of 15

NTTF 2.3 SEISMIC PEER REVIEW SUPPLEMENTIPARY REPORT CATAWBA NUCLEAR STATION UNIT I Report No. ]457690303-R-M-00004, Rev. 0 March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID Equipment 50%

Non 50%

Line Overall Team Comments Class Anchorage Anchorage Mounted Status CVI El 567 Area Walkdown (Deg 176 Rad 50)

Reactor Bldg I.

WD centered around pump IND2A tLeitch/

2.

Unattached cable runs noted in area; work request Kennedy initiated

3.

No seismically adverse conditions noted

4.

Photo provided IND2A Leitch/

No seismically adverse condition noted 8

X Y

Kennedy Safetly related cable fasteners and supports in degraded condition

"_noted; work request initiated (work order 02070468)

CV) El 568 Area Walkdown (Deg 176 Rad 25)

Reactor Bldg

1.

WD centered around pump I ND I B Leitch/

2.

No seismically adverse conditions noted Fung

3. Temporary shielding judged adequately supported; tubing as-found condition judged insignificant

_4.

Photos provided INDIB Leitch/

No adverse condition noted 8

X Y

litg Documents referenccd Fung Photos provided CVI El 635 Area Walkdown (DegI05 Rad 37)

Reactor Bldg Leitch/

I.

WD centered around 3 inline components

2.

No seismically adverse conditions noted 3ung Photos provided to illustrate congested but adequate clearance conditions INC34A Leitch/

No adverse condition noted 7

X Leth Documents referenced Fung_ _Comment provided wrt maintenance schedtle lbr component INC32B 7

l.,eitch/

No adverse condition noted Funn Photos provided INC36B No adverse condition noted Leitch/

Comment provided wrt maintenance schedule for component Fung Photos provided to illustrate congested but adequate clearance I_

conditions

.4.

Page A-3 CNC-1206.03-00-0203 Rev 1 Attachment BA Page 13 of 15

NTTF 2.3 SEIS.MIC PEER REVIEW SUPPLEMENTARY REPORT CATAB\\VIA NUCLEAR STATION UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items EDB ID Equipment j 50%

Non 50%

Line Overall Team Comments Cas Ancho Anchorage Mounted Status CV I I.156,s Area Walkdown (Deg 244 Rad 47)

Rczictor 1ldg 1

Leitch/

I.

WD centered around drain I

Kennedy

2.

No seismically adverse conditions noted

3. Comments/photos included describingfjustifýing minor

_ _conditions IF\\V8 I

Leitch SWEL 2 component 00 x

Y KNo seismically adverse condition noted Kennedy Documents referenced; photo provided CV I El 563 Area Walkdown (Deg 300 Rad 33)

Reactor Bldo y-Leitch/

1.

WD centered around drain Fung

2.

No seismically adverse conditions noted

3.

Comments describing/justifying minor conditions I1-FW46 Leitch/

SWEL 2 component 00 X

Y No seismically adverse condition noted Fung

_Documents referenced; photo provided RXI E1 557 Area Walkdown (Deg 280 Rad 58-63)

R13 Annulus I.

WD centered on 3 SWEL 2 components y

Leitch/

2.

No seismically adverse conditions noted Fung

3. Comments/photos included describing/justifying minor conditions, apparent good practice issue re: clearances INVI'D0042 SWEL 2 component 00 Leitch/

No seismically adverse condition noted 0

X Y

Fun Documents referenced; photos provided Fung Comments justify adequacy of close clearance/potential interaction condition NV865Leitch SWEL 2 component No seismically adverse condition noted Fung Documents referenced; photos provided

ý '

FI NV SUS5 Anchorage verified 5Leitch/

SWEL 2 component; anchorage verified x

Y Fung No seismically adverse condition noted Documents referenced; photos provided

_Background comments provided Page A-4 CNC-1 206.03-00-0203 Rev 1 A Page 14 of 15

NTTF 2.3 SEISMIC PEER REVwIW SUPPL.EMENTARY REPORT CATAWIBA NUCLEAR STA'rlON UNIT I Report No. 1457690303-R-M-00004, Rev. 0 March 2013 Summary of Peer Review of Final SWCS and AWCS For Inaccessible Items Equipment r 50%

Non 50%

Line Overall ID I

Team____

Comments Class Anchorage Anchorage Mounted Status l 31dg El IArea Walkdown (CC-55) 594 I.

WD centered on SSPS Train A cabinets Control Roon Y

Fung

2.

Required removal of some ceiling panels; opening of cabinets to complete

3.

No seismically adverse conditions noted "SSA I

Anchorage verified 1

Leitch/

No seismically adverse conditions noted 18 X

Fung Documents referenced; photos provided Background discussion included in form of comments AuN ido E1 Area Walkdown (Room 372 AA-51) 560 1.

WD centered on 2 transformers Leitch/

2.

No seismically adverse condition noted Fung

3.

Documents referenced; photos provided

4.

Discussion provided on resolution of apparent close clearance conditions I E"Xt ILech Anchorage verified Leitch/

No seismically adverse conditions noted Fung Documents referenced; photos provided Background discussion included in form of comments I ETXD Anchorage verified i

Xy Leitch/

No seismically adverse conditions noted 4

I Fung Background discussion included in form of comments to resolve I_

apparent close clearance condition op4#~

Page A-5 CNC-1206.03-00-0203 Rev 1 A Page 15 of 15

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 1 of 15 Executive Summary The results of the Catawba Unit 1 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns are provided herein. The walkdowns were performed in accordance with Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, as issued in June 2012. Catawba committed to utilize this guidance for the conduct of the seismic walkdowns via docketed correspondence dated 7/9M12.

The EPRI walkdown guidance provided guidance and procedures to perform seismic walkdowns as required by the U.S. Nuclear Regulatory Commission (NRC) 50.54(f) letter regarding NTTF Recommendation 2.3: Seismic.

The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components that represent diversity of component types and assures inclusion of components from critical systems / functions; conduct of the walkdowns, evaluation of potentially adverse conditions against the plant seismic licensing basis; and reporting requirements. It also includes checklists to be used by the Seismic Walkdown Engineers (SWEs) in the performance of the seismic walkdowns and walk-bys.

Revision 0 of the submittal report documented the results of the walkdown of accessible items in September 2012. Revision 1 of the submittal report adds the results of the walkdown of inaccessible items performed in November 2012.

The results of the walkdowns and licensing basis evaluations verified the adequacy of the Catawba monitoring and maintenance procedures with regard to the seismic licensing basis.

1,0 Seismic Licensing Basis Site Characteristics:

The major Category I structures such as the Reactor Building and the Auxiliary Building are supported on continuous rock (UFSAR 2.5.4.5). In areas where the continuous rock level is below the foundation bearing level, fill concrete was required to bring the area up to a suitable elevation.

Response Spectra:

The Catawba Unit 1 Safe Shutdown Earthquake (SSE) is conservatively specified to have a peak ground acceleration of 0.15g horizontally and 0.10 g vertically. The Operating Basis Earthquake (OBE) is 8/15 of the SSE at all frequencies (UFSAR 2.5.2.8 and CNS-1465.00-00-0007, section 3.3).

The ground response spectra curves are enveloped for analysis and design of all Category I building foundations on closely joined rock and slightly weathered rock and for all building elevations where the floor slab rests on rock or fill concrete.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 2 of 15 Structure, System and Component (SSC) Seismic Design:

All structures, systems and components required to shut down and maintain the reactor in a safe and orderly condition or prevent the uncontrolled release of excessive amounts of radioactivity have a seismic classification of Category I. The Catawba design complies with Regulatory Guide 1.29 for SSC seismic design requirements, with the exception of SSCs provided in the Westinghouse scope. The seismic design for the Westinghouse supplied SSC satisfied the classification of safety related systems and components as outlined by ANSI-N18.2a-1975 "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants" and is presented in UFSAR section 3.2. (CNS-1465.00-00-0007).

a Duke Class A, B, C piping per ASME Section I11, 1974, Class III (Reference UFSAR TABLE 3-5) a Duke Class A, B, C valves per ASME Section I11, 1974 (Reference UFSAR TABLE 3-6)

Duke Class F piping per ANSI B31.1, 1973 (Reference UFSAR TABLE 3-5)

Duke Class F valves per ANSI B31.1, Class Ill (Reference UFSAR TABLE 3-6)

Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.

& Regulatory Guide 1.48, "Design Limits and Loading Combinations for Category I Fluid System Components,"

May 1973.

Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nucl.ir Pet:."-- Plants," Revision 1, December 1973.

Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants," October 1973.

Regulatory Guide 1.92, "Combining Responses and Spatial Components in Seismic Response Analysis,"

Revision 1, February 1976.

Regulatory Guide 1.122, "Development of Floor Response Spectra for Seismic Design of Floor Supported Equipment or Componenls," Revision 1, February 1978.

Regulatory Guide 1.100, 'Seismic Qualification of Electric Equipment for Nuclear Power Plants," Revision 1, August 1977.

IEEE Standard 344-1971, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Station.

IEEE Standard 344-1975, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 3 of 15 2.0 Personnel Qualifications The personnel involved in the Catawba NTTF Recommendation 2.3 Seismic Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in rABLE 2-1 below.

Additional Peer Review Team experience is outlined within the Peer Review Summary Report (ATTACHMENTS 6A and BA).

TABLE 2-1 Personnel Qualifications SW E1 E

-o 6~

Qr

.2 Oa 0

ui~

PE Lu UX a)..

a)

X J

-~

0>

Bryan Hanna, P.E.*, (ARES-BS/Civi Engineering 12 SW E X

Kevin Rubright, (ARES)

BS/Civil Engineering 30 SWGE X

John North, P.E., (ARES)

BS/Civil Engineering 28 SWE X

X...

Anthony Fazio, (Shaw)

BS/Chemical

>40 SWE X

Engineering Philip Berdos, (Shaw)

BS/Mechanical SEngIineering 6

SWE

__X James Pappas, P.E.,

MS/Energy 31 SWE X

(Shaw)

Engineering James Adam, P.E., (Shaw)

IMS/Nuclear Engineering 4

S (2) x Tom R Leitch, P.E., (Duke)

BS/Civil Engineering 35 SWE (2)

X X

X X

J David Kennedy (Duke)

B/Civil Engineering 22 SWE t X '

Michael F Medlin, P.E.

25/Civil Engineering 31 SWE X'

X x

(Duke)

BS/Civi Enierig3_

Raymond C Fung, E.,

MS/Civil Engineering 32 S<X X

Duyke)

XQG 1

Robert L. Keiser P.E.,

MS/Civil Engineering

>20 SQUG X

(Duke)

>20_SWE___

__X Charles M. Conselman, P.E.

BS/Civil Engineering 28 SWE 2X)

(ARES)

Paul Baughman P.E.,

B5/Civil Engineering

>40 SQUG11t (ARES)

BCi

_Enned SW E12 Robert N Pryce (Duke)

BS/Mech Engineering 28 PSRO X

X X

Tom Baumgardner (Duke) n/a 45 PSRO X

X Fred Willis P.E., (Duke)

BS/Civil Engineern 32 X

Mark Shutt P E., (Duke)

BS/Civil Engineering 32 X

George Bushnell P.E.,

25CiilEninein 4+

WE 2 (Shaw)

BS/Civil Engineering 40+

SWE('

X NOTES:

1)

SQUG Seismic Capability Engineers (SCEs) have successfully completed SQUG training.

2)

SeismIcWalkdown Engineers (SWEs) have successfully completed EPRI 1025286 2 day walkdown training course.

3)

Senior Team Member

4)

Prior Senior Reactor Operator (SRO).

IL&

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 4 of 15 3.0 Selection of Equipment for the SWEL-1 and SWEL-2 Lists The Catawba Unit 1 SWEL-1 and SWEL-2 equipment selection was performed in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference CNC-1206.03-00-0202, Rev. 0).

SWEL -1 The EPRI SWEL-1 Screening Criteria #1 through #3 are as follows:

1) Seismic Category I licensing bases
2)

Exclude structures, penetrations, and piping systems

3)

Equipment must perform safety function (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, decay heat removal, containment integrity).

The EPRI screening criteria further allows major NSSS equipment inside containment to be excluded.

The original Catawba IPEEE Seismic Walkdown list (CNC-1535.00-00-0005, Rev. 3), was used as an initial "Base-1 List" of potential SWEL-1 walkdown components. After exclusion of non-seismic equipment, the prior IPEEE list effectively represents the output of EPRI guidance equipment Screening criteria's #1, #2 and #3. The Catawba Unit 1 SWEL-1 "Base-1 List" Is provided in ATTACHMENT 1A. Some equipment on the list is denoted as non-seismic and two non-seismic items were included on the final SWEL-1 equipment list.

EPRI Screening criteria #4 was then used to select equipment from this "Base-1 List." EPRI screening criteria

  1. 4 requires a representative cross-section of the following sample selection attributes:

include a variety of systems Include variety of types of equipment Include a variety of equipment environments Include major new/replacement equipment Include equipment enhancements implemented in response to prior IPEEE walkdown identified discrepancies The Catawba Unit 1 SWEL-1 equipment list (ATTACHMENT 2A) comprised 119 components in 26 different systems. The SWEL-1 list represented equipment from each of the EPRI guidance equipment classes, with the exception of Low Voltage Switchgear, Engine Generators, and Motor-Generator Sets. Catawba does not have any Seismic Cat I equipment within the motor generator equipment class. The SWEL-1 lists included equipment located in -40 different plant areas/rooms locations. The selected equipment locations represent a broad range of equipment environmental conditions (e.g. inside containment, partial outdoor exposure, electrical/mechanical penetration rooms, pipe-chases, control room, etc.). Modified, new, and/or replacement equipment comprised

-25% of the SWEL-1 list.

Significant modified/new/replacement equipment since the IPEEE was limited, and primarily included equipment such as battery racks/chargers/inverters, MOV/AOVs, and controls upgrades/replacements. Some of the items listed included equipment which was enhanced in response to the prior IPEEE walkdown effort.

The SWEL-1 component selection further considered PRA risk significance relative to the external seismic event.

The SWEL-1 component list included a broad sampling of components, which were identified to have a significant contribution to CDF for the external seismic event.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 5 of 15 SWEL -2 The Catawba Unit 1 SWEL-2 spent fuel pool equipment list was developed in accordance with the EPRI guidance. Seismic Category I structures, piping, and containment penetrations were specifically excluded by the EPRI guidance. The four screening criteria specified were as follows:

1) Seismic Category I licensing bases
2)

Spent Fuel Pool (SFP) equipment appropriate for an equipment walkdown process

3) Sample considerations represent broad population of equipment with considered sample selection attributes such as:
a.

represent a variety of systems

b.

major new/replacement equipment

c.

variety of equipment types

d.

variety of environments OR

4) Equipment which could result In rapid drain down of the SFP (includes both seismic and non-seismic components and similar factors outlined in 3) above, as practical).

The SWEL-2 equipment "Base-2 List" (ATTACHMENT 3A) was established based on screens #1 and #2 above.

Equipment was selected from the Base-2 List based on screening criteria #3 above, and primarily included major equipment such as the spent fuel cooling system pumps and heat-exchangers.

The SWEL-2 list was further supplemented based on screening criteria #4 above, to include equipment which could result In SFP rapid drain-down, as defined by the EPRI guidance.

The SWEL-2 Rapid Drain Down Equipment List is also provided in ATTACHMENT 3A.

The screen criteria #4 did not exclude non-seismic components from SWEL-2 selection. Due to the siphon and drain down resistant design of the spent fuel pool systems at Catawba, some manual valves and a strainer that would not be in the specific "classes of equipment" outlined by the EPRI guidelines were included in the "Rapid Draindown List". The final SWEL-2 list is provided in ATTACHMENT 4A and was comprised of 9 components.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 6 of 15 4.0 Seismic Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group / ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at Catawba Nuclear Station.

The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the accessible items, are provided in Attachment 5A 1. Duke Energy self-performed the NTTF 2.3 seismic walkdown of inaccessible items.

The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the inaccessible items, are provided in Attachment 7A.

The seismic walkdowns and area walk-bys were conducted in accordance with the guidance outlined in EPRI Report 1025286. The EPRI Seismic Walkdown Checklists (SWC)s were completed for each equipment item on the SWEL. The EPRI Area Walk-By Checklists (AWC)s were completed for areas/rooms associated with SWEL equipment.

The component seismic walkdown inspections were primarily focused on the identification of potentially degraded component anchorage conditions, and potentially adverse seismic interactions with surrounding SSCs.

For the non-line mounted components, the visual inspections assessed whether the anchorage was degraded (e.g. bent, loose, broken, missing, corroded, localized concrete cracks). Additionally, for at least 50% of the non-line mounted components, the as-built field anchorage was verified to be consistent with design documentation.

The area walk-by inspections were performed for SWEL equipment areas. The area walk-bys assessed whether other surrounding equipment in the area/room (up to either 35' radius around SWEL component or the entire room containing the SWEL component) had potentially degraded anchorage, or whether the potential for adverse seismic interactions were present.

If the Seismic Walkdown Engineers (SWEs) determined a potentially adverse seismic condition existed, then thie issue was entered into the corrective action program (CAP) to allow further engineering evaluation. The CAP engineering evaluation determined whether the potentially adverse seismic condition was degraded, unanalyzed, or non-conforming to the design and licensing bases.

Seismic Walkdown Checklists (SWC) have been completed for all of the components listed on the SWEL. This total is comprised of 119 SWEL-1 components, and nine SWEL-2 components. Sixteen of the SWCs, which were inaccessible2 during the ShawtARES walkdown, were completed by Duke personnel. Fourteen of these p.,

were completed during the outage, and two were completed prior to the outage. For the non-line mounted L\\K SWEL equipment, an anchorage as-built verification was completed for 76% of the equipment with anchorage.

Additionally, a total of 76 Area Walk-Bys Checklists (AWC) were completed. Eleven AWC's were completed by Duke personnel during the outage.

The seismic walkdowns and walk-bys identified 40 "Potentially Adverse Seismic Conditions", which are itemized in TABLE 4-1.

Refer to the notes for the walkdown items for the "CAP Disposition" explanation. Each of the potentially adverse seismic conditions was entered into the CAP. Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. InL\\

some cases work requests or CAP ACTIONS were initiated as required to resolve minor issues and/or to enhance/evaluate field equipment clearances.

Potentially Adverse Seismic Condition #33 is not listed in Appendix B of ATTACHMENT 5A. It was imported from the Unit 2 walkdown report as a shared equipment walkdown Item.

1CNS documented the submittal attachments as 1A, 2A, etc. for Unit 1, and 1B, 2B, etc. for Unit 2.

Fourteen were Inaccessible during plant operation. Two had anchorage partly obscured and work orders were required to access the obscured anchorage.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 7 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potenlially Adverse Condition Disposition (See notes)

1) Romn 400, NN-53 Poorly restrained small cable tray with polential tbr interaction with 10" fire water header. Also.

Walk-by for poi-lateral support of.iunction box that coHsts-.ts flCxiblC c0ndtuitlcabling to I RNTE5010.(Nois-1,9 I RN225 B QA) It has a potential for cnble to tear out ClUring n seismic event and lose function.

1,arge bore RF lite (approx. 10" dia.) and branch lines arc generally very poorly latcrally

2) Room 400, NN-53 restrained throUtghout the area. One instance the unrestrained 10" line is toUCtiing I vertical Walk-by for support Ibr the RN Return H leader. I-1/4" din. SS line (no label; dark-bloc pain)) ruits through 2, 9 I RN2253 tilse area and is poorly-SUpported (laterally). Potential for seismic interaction in several locations.
3) Room 407, QQ-61 A continuations Iiom other walk-down areas (see AWC for Atix, 577', Room 400, QQ-60 area)

Walk-by for of unsupported stainless steel piping (app'ox. 2" to 2-1/2" line / Refl" Deminenalizcd Water) is 1,9 IWakN58B poorly supported (laterally) and is likely to interact with various structures and fcntures during a

.5seismic event and cause tlooding or sprit.

,I) Room 400, 1..,-

53: Area Walk-RF line valve I RF254 actuator stem is within 3/16" of vertically-mounted TS Mx8 (approx). The 1,9 By for I KC8113B R1 line on which the valve is mounted (inline) is poorly supported (laterally).

5)

Room 400, LL-VVB breaking nir line and YM dcrifseralization. Water lines are poorly supported and are 53: Area Walk-currently touching near L..-53. Also, WE (Equipment Decontamination) lines in the amen are 1,9 B)' for I KC813 B poorly laterally supported.

Door 4809 associated with the adjacent Unit I, 113 Battery Elnclosure opens outward toward

6) 1 DGCB: 11.t subject equipment. The door can only open about 8-9 inches and cannot be used for access.

Diesel Generator I l

'owcvr, the door could be accidentally opened from the inside of the enclosure and could 1, 9 Battery Charger strike the subject equipment.

7)

Aux Bldg, 594',

Room 500, NN-Base orNon-QA ONFIHG (NF Ice Bin) has boric acid around perimeter. The white residue and 2, 9 59 Area Walk-By corrosion is at anchors and drains.

for I KCTKB

8) DHI (Inner), FF-53: Area Walk-By foA I SVc,

Scaffold storage needs tie-back to "dedicated" tic-off point, approved by engineering 1, 9 BySAS, afnd department. Also, one ladder eot tied back.

I SV26B

9) 1VGCPBI: IBI Four anchor bolts total. The two bolts on the east side have mild corrosion with the bolt in the EDG Starting Ai' NE corner having the most serious corrosion.

1, 9 Compressor

10) IVGCPBI: IBI An adjacent hand wheel chain for EQ I RNP08 hangs low enough such that it could impact or EDG Sting Air become entangled with the subject equipment.

Compressor T1:

wo adjacent fire extinguishers (one each containing C02 and water) are hanging from small 11)Room 372, BB-5 hooks and could jump offduring a seissIlic event. The extinguishers could discharge retardant I EADB and could lurch across the floor and strike adjacent equipment. These hooks should be evaluated to confirm the extinguishers will not jump off.

12) Yard, Bottom of IFWTK0001 Containment Basin:

Area Walk-By for Unistrut base for cable tray support and various instrumentation cabinets are severely corroded.

2, 7 1FWLTSOO,I FWL T5010, IFWTKOI, and FWLT5130

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 8 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions Walkdown Item Polentially Adverse Condition CAP Disposition (See notes) 13)] FWI..T5000:

FWST WR Level Channel

  1. 1l Instrumentation panel angle frame supports and associated wedge anchors arc severcly oxidized

/ corroded.

2,7

14) I F W L r5010:

]:WST \\VR.

Instrumentation panel angle roani sujoporls antd associated %%edge anchors arc severely oxidized 2,7 Level Channel

/ colroded.

2 15)1ECA: 125VDC CN-1214-08.08 Rev does not i ndicatc weld al the inierrace beween chnrger bottom rnr aue d Vital Battery field-installed plates. See section C-C. (Shown on CN-1214-08.08 Rev 1A) 3,9 Charger L16)

IEBA: IA ESSENTIA I, One ( I) achoIr nut appCarsi to lack full engagement with the anchor stud. Location of specilic BATIAL slud/nut: starting fioom doorway to battery rack enclosure find the second row ol'baltery 1, 6 BATTERY rack/frame anchors. Observe second anchor in from aisle way.

RACK

17) Aux Bldg, 543',

Room 23!, 11,-

55: Area Walk-Valve I NV203A has a heavy operator with long moment arm and should be verified against By for design isometric drawing. (Duke comment - This is a rigorously analyzed system) 1, 9 I NVIIU13CC and INV202B

18) 1 EMXB: 600 VAC Essential Motor I out o1"96 bolts are missing (below bucket IEMXB FOID: back-left bolt location).

1, 8 Control Center

19) AWC Aux Bldg, An approx. 214" diameter fire suppression pipe is suspended by threaded rods and clevises. Rods 554', Rm 350 5-545: Are 350 are approximately 20 feet long. End of rod at lower end is adjacent to Unistrut. Clevis can swing BB-5455: Area into Unistrut. Pipe connections are welded. Pipe may become damaged by interacting with 1,9 Walk-By for Unistrut. (Duke comment -Evaluation determined interaction is limited to minor scraping)

IEID and IEIF 20)1 [1F: t20 VAC Vital An approximately three inch diameter rigid electrical conduit sweeps 90 degrees from I ElF to Swing nlverter Unistrut support. Unistrut is connected to column and to a network of Unistrut which is also 2, 9 connected to ceiling (upper diaphragm)...__

21) ALIx Bldg, 543',

Room 2t7,FF53-JJ51: Area Walk-By There was a missing stud and nut on a base plate fora stand-off arm for instrument fortNt185A.

tubing1 WLIV606I(Non-QA).

2,9 INV77A, and INV312A

22) Aux Bldg, 543',

Room 217,FF53-Relatively congested to very congested area. There was a hand wheel for 1FW24 (4" line) that is J.J5 1: Area Walk-By about 3/8" from a perpendicular pipe (lYN127) (Non QA '" dia pipe). During seismic event 1,9 forlNt185A, INV77A, and interaction line could damage both pieces of equipment.

INV312A

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 9 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potentially Adverse Condition Disposition (See noteg)

23) Aux Bldg, 594',

Room 570, Various:

Area Walk-By forICRA-C-I CP, I CRA-C-I condenser head pressure transmitter (OYCPT6120) has vulnerable tubing which ICRA-C-I,ICRA-could be compromised by lateral displacement of operator for I YC6 (YC Chiller A Supply to 1,9 PFT-l, ICRA-Channel A Header Isolation). (Duke verified OK per CNC-1206.02-89-2003)

PFTF-I, CR-AHlU-1, ICRA-D-1, and OYCPUCWI

24) Aux Bldg, 594",

Room 570,Various:

Area Walk-By forlCRA-C-I CP, Operator could be damaged (stein) due to potential impact with rigid veir. Support for control ICRA-C-lICRA-1, lRT-I,ICRA.

panel. Approx 1.25" gap. (Duke verified OK per CNC-l1206.02-89-2003) 1,9 PFTF-lICR-AI-U-

1. ICRA-D-1, and OYCPUCWI
25) Aux Bldg. 594',

Room 570,Various:

Area Walk-By for] CRA-C-I CP, 1YC5 (YC Chiller A supply to channel A header drain) has only a 3/16" gap from hand wheel ICRA-C-I. CRA-2 PFT-rI, ICRA-to adjacent YC drain.

PFTF-I,ICR-AHFU-1, ICRA-D-1, and OYCPUCWI

26) Aux Bldg, 594',

Room 570,Various:

Area Walk-By forlCRA-C-l CP.

ICRA-C-I,ICRA-I" O.D. drain line has an approximately I" gap from IYC5 drain.

2, 9 P'FT-1, ICRA-PFTF-I,l CR-AHU-1, ICRA-D-t, and OYCPUCWI

27) Room 234, Aux Bldg, 543'% Area A VQ system pipe (approx. 4" dia. CS) is within 1/8" of safety injection pump suction line Walk-By for vertical restraint. The VQ system line is only supported vertically with clevis hangers, and IN[PUB, would interact significantly with the suction line vertical restraint.

1, 9 1MV253B,IN1136B

, INl144A, Approx. mid-line on the 4" VQ system line is a flange connection and a likely source of leak or INII47B, and spray.

IKCHX0052

[28) RN Pump Hotuse, Pit A, Area Walk-Safety hoist located over access shaft could swing toward adjacent wall and impact adjacent By for IRN.30 A, spiral tubing. Recommend securing hoist to access shaft handrail.

2, 5 and ORNLT7390.

29) 1 FWLT5130 FWST Instrumentation panel angle frame supports, and associated wedge anchors arc severely 2, 7 WR Level Ch4 oxidized/corroded.*(Also, see item 13) 2, 7 30)Area Walk-By for No lateral bracing in the weak direction for IDCSMC2. (QA-4).

Impact on other panels is 2,9 1MCI and 2MC2 unknown.

2,_9

31) DHI, 587',Room 591: Area Walk-By 1Wz conduit is loosely attached to ICA149 (QA-1) termination box (I2"x12"x6") for limit 2,9 for I CA62A and switches.

ICA66B

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 10 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potentially Adverse Condition Disposition ISoe notes)

32) 1CRA-c..

CP:

Anchorage system is very robust for seismic loads, Bolts appear to be 518' O.D. Still requires Chiller Comp Cont.

2,9 Panel "A" Trn drawing verification.

33) Aux Bldg 594, Room 560, FF-59 Area Walkby for Corrosion: AHU plenum has rusty anchor bolts.

2, 9 2CRA-FAN

,(2CtRA-MU-1)

34) 2CRA-FAN Anchorage layout dimensions were verified; however current licensing basis were not available 2,9 (2CRA-AHU-I) to verify anchor bolt sizes.
35) 2CRA-FAN Hardware: Four anchor bolts are slightly bent. Up to approx. 3/8" gap is created between one 3

(2CRA-A.HU-I) side of nut and mounting flange.

___3,_9

36) CV 1.560' Dcg 46, Loose locknut on rod supporting I WL820 could lead to support failure unless corrected. This RAD 47, Area 2,9 Walkby for I NI54A was corrected on 12/08/2012 per work order 02070034.
37) CVI, 567', DEG Electray marked 140722 not secured to unistrut due to missing/loose fasteners, and cables are 176, RAD 50, Area not well attached to the tray due to missing/loose straps. These cables attach to I ND37A. This 2, 9

\\Valkby for IND2A.

was corrected on 12/11/2012 per work order 02070453.

38) cvM, 567',DEG Nue, Safety RO. cables run fTom the valve operator to ajunction box. Box found not fastened 176, RAD 50 to the unistrut support that goes to the wall due to fasteners between box and Unistrut being Seismic Walkdown either loose or missing. During Seismic event, box could fall off unistrut and only be supported 2, 9 for IND2A.

by cables. Resolved per work order 02070468, completed 12/11/2012.

SWEL-2

1)

IK.FPUA: IA Spent Fuel Pool Pump A conduit/cable attached to a temperature element on one of the pump bearings, via a cable tray-mounted junction box has very little slack (IKFTE5330)(Non QA). The installation is further subject to adverse seismic interaction due to a lack of support for the cable tray that supports the J-box. A similar situation exists with a conduit/cable, sensor, and cable tray-supported J-box at the rear pump motor bearing.

R

2)

CVI 568' DEG 244, RAD 47, Noted that first tubing clamp off operator for I VP7A is loose. This is VI tubing attached to Area Walkby for 1 V13690. Resolved per work order 02070028, completed 12/15/2012.

2,9 I FW8 CAP DISPOSITION Notes:

1) Field configuration m Current Licensing Bases (CLB) requirements, and no field work required.
2)

Field configuration meets CLB requirements; however, work request/work order/ACTION initiated to resolve minor issue, verify unknown condition, or enhance/correct field configuration.

3) Field configuration meets CLB requirements; however, design drawing updated to reflect field configuration.
4) CLB not met, and required field modification. (No items required this designation.)

A "N I&L

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 11 of 15

5) Lifeline hoist at RN Pumphouse was found installed such that it may contact safety related tubing during a seismic event. The hoist was secured such that no adverse interaction would occur during a seismic event,
6)

Battery 1EBA rack anchor (one of 48) identified to have less than full thread engagement which was evaluated and determined to be acceptable. Also, the hoist in the lEBA Battery Room was evaluated for potential seismic interaction and it was determined that there is nothing in the travel path which would be contacted if the hoist moved.

7) The mounting bolts for the Refueling Water Storage Tank level transmitters were evaluated for corrosion and determined to be robust and acceptable as is. Work Request 01073777 will be used to address/refurbish the corroded mounts.
8) One (of 96) mounting bolt was found missing on Motor Control Center 1EMXB. Engineering initially determined that, based on the total number of mounting bolts, seismic anchorage is adequate.

Subsequent review of drawing CN-1214-01, Rev. 46 (on type 4 mounting base plan view) discovered a note allowing the omission of this bolt per NCI 3479.

9) Less significant item, identified in the CAP to drive appropriate actions or document disposition of the issue.

INACCESSIBLE COMPONENTS:

Unit 1 components that were Inaccessible until the next unit shutdown are listed in TABLE 4-2. There were A

fourteen of these components.

These component seismic walkdowns and associated area walk-bys were completed by Duke Energy during the outage.

TABLE 4-2 Walkdown Inspections Performed in Fall Refueling Outage Location' EquiprpentID Narntale :'

1 Reactor Bldg.

1NV52A 1A NC PUMP SEAL RETURN 1

Reactor Bldg.

1NI54A C-Leg Accum A Discharge Isolation 1

Reactor Bldg.

1N1438A Emergency N2 From CLA to 1NC-34A 1

Reactor Bldg.

1ND2A ND Pump 1A Suct From Loop B 1

Reactor Bldg.

INDIB ND Pump IA Suct From Loop B 1

Reactor Bldg.

1NC34A Unit I PZR PORV 1

Reactor Bldg 1 NC32B Unit I PZR PORV 1

Reactor Bldg.

1NC36B Unit 1 PZR PORV 1

Reactor Bldg.

1NV865A SBMUP Suction from xfer Tube 1

Reactor Bldg.

VFW8 Refueling Cavity Drain 1

Reactor Bldg.

1FW46 Refueling Cavity Drain 1

Annulus.

1NVPDO042 SBMUP Discharge Pulsalion Dampener 1

Annulus 1NVPUSB Standby Makeup Pump (NV) 1 Control Room 1SSPSA Solid State Prot Sys TT A

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 12 of 15 RESOLUTION OF UNKNOWN ITEMS There were a total of eighteen SWCs originally designated to be "unknown" in the walkdown report in Attachment 5A. The resolution of these items is described below.

There were three SWCs in the Auxiliary Building which were designated "unknown."

It o

Two SWCs were associated with plant operations activities which would not allow access during the walkdown time frame. These items were 1ETXA (4160/600 VAC Transformer) and 1SSPSA (Solid State Protection System).

1ETXA was removed from the list and replaced with 1ETXB (4160/600 VAC Transformer). This item was walked down by Duke Energy.

1SSPSA was walked down during the fall Unit 1 outage (see Table 4-2).

One SWC (iEMXC) was inaccessible at the time of the walkdown. Also some anchors were not visually IA->

accessible.

1EMXC was removed from the list and replaced with 1ETXD (4160/600 VAC Transformer).

This item was walked down by Duke Energy.

There were eight items from the SWEL-1 list that were designated to be "unknown" because they are located in the Reactor Building.

These eight items are shown in Table 4-2. They are INV52A, 1N154A, 1N1438A, 1ND2A, 1NDIB, 1NC34A,

(,4 1NC32B, and 1NC36B. The walkdowns were performed by Duke Energy during the fall 2012 refueling outage.

There were five items from the SWEL-2 list that were designated to be "unknown" because they are located in the i*L*

Reactor Building.

These items are shown in Table 4-2. They are 1NV865A, 1VFW8, 1FW46, 1NVPD0O42, and 1NVPUSB.

They were all walked down by Duke Energy during the fall 2012 refueling outage.

A_

There were two items from the SWEL-1 list that were designated to be "unknown" because the anchorage could not be completely verified. They were resolved as described below:

1FWTK01 - Due to enclosure of the tank with sheet metal siding material, the anchorage was not visible and the anchorage configuration could not be verified. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program. This was documented in PIP.

1 DGBNGC - Anchors between the Unistrut and the concrete wall are not visible or accessible. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program.

The Unistrut and the anchors from the cubicle to the Unistrut were confirmed in very good material condition, and the location environment is mild most of the time. This was documented in PIP.

5.0 Licensing Basis Evaluations As shown in Table 4-1, a total of 40 potentially adverse seismic conditions were identified by the seismic walkdowns and area walk-bys. Also, one issue with the anchor bolts for 0YCPUCW1 was identified during the TI-188 walk-down inspection with the regional NRC inspector. All of the potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to correct minor issues and/or to enhance fiela equipment clearances.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 13 of 15 The potentially adverse seismic conditions and their individual Problem Investigation Process (PIP) tracking numbers are listed in the Unit 1 NTTF 2.3 Seismic Walkdown Summary Reports (Attachment 5A and A).

6.0 IPEEE Vulnerabilities The Catawba IPEEE NRC submittal of 6/21/94 (Reference 8) concluded that there were no seismic vulnerabilities from external events.

Thus, there were no identified plant changes which would significantly reduce the risk from seismic external events. Table 3-3 of the IPEEE NRC submittal identified one enhancement to resolve minor field walk-down issues, This enhancement is described in Table 6-1.

TABLE 6-1 IPEEE Enhancements Equipment Deficiency Identified Resolution Date Resolved Installed missing spacers, added Unit 1 EDG battery racks were missing dummy batteries, stiffened side spacers.

rails. Later replaced batteries and 09/28/2005 racks with new design.

(EC12956) 7.0 Peer Review Duke Energy (Duke) contracted with the Shaw Group (Shaw) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). The Peer Review Report is contained in ATTACHMENT 6A.

The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the activities. The peer review team is identified in Table 2-1 and their qualifications are provided in ATTACHMENT 6A.

The Shaw/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The peer review covered the following:

The selection of the SSCs included on the Seismic Walkdown Equipment List (SWEL).

A sample of the checklists prepared for the seismic walkdowns and area walk-bys.

The licensing basis evaluations.

The decisions for entering the potentially adverse conditions in the Corrective Action Program (CAP) process.

The submittal report.

The peer review process for the SWEL development and the seismic walkdowns consisted of the following:

Reviewing the activity guidance in EPRI 1025286, the NEI Q&A bulletins, the NEI first-mover reports, and NRC Temporary Instruction 25151188.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 14 of 15 0

Conducting an in-process review at the plant site, including interviews with the personnel performing the activity and reviewing in-process documentation.

0 Performing an in-plant surveillance (for the walkdown activity) of a seismic walkdown and an area walk-by.

6 Providing in-process observations and comments to the personnel performing the activities.

a Conducting a final review of a sample of the completed documentation.

The peer review process for the licensing basis evaluations and the decisions for entering potentially adverse conditions into the CAP consisted of reviewing the overall review process and a sample of the licensing basis reviews. The peer review process for the submittal report consisted of reviewing the draft submittal prepared by Catawba Design Engineering for licensing review.

The peer review identified several items, previously added to the Corrective Action Program, which may need IIN additional detail with respect to the licensing basis review. It should be noted that these items were not considered in error, only that they may require more specific detail in the licensing basis evaluation to document that they were thoroughly assessed.

The Items identified by the peer review were reviewed by CNS Civil Design Engineering. Additional detail was added to each, as appropriate to document the licensing basis evaluation.

The bulleted items of Section 1 (Purpose and Approach) of EPRI 1025286 were reviewed and determined to be properly assessed by the Peer Review Team. The conclusion of the peer review was that the CNS NTTF 2.3 seismic walkdown effort has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the in-process review of the SWEL development and the walkdowns have been addressed satisfactorily.

Following completion of the walkdown of the inaccessible items by Duke Energy, the Peer Review Team performed a supplementary peer review. This is described in the Supplementary Peer Review Report in Attachment BA. The supplementary peer review covered the walkdown of the inaccessible items and resolution of the comments on the licensing basis evaluations.

REFERENCES:

1) CNS-1465.00-00-0007, Rev. 2, Seismic Design Bases Specification Document
2)

UFSAR Section 3.2.1 Seismic Classification

3) UFSAR Section 2.5.1.2 Site Geology
4)

UFSAR Sections 2.5.2.6, 2.5.2.7 SSE/OBE

5)

UFSAR Section 3.7 Seismic Design

6)

CNC-1206.03-00-0202, Rev. 0, 10CFR50.54(f) Rec. 2.3 Fukushima Seismic Walkdowns

7)

EPRI Report 1025286, Dated June 2012, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 B) Catawba Response to GL 88-20, Individual Plant Examination of External Events (IPEEE) Submittal, dated June 21, 1994, D.L. Rehn to NRC.

9)

CNC-1 535.00-00-0006, Rev. 0, Seismic Hazard Curve Sensitivity for the Catawba IPEEE.

10) CNC-1 535.00-00-0005, Rev. 3, Seismic Capacity Evaluations for IPEEE and EPRI Margins Study.
11)

Equipment Deficiencies Identified During the 1994 IPEEE Seismic Walkdowns - (See Ref 8 Table 3-3).

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 15 of 15

12) CNS-1 108.00-00-0002, Rev 11 "Specification for the Response Spectra and Seismic Displacements for Category I Structure
13) 719/12 correspondence to NRC from Ben C. Waldrep, "Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident" ATTACHM ENTS:

1A) Catawba Unit 1 SWEL-1 Base-1 List 2A) Catawba Unit 1 SWEL-1 3A) Catawba Unit 1 SWEL-2 Base-2 List and Rapid Drain Down List 4A) Catawba Unit 1 SWEL-2 5A) Seismic Walkdown Summary Report and Checklists (Shaw/ARES Report) 6A) Peer Review Summary Report 7A) Seismic Walkdown Summary Report and Checklists (Duke Report) 8A) Supplementary Peer Review Report

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