ML13162A092
| ML13162A092 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/28/2013 |
| From: | Henderson K Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13162A092 (166) | |
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.*
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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.
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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
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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.
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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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~
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CNC-1206.03-00-0203 Rev 0 A Page 8 of 36 AT-T I1 O CN(
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GENERIC LETTER 88-20; SUPPLEMENT 4 INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT I
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Prepared By Reviewed By Approved By
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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
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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
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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
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 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_
x AOV 1Ni57 0.75 X
AOV 1N8 0.75 x
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
6 X
SG S1V ISV15 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 LOAD CENTER 1ELXA 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
___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
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 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
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 I
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
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)____
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)
MOV 1NS18A 12 MOV 1NS29A (32A) 8 4160V AC SWITCHGEAR 1ETA (0ETB)
.I"DCPANELBOARD )EIDE (IEDF]
Une Included in Press, bndry, VX SYSTEM Size (in.)
Seismic PRA Integrity only AIR-OP. DAMPER 1ARF-D-5 (-8)
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_
MOTOR-OP. DAMPER 2ARF-D-2 (-4)
CONTAINMENT AIR RETURN FAN 2A (28)
'.I
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)
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.
CNC-1206.03-00-0203 Rev 1 A Page 29 of 105
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-~
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)
Equipment ED No. 1NC34A Equip. Class' 7 (AOV)
Equipment Description PZR PORV Photo ra hA Note: INC34A Note:
Note:
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)
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.
CNC-1206.03-00-0203 Rev 1 A Page 54 of 105
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[
NF-U[-]
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
__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
- 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
- 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
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.
- 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