ML12348A087
| ML12348A087 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/27/2012 |
| From: | Constellation Energy Nuclear Group, EDF Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12348A087 (175) | |
Text
ATTACHMENT (1)
SEISMIC WALKDOWN REPORT Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT (2)
EQUIPMENT LISTS Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT (3)
WALKDOWN CHECKLISTS Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT (4)
AREA WALK-BY CHECKLIST Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT (5)
INACCESSIBLE EQUIPMENT AND PEER REVIEW Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT (6)
REGULATORY COMMITMENTS CONTAINED IN THIS CORRESPONDENCE Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT 5 REGULATORY COMMITMENTS CONTAINED IN THIS CORRESPONDENCE The following table identifies actions committed to in this document by (station). Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
REGULATORY COMMITMENT DUE DATE Perform follow-up inspections of equipment anchorages and By the end of the NMP2 refueling electrical cabinets as discussed in the Seismic Walkdown outage in Spring 2014.
Report.
Submit results of follow-up inspections of equipment Within 60 days after the end of the anchorages and electrical cabinets as discussed in the NMP2 refueling outage in Spring 2014.
I
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table of Contents List of Tables.........................................................................................................
Executive Summary.................................................................................................
iii I INTRODUCTION....................................................................................................................
1-1 1.1 Background..................................................................................................................
1-1 1.2 Plant Overview.............................................................................................................
1-1 1.3 Approach......................................................................................................................
1-1 2 SEISM IC LICENSING BASIS...........................................................................................
2-1 2.1 Overview......................................................................................................................
2-1 2.2 Seismic Design.............................................................................................................
2-1 3 PERSONNEL QUALIFICATIONS.........................................................................................
3-3.1 Overview......................................................................................................................
3-1 3.2 W alkdown Personnel...................................................................................................
3-1 3.3 Additional Personnel....................................................................................................
3-3 4 SELECTION OF SSCS......................................................................................................
4-1 4.1 Overview......................................................................................................................
4-1 4.2 SW EL Development................................................................................................
4-1 5 SEISM IC W ALKDOW NS AND AREA W ALK-BYS.......................................................
5-1 5.1 Overview......................................................................................................................
5-1 5.2 Seism ic W alkdowns................................................................................................
5-1 5.3 Area W alk-Bys.............................................................................................................
5-2 5.4 Supplemental Information On Electrical Cabinet Internal Inspections....................... 5-2 6 LICENSING BASIS EVALUATIONS....................................................................................
6-1 7 IPEEE VULNERABILITIES RESOLUTION REPORT.........................................................
7-1 8 PEER RE VIEW........................................................................................................................
8-1 8-1 Peer Review Introduction.............................................................................................
8-1 8.2 Peer Review - Selection of SSCs.................................................................................
8-2 8.3 Review of sample checklist & area walk-bys..............................................................
8-4 8.4 Review of licensing basis evaluations.........................................................................
8-8 8.5 Review of final submittal Report & Sign-off...............................................................
8-9 9 REFERENCES.........................................................................................................................
9-1 Appendicies A PROJECT PERSONNEL RESUMES AND SWE CERTIFICATES.....................................
A-I
ATTACHMENT 1 SEISMIC WALKDOWN REPORT List of Tables Attachment I Table 2-1 NMP2 Summary of Design Codes Table 3-1 Personnel Included in NTTF 2.3 Table 4-1 SWELl by Equipment Class Table 4-2 Safety Class Representation among selected SWELl Components Table 5-1 Table of potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile 2 Identified During Walkdowns Table 5-2 Table of potentially Degraded, Nonconforming or unanalyzed Conditions for Area Walk-bys at Nine Mile 2 Identified During Walkdowns Table 7-1 IPEEE Improvements or Initiatives for NMP2 Table 8-1 Table of SWC and AWC Samples from Seismic Walkdown Inspection for Unit 2 Table 8-2 Table of Actions Resulting from Seismic Walkdown Inspection for Unit 2 Table B-I Nine Mile Point Unit 2 SWELl Base List Table B-2 Nine Mile Point Unit 2 SWEL2 Base List Table B-3 Nine Mile Point-2 SWELl Table B-4 Nine Mile Point - 2 SWEL2 Table C-I Summary of Seismic Walkdown Checklists Table D-I Summary of Area Walk-By Checklists Table E-I Summary of Inaccessible Equipment Table E-2 Summary of Equipment Subject to Supplemental Internal Inspections ii
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Executive Summary This report documents the seismic walkdowns performed at Nine Mile Point Nuclear Station Unit 2 (NMP2) in response to the 50.54(f) letter issued by the NRC.
The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter, Enclosure 3, Recommendation 2.3: Seismic [Ref. 10]. The guidelines and procedures prepared by NEI and endorsed by the NRC were published through the Electric Power Research Institute (EPRI) as EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 [Ref. 1]. Nine Mile Point Unit 2 has committed to using this NRC-endorsed guidance as the basis for these walkdowns and this report.
EPRI Technical Report 1025286 was used to perform the engineering walkdowns and evaluations described in this report. In accordance with EPRI Technical Report 1025286, the following topics are addressed in the subsequent sections of this report.
Seismic Licensing Basis Personnel Qualifications Selection of Systems, Structures, and Components (SSCs)
Seismic Walkdowns and Area Walk-Bys Seismic Licensing Basis Evaluations Individual Plant Examination for External Events (IPEEE) Vulnerabilities Resolution Report Peer Review Seismic Licensing Basis The Seismic Licensing Basis for NMP2 is briefly described in Section 2 of this report. Detailed information regarding site seismology and seismic design of systems, structures, and components (SSC) is discussed in Updated Final Safety Analysis Report (UFSAR) Chapters 2 and 3 respectively. (Ref. 2)
Personnel Qualifications Personnel qualifications are discussed in Section 3 of this report. The personnel who performed the key activities required to fulfill the objectives and requirements of the 50.54(f) letter are qualified and trained as required in EPRI Technical Report 1025286 [Ref. 1]. These personnel are responsible for:
" Selecting the SSCs that should be placed on the Seismic Walkdown Equipment List (SWEL)
" Performing the Seismic Walkdowns and Area Walk-Bys iii
ATTACHMENT 1 SEISMIC WALKDOWN REPORT
" Performing the seismic licensing basis evaluations, as applicable
" Identifying the list of plant-specific vulnerabilities identified during the IPEEE program and describing the actions taken to eliminate or reduce them
" Performing the peer reviews Selection of SSCs Selection of SSCs is discussed in Section 4 of this report. The process used to select the items that were included in the overall Seismic Walkdown Equipment List (SWEL) is described in detail in EPRI Technical Report 1025286, Section 3: Selection of SSCs [Ref. 1]. In general, the SWEL is comprised of two groups of items, which are described at a high level in the following subsections.
Sample of Required Items for the Five Safety Functions - SWELl Screen #1 narrowed the scope of SSCs in the plant to those that are designed to Seismic Category I requirements because they have a seismic licensing basis.
Screen #2 narrowed the scope of SSCs by selecting only those that do not regularly undergo inspections to confirm that their configuration continues to be consistent with the plant licensing basis. Cable/conduit raceways and Heating, Ventilation and Air Conditioning (HVAC) ductwork, although not included as "equipment" in the SWEL, were reviewed during area walk-bys of the spaces containing items on the SWEL.
Screen #3 narrowed the scope of SSCs included on SWEL 1 as only those associated with maintaining the five safety functions. These five safety functions include the four safe shutdown functions (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, and decay heat removal, which includes the Ultimate Heat Sink), plus the containment functions.
Screen #4 was a process that resulted in a SWELl that sufficiently represented the broader population of plant equipment and systems needed to meet the objectives of the 50.54(f) letter [Ref. 10]. The following five sample attributes were used:
A variety of types of systems Major new or replacement equipment A variety of types of equipment A variety of environments Equipment enhanced due to vulnerabilities identified during the IPEEE program Spent Fuel Pool Related Items - SWEL2 Screen # 1 and Screen #2 were used to narrow the scope of SSCs to those that have a seismic licensing basis and those that are appropriate for an equipment walkdown process. Screen #3 was a process iv
ATTACHMENT 1 SEISMIC WALKDOWN REPORT intended to result in SWEL2 that sufficiently represents the broader population of spent fuel pool Seismic Category I equipment and systems to meet the objectives of the 50.54(t) letter, and included the following sample selection attributes:
A variety of types of systems Major new or replacement equipment A variety of types of equipment A variety of environments Screen #4 identified items of the spent fuel pool that could potentially cause a rapid drain-down of the pool, even if such items are not Seismic Category 1. Any items identified as having the potential for rapidly draining the spent fuel pool were to be added to SWEL2.
For NMP2, the SWEL is comprised of:
SWELl resulted in 99 items for walkdown.
SWEL2 resulted in 8 items for walkdown.
There are no SSCs associated with rapid drain down to be included on SWEL2.
Seismic Walkdowns and Area Walk-Bys Section 5 of this report documents the equipment Seismic Walkdowns and the Area Walk-Bys. The online seismic walkdowns for NMP2 were performed during the week of July 16, 2012. The walkdown team consisted of two Seismic Walkdown Engineers (SWE), an Operator with an active SRO license, Design Engineering and Operations/Maintenance personnel as needed.
The seismic walkdowns focused on the seismic adequacy of the items on the SWEL. The walkdowns focused on the following:
" Adverse anchorage conditions
" Adverse seismic spatial interactions
" Other adverse seismic conditions (e.g., degradation)
Area Walk-Bys were conducted in each area of the plant that contained an item on the SWEL. The Area Walk-By was performed to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item. There were 41 Area Walk-bys for NMP2. The key examination factors that were considered in the Area Walk-Bys included the following:
Anchorage conditions (if visible without opening equipment) 0 Significantly degraded equipment in the area Potential seismic interaction v
ATTACHMENT 1 SEISMIC WALKDOWN REPORT
" A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g.,
condition of supports or fill conditions of cable tray)
" Potential adverse interactions that could cause flooding/spray and fire in the area
- Other housekeeping items, including temporary installations The seismic walkdown team walked down 93 of the 99 components on the SWELl and all 8 SWEL2 components. Walkdowns for 6 components were deferred due to accessibility issues such as being located in containment. Anchorage verification for NMP2 was required for minimum of 26 components to meet the 50% verification requirements of EPRI Technical Report 1025286 [Ref. 1]. The components selected for verification numbered 31 exceeding this minimum requirement. A total of 30 anchorage configurations were confirmed to be installed in accordance with the station documentation. The deferred NMP2 items will be walked down during a unit outage or another time when the equipment is accessible, as appropriate.
As outlined in Attachment 5, Table E-2, 17 electrical cabinets require follow-up internal inspection for other adverse seismic conditions. The industry was made aware of the NRC staff position on opening electrical cabinets after the online seismic walkdowns were completed. Follow-up inspections of the electrical cabinets will be completed, as required, during a unit outage or another time when the equipment is accessible.
During the walkdowns of NMP2, there were no adverse seismic conditions identified that challenged the licensing basis for the plant. 13 Condition Reports (CRs) were issued to address conditions such open lighting S-hooks, cracks in grout pads, and seismic housekeeping issues. These issues were dispositioned in the Seismic Walkdown Checklists (SWC) and Area Walk-by Checklists (AWC) that are included in this report. Further, as described below in the discussion of Seismic Licensing Basis Evaluations, these non-adverse seismic conditions were entered into the station's Corrective Action Program to be addressed. Seismic housekeeping issues were found to be the most common.
SWCs and AWCs were completed for all components that were walked down. SWCs for deferred items and their associated AWCs will be completed at the time of the follow up walkdowns and a revision to the submittal report will be issued after the NMP2 outage. Any SWCs or AWCs that need to be revised as a result of the deferred inspections will be updated and re-submitted in the supplemental submittal report.
Seismic Licensing Basis Evaluations EPRI Technical Report 1025286, Section 5: Seismic Licensing Basis Evaluation provides a detailed process to perform and document seismic licensing basis evaluations of SSCs identified when potentially adverse seismic conditions are identified during the equipment Seismic Walkdowns or Area Walk-Bys.
The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets a station's seismic licensing basis without entering the condition into a station's Corrective Action Program (CAP). Further, the process directs that if a condition cannot be readily shown to meet the seismic licensing basis, then the identified condition should be entered into the vi
ATTACHMENT 1 SEISMIC WALKDOWN REPORT station's CAP where it will be determined that the condition does or does not meet the seismic licensing basis.
Constellation Energy Nuclear Group/NMP2 staff did not utilize the process provided in EPRI Technical Report 1025286 to perform and document seismic licensing bases evaluations of SSCs with a potentially adverse seismic condition, as no adverse conditions were discovered. Instead, all questionable conditions identified by the SWEs during the equipment Seismic Walkdowns or Area Walk-Bys were entered into the station Corrective Action Program (CAP) to be further evaluated and addressed as required. Tables 5-1 and 5-2 at the end of Section 5 of this report provide a summary of the conditions identified during the Seismic Walkdowns and Area Walk-Bys.
IPEEE Vulnerabilities The IPEEE submittal for NMP2 [Ref. 9] identified the seismic vulnerabilities included in Section 7 of this report.
Peer Reviews A peer review team consisting of two individuals was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of EPRI Technical Report 1025286 [Ref. 1]. The Peer Review process included the following activities:
Review of the selection of SSCs included on the SWEL Review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-Bys Review of Licensing basis evaluations, as applicable Review of the decisions for entering the potentially adverse conditions into the CAP process Review of the submittal report Provided a summary report of the peer review process in the submittal report Section 8 of this report contains the Peer Review summary report. The Peer Review determined that the objectives and requirements of the 50.54(f) letter are met. Further, the efforts completed and documented within this report are in accordance with EPRI Technical Report 1025286 Summary In summary, seismic walkdowns have been completed at NMP2 in accordance with the NRC-endorsed walkdown methodology. All potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the corrective action program to be addressed. Deferred walkdown items and expected completions dates are outlined in Attachment 5.
vii
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 1
Introduction
1.1 Background
In response to Near-Term Task Force (NTTF) Recommendation 2.3, the Nuclear Regulatory Commission (NRC) issued a IOCFR50.54(f) letter on March 12, 2012 [Ref. 10] requesting that all licensees perform seismic walkdowns to identify and address degraded, non-conforming, or unanalyzed conditions with respect to their current seismic licensing basis. The Nuclear Energy Institute (NEI),
through the Electric Power Research Institute (EPRI), prepared industry guidance to assist licensees in responding to this NRC request. The industry guidance document, EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 [Ref. 1], was endorsed by the NRC on May 31, 2012. Constellation Energy and Nine Mile Point Nuclear Station Unit 2 (NMP2) have committed to using this NRC-endorsed guidance as the basis for these walkdowns and this report.
1.2 Plant Overview The Nine Mile Point Nuclear Station is comprised of two operating boiling water reactor (BWR) generating units. The plant is situated on the southeast shore of Lake Ontario, in Oswego County, New York and is approximately 6.3 Miles northeast of the city of Oswego, NY. Nine Mile Point Nuclear Station (NMPS), Unit 2 has a Mark II containment with a plant-rated core thermal power level of 3,988 MWt (OPERATING LICENSE NO. NPF-69) and has been in commercial operation since October 1986 (Nine Mile Point Nuclear Station Updated Safety Analysis Report (USAR), [Ref. 2]).
1.3 Approach In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:
Seismic Licensing Basis Personnel Qualifications
" Selection of SSCs Seismic Walkdowns and Area Walk-Bys Licensing Basis Evaluations IPEEE Vulnerabilities Resolution Report Peer Review 1-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 2
Seismic Licensing Basis 2.1 Overview This section of the report summarizes the seismic licensing basis for NMP2. The safe shutdown earthquake (SSE) and a summary of the codes, standards, and methods used in the design of Seismic Category I SSCs are presented.
2.2 Seismic Design The Seismic Licensing basis is defined in Sections 3.7A and 3.7B of the NMP2 Updated Safety Analysis Report (USAR) [Ref. 2]. Section 3.7A is applicable to the seismic design applied to structures, systems, and components (SSCs) within the Architect / Engineer (Stone & Webster Engineering Corporation) scope of supply. Section 3.7B is applicable to the seismic design of SSCs within the Nuclear Steam Supply System (NSSS) (General Electric) scope of supply.
Design Response Spectra The design response spectra are developed in accordance with Reference 3 published procedures and RG 1.60 [Ref. 4]. The critical parameter defined is the maximum expected ground acceleration. Associated with the maximum ground acceleration, the maximum ground displacement is determined by linear scaling from Figures 1 and 2 of Regulatory Guide (RG) 1.60 in proportion to the maximum expected ground acceleration. Detailed smooth spectra for any given value of damping are obtained by locating critical points and joining them by straight lines in a tripartite logarithmic plot. These critical points are obtained from given amplification factors and cutoff frequencies. The design peak ground acceleration (PGA) is 0.15 g for the SSE and 0.075 g for the operating basis earthquake (OBE). These design response spectra are not related to any site-dependent ground motion time history.
The ratios of vertical design response spectral values to the horizontal design response spectral values comply with the position of NRC RG 1.60 [Ref. 4]. The ratio varies for different frequencies as required by RG 1.60.
Design Response Spectrum Derivation An artificial earthquake is generated to produce a response spectrum which envelope the design response spectra discussed above. This artificial earthquake is generated and checked by comparing spectral values at 80 periods between 0.02 and 5.0 sec and is generated for damping values of 1, 2, 5, 7 and 10 percent.
Based on this comparison, the artificial earthquake time history is deemed to be acceptable and is used for structural analysis and design purposes following RG 1.60 [Ref. 4].
Critical Damping Values Seismic analysis is performed using total system damping characterized by modal damping. The modal damping value is calculated as a ratio of the sum of the energy dissipated in each component element 2-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT (based upon the assigned damping ratio of each element) to the total available modal energy for each cycle in a hysteretic system.
In determining the modal damping ratios, component damping values consistent with expected stress intensities seen on a component are used. For example, component damping for welded structural steel is assigned a value of 2 percent of critical damping for OBE and 4 percent for SSE.
Structures - The damping ratios are defined in RG 1.61 [Ref. 5] for various structure types.
Equipment - The percentages of critical damping values assigned to Category 1 systems and components are defined in RG 1.61 [Ref. 5].
Piping - The percentages of critical damping values used for the analysis of all piping are consistent with RG 1.61 [Ref. 5]. The alternative damping values used for NMP2 are those described in Figure 1 of RG 1.61. Potentially increased piping displacements resulting from the use of these alternative damping values are verified when piping supports are moved, modified, or eliminated. This verification ensures that there will be no adverse interaction with adjacent structures, components, or equipment.
Support Media for Category 1 Structures Major Category 1 structures are founded on sound rock. The top of bedrock is encountered at elevations ranging from 240 to 246 ft. The foundation/support media information for Category I structures were appropriately considered. The static and dynamic properties of Category.1 structural backfill was also appropriately considered.
Three Components of Earthquake Motion and Modal Responses The spatial components from seismic response analysis are combined in accordance with RG 1.92 [Ref.
6]. All Category I structures are analyzed with three orthogonal component motions (two horizontal and one vertical) from the prescribed earthquake. When the response spectrum (RS) analysis is performed, the representative maximum value of a particular response (e.g., stress, strain, moment, shear, or displacement) of a given element of an SSC is obtained by taking the square root of the sum of the squares (SRSS) of corresponding representative maximum values from each of the three orthogonal RS results calculated independently.
In cases where time history dynamic analysis is used, all three statistically independent (correlation coefficient <0.2) orthogonal ground accelerations of the prescribed earthquake are input simultaneously.
The particular response in a direction of interest is obtained by algebraic summation of the response in that direction at each time interval due to each of the three ground accelerations.
In the RS modal analyses, the modal responses are combined using the grouping method or double sum method as described in RG 1.92 [Ref. 6].
Effects of Parameter Variations on Floor Response Spectra Effects on calculated values of fundamental structural periods due to variations in damping and structural material properties are taken into account. Category I equipment and piping systems designed using floor 2-2
ATTACHMENT 1 SEISMIC WALKDOWN REPORT RS and having natural periods within +/- 15 percent of a peak resonant period are assigned that peak response value, Outside this range, peak broadening is used.
Design Criteria for SC-I Equipment Category I SSCs are those that are important to safe shutdown conditions and designed to remain functional in the event of a safe shutdown earthquake (SSE). They are those necessary to ensure:
The integrity of the reactor coolant pressure boundary (RCPB).
The capability to shut down the reactor and maintain it in a safe condition.
The capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures.
In addition, Seismic Category 1 structures, systems, and components are designed to remain functional and within applicable stress and deformation limits (elastic range of materials) when subjected to the effects of the vibratory motion of the OBE in combination with normal operating loads.
Mechanical Components Mechanical components are designed as described in USAR Section 3.9 [Ref. 2]. Elastic analysis techniques are utilized in the qualification of Category I American Society of Mechanical Engineer (ASME) Code and non-Code equipment. Stress limits utilized for the faulted plant condition are outlined in Section 3.9 A.3. 1. Design conditions and stress limits defined are applicable for an elastic system (and equipment) analysis. Stress limits for inelastic system (and/or component) analyses are in accordance with ASME Section III, Appendix F.
Category 1 ASME Safety Class 1, 2, and 3 components are designed, analyzed, and certified in accordance with the appropriate ASME III Code edition and addenda as defined in their design specifications. However, if Code nameplates are removed from installed equipment, traceability is provided in accordance with ASME III 1980 Edition, Winter 1981 Addendum, Subsection NCA, Subarticle 8240(b).
Piping Category I ASME Safety Class 1, 2, and 3 piping and pipe supports are analyzed and designed in accordance with requirements of ASME Section III, Subsections NB, NC, ND, and NF, respectively.
These analyses also comply with Appendix F of ASME Section 1I1. The 1974 Edition is primarily used with some limited exceptions.
Electrical Components Electrical components are designed as described in USAR Sections 3.1OA and 3.1OB [Ref. 2]. Per Section 3.1O.A of the USAR SC-I electrical equipment are qualified for the balance of plant scope of supply per the Institute of Electrical and Electronics Engineers (IEEE) Standard 344-75 [Ref. 7]. Per Section 3.10.B of the USAR SC-I electrical equipment are qualified for the NSSS scope of supply per the 2-3
ATTACHMENT 1 SEISMIC WALKDOWN REPORT IEEE 344-71 [Ref. 13] and IEEE Standard 344-75 [Ref. 7]. The IEEE 344-75 standard is comprehensive and similar to the current requirements for nuclear safety related components.
The methods by which the supplier can qualify equipment for compliance with seismic requirements are as follows:
I.
Testing:
- 2.
Type-testing (prototype):
- 3.
Analysis:
- 4.
Combination of I or 2 and 3:
For flexible equipment too complex to be represented properly by an analytical model. Seismic tests are performed by subjecting the equipment to vibratory motion which conservatively simulates the motion at the equipment mounting during an OBE, followed by the vibratory motion associated with a safe shutdown earthquake (SSE).
Same as testing described above, except a prototype is used as a representative for its equipment type.
Equipment may be qualified by analysis if the equipment is not too complex and can be represented in a mathematical model performed as a static analysis and/or dynamic analysis.
Some electrical equipment and instrumentation are qualified by a combination of test and analysis. This qualification can be achieved through various methods such as extrapolation from similar equipment and by comparison of similar seismic conditions previously qualified.
These methods, including the factors for selection of an analytical or test option, test objectives, and acceptability criteria, are described in Section 3.7A.3.1.1, of the USAR [Ref. 2]. Qualification and documentation procedures used for Category 1 equipment and/or systems meet the provisions of IEEE-344-1975 [Ref. 7] as supplemented by the requirements Of RG 1.100 [Ref. 14].
2-4
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Applicable Codes Table 2-1 includes a summary of the Design Codes used in the NMP I design.
Table 2-1 NMP2 Summary of Design Codes SSC / Activity Design Code Reinforced concrete primary American Concrete Institute, Building Code Requirements for Reinforced contaimnent Concrete ACI 318-71. Except for regions around penetrations that are designed to meet the requirements of ASME Section 111, Division 2, the primary containment steel liner is designed following the requirements of ASME Section III, Division 1.
Concrete Structures ACI-307-1979 American Concrete Institute, Specification for the Design and Construction of Reinforced Concrete Chimneys.
ACI-318-1971, American Concrete Institute, Building Code Requirements for Reinforced Concrete).
Steel Structures AISC 1969, 1978 American Institute of Steel Construction, Specification for the Design, Fabrication, and Erection of Structural Steel for Buildings, including Supplements 1, 2, and 3, (November 1, 1970, December 8, 1971, and June 12, 1974).
AISC 1972, AISC 1976 Code of Standard Practice for Buildings and Bridges, AISC Manual AISI 1968 American Iron and Steel Institute, Specification for the Design of Cold Formed Steel Structural Members, including 1972 Printing with Addendum No. 1.
Quality Control Testing, American National Standards Institute (ANSI) N45.2.5 and IOCFP inspection, and Appendix B.
documentation Welding AWS D1.1-1975 American Welding Society, through 1982 Structural Welding Code with limited exceptions.
NCIG-01, Rev. 2, Visual Weld Acceptance Criteria May 7, 1985 (VWAC) for Structural Welding at Nuclear Power Plants, Prepared by Nuclear Construction Issues Group (NCIG).
Welder Qualification ASME Section IX or AWS DI.1, with limited exceptions.
2-5
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 2-1 NMP2 Summary of Design Codes SSC / Activity Design Code Piping & Mechanical Equipment ASME III - 1971 American Society of Mechanical Engineers Divisions 1, 5, 9, Boiler and Pressure Vessel Code, 1971 Edition through Summer 1973 Addenda, Sections 11, I1l, Divisions 1, 5, and 9, including applicable code cases, with limited exceptions.
ASME III - 1974 American Society of Mechanical Engineers Division 1, Boiler and Pressure Vessel Code, 1974 Edition through 1976 Addenda".
ASME III - 1977 American Society of Mechanical Engineers Subsection NF, Boiler and Pressure Vessel Code, 1977 Edition, Subsection NF with limited exceptions.
Valves ASME Section III, Class 1, 2, and 3 Electrical Equipment IEEE 344-1975, [Ref. 7].
New and Replacement Components for Regulatory Guide 1.97 and 10 CFR 50.49 components Components (that require seismic qualification) are performed to the requirements of IEEE 344-1975, [Ref. 7].
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT 3
Personnel Qualifications 3.1 Overview This section of the report identifies the personnel that participated in the NTTF 2.3 Seismic Walkdown efforts. A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI Seismic Walkdown Guidance [Ref. i]. Resumes provided in Appendix A provide detail on each person's qualifications for his or her role.
3.2 Walkdown Personnel Table 3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.
Table 3-1 Personnel Included in NTTF 2.3
.2
- - 00 0
U z 0
'0 Personnel
- a.
r0 c
Mr. Andrew Scheg X
X Mr. James Moody X
X Mr. John McAndrew X
Mr. George Gary Thomas X
X Ms. Neda Stoeva X
X Mr. Walter Djordjevic XVNote 1)
Mr. Antonio Perez X
Notes:
- 1. Peer Review Team Leader.
The following include a short synopsis of each individual's qualifications.
George Gary Thomas, P.E. Mr. Thomas is a Senior Consulting Engineer in the S&A Cleveland office with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads. He has over 29 years experience in extreme load evaluations and calculations for nuclear systems, structures and components. He has managed and led seismic walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments.
Mr. Thomas has performed the seismic analyses of braced steel frames, concrete foundations, masonry walls, large storage tanks, and electrical and mechanical equipment anchorages. In addition, Mr. Thomas has executed the walkdown and analysis of tank structures and their associated leak path piping to assess loss of inventory in the event of seismic events using manual and finite element methods. Mr. Thomas was one of the original Seismic Matter experts that developed the SQUG GIP and Walkdown Training Course. Mr.
Thomas has an MSCE and BSCE with emphasis in Structural Engineering from the Purdue University.
3-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT He is a licensed P.E. (civil) in Texas and has completed the SQUG walkdown training course, IPEEE add-on course, and NTTF Recommendation 2.3 Seismic Walkdown Engineer (SWE) training course.
Neda Stoeva:
Ms. Stoeva is an engineer in the S&A Cleveland office with experience in the nuclear power industry.
Ms. Stoeva has conducted seismic analyses of electrical and mechanical equipment anchorages and civil structures including containment. Ms. Stoeva has an MSCE and BSCE in Structural Engineering from the University of Buffalo and has passed the E.1.T. in New York. Ms. Stoeva has completed the NTTF Recommendation 2.3 SWE training course.
Walter Djordievic: Mr. Djordjevic is also designated the peer review Team Leader. Mr. Djordjevic is an advanced degree structural engineer and has over thirty years of nuclear seismic experience.
Mr.
Djordjevic has completed the SQUG walkdown training course, IPEEE add-on course, and NTTF Recommendation 2.3: Seismic Fragility and Seismic SWE training course.
Antonio Perez: Mr. Perez is a mechanical engineer with 15 years of experience and a trainee in a 9 month Senior Reactor Operator Certificate training program.
Andrew Scheg: Mr. Scheg is a former systems engineer with over 6 years of nuclear experience. He is currently working in the station PRA group. Mr. Scheg is fully qualified as a PRA engineer and has completed the 6-week EPRI Education of Risk Professionals Course. His past works in the PRA field include Risk Informed In-Service Inspection, significance determination evaluations, Maintenance Rule Expert Panel Member, and mitigating System Performance Index (MSPI) evaluations. He is involved with the development and coordination for execution of NRC NTTF actions 2.1 (Seismic PRA) and 2.3 (Seismic Equipment Walkdowns)..
James Moody: Mr. Moody has over twenty years of experience in the power industry, specializing in risk management, decision-making, probabilistic risk assessment, and reliability engineering. He has been a leader in both the development and application of risk assessment at numerous facilities. He is developing PRA models at AREVA for the European PWR to be licensed in the US, continues to support EPRI with risk-informed ISI projects and Constellation Energy with fire PRA and internal events. In addition, he regularly participates in and assists with PRA updates to meet the ASME Standard and Regulatory Guide 1.200.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT 3.3 Additional Personnel Mr. John McAndrew is an NRC licensed Senior Reactor Operator at NMP2 and provided an independent review of the Seismic Walkdown Equipment Lists (SWELs) as well as assisted during seismic walkdown activities. Mr. McAndrew provided several recommendations for the SWELs including inclusion of the Standby Liquid Control System (SLCS) components given the importance of this system for reactivity control functions. His contributions associated with accessibility of equipment were instrumental in identifying components where access issues warranted alternative selection considerations.
Mr. Patrick Nellis is a qualified Nuclear Auxiliary Operator at NMP2. This Operator provided assistance and accompanied Seismic Walkdown Engineers during walkdown activities. This effort provided real time insight and knowledge of plant configuration and operational considerations potentially impacting walkdown activities.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT 4
Selection of SSCs 4.1 Overview This section of the report describes the process used to select SSCs that were included in the Seismic Walkdown Equipment List (SWEL).
4.2 SWEL Development Development of the Seismic Walkdown Equipment List I (SWELl) for NMP2 is based on EPRI 1025286 "Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic" [Ref. 1] and Seismic Equipment List (SEL) developed for the Seismic Probabilistic Risk Assessment (SPRA) developed in accordance with NTTF Task 2.1. The SEL contains equipment information fields such as PRA, IPEEE, Seismic Category 1, plant location fields, equipment class etc.
The results of the SWEL development are provided in the following tables:
" Table 4-1: Unit 2 SWELl selection count by Class
" Table 4-2: Safety Class Representation among selected SWELl Components
" Table B-1, NMP Unit 2 SWELl Base List (Contained in Attachment 2)
" Table B-2, NMP Unit 2 SWEL2 Base List (Contained in Attachment 2)
" Table B-3: Unit 2 SWELl List, (Contained in Attachment 2)
" Table B-4: Unit 2 SWEL2 List, (Contained in Attachment 2) 4.2.1 SWELl - Sample of Required Items for the Five Safety Functions In order to establish an initial list of components for inclusion in the SEL and SWELI, a review of the Unit 2 IPEEE and the Unit 2 current PRA models was conducted. Those components addressed in these documents formed the initial population of components for consideration. By using these as a starting point, there is an assurance that station risk is taken into account in the development of the overall lists.
In addition to these components, the following component/system groups were added to ensure that all of the SWEL sample considerations were satisfied:
All of the Seismic Category I cabinets and racks were added to the SEL. This was done because many of the individual relays addressed in the IPEEE and PRA were in common cabinets and instrument racks. By addressing the overall rack, a more complete walkdown is achieved.
A review of the Unit 2 USAR, [Ref. 2], was also conducted to ensure that all Seismic Category I systems had been considered for inclusion.
" An initial review revealed that there were no "risk significant" Seismic Category I air compressors, chillers, or motor-generator (MG) sets.
o All of the Control Building Ventilation (HVC) and Control Building Chilled Water (HVK) components were added to the SEL to ensure that each of the component types specified in EPRI 1025286 was addressed, where applicable. Although these systems are 4-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT not "risk-significant" per the IPEEE and station PRA, they do contain Seismic Category I compressors and chillers.
o A review of all of the NMP2 MG sets was conducted and it was determined that there are no MG sets that are applicable to the walkdown criteria [Ref. I].
After incorporating these components into the available population, the following screens were applied to identify those components applicable to the SWEL review process:
I. Seismic Category I (SCI)
From the overall scope established for the SEL, a review of the Seismic Category I components was conducted. All Non-Seismic Category I components were removed from SWEL I consideration.
- 2.
Equipment and Systems While developing the SWEL a representative population of different SSC's was ensured by including a representative sample of each of the component types listed in Appendix B, "Classes of Equipment" of EPRI 1025286, [Ref. 1]. The Class 0 designation was used for equipment types not covered by types 1 through 21. In performing this screen, relays, fuses, breakers and instruments were assigned as subcomponents to a rack or cabinet; these racks and cabinets are part of the population used to identify the SWEL. Similarly, other subcomponents such as pump motors, pump coolers, etc. are grouped into the large one.
This filter predefines the following screens to focus the SWEL component list:
Major pieces of equipment in the Nuclear Steam Supply System (NSSS) located inside of the containment building.
Components that are routinely inspected under other established programs that evaluate structural integrity and adequacy.
Seismic Category 1 Structures Containment penetrations
- Piping within Seismic Category I Piping Systems.
This includes manual valves, check valves, expansion joints, strainers, flow elements, filters, rupture discs, and dryers. These elements are considered passive and part of the piping system pressure boundary.
Additionally, these components do not pose significantly more risk to system operation during a seismic event than the piping itself. These components are expected to operate normally and do not result in a significant stress on the pipe during a seismic event.
Distribution items such as cable/conduit raceways and HVAC duct can also be excluded as they are considered as part of the Walk-By scope.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT The following additional screens were applied. Each item includes a description of how the screens were applied to the SEL population to establish those components to be left for SWELl consideration:
Loss of Offsite Power (LOOP) - It is assumed that a seismic event will result in a failure of offsite power; therefore, all components dependent solely on offsite power are screened from SWELl consideration.
" ATWS/Loss of Offsite Power (LOOP) -
safety related breakers and switchgear solely dependent on offsite power were screened. These particular items are associated with reactor recirculation pump trip for Anticipated Transient Without Scram (ATWS).
Fuel Racks - these are passive structures and not considered to be within the scope of the SWELl.
Non-Safety Related (NSR) - certain items such as drywell coolers and sump level switches etc. were screened since they are not safety related and not modeled in the SPRA.
- 3. Supports Five Safety Functions
- a. Reactor Reactivity Control: this function is fail-safe and reliable. The reactor and control rods are part of the NSSS inside the primary containment. The scram input signals and scram solenoids are considered as well as alternate means of adding negative reactivity such as through the Standby Liquid Control System (SLCS). Consideration of the SLCS was at the suggestion of the NRC licensed Senior Reactor Operator.
- b. Reactor Pressure Control: these components (Safety Relief Valves - SRVs) are NSSS components located inside primary containment.
They are also considered reliable and seismically rugged.
Although the safety valve function protects the reactor and is not dependent on signals, the pressure input signals required for SRV response are considered.
- c. Reactor Inventory Control: High Pressure Core Spray System (HPCS) and Recirculate Core Injection Cooling (RCIC) are considered critical.
These pumps and MOVs are included.
Division I AC, DC and service water are considered.
- d. Decay Heat Removal: Residual Heat Removal (RHR) is most important. RHR Train A pump, heat exchangers and MOVs are included. Division I AC, DC, and service water are also considered.
- e.
Containment Function: the containment and containment penetrations are not in the scope and are considered seismically rugged. However, key containment isolation valves were considered as identified in the PRA and IPEEE.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Although the SWEL specifically identifies Division 1 components at NMP2, the intent of these selections was to allow for substitution of the alternate division if required. The design of the units is such that there are at least 2 functionally identical equipment trains. Instances in which inspection of alternate division equipment may be inspected include:
Equipment in one division was protected If one division had a higher dose associated with its inspection, and there was no additional risk associated with inspecting the alternate division component(s).
By substituting in the alternate division's components, sampling criteria established by the initial SWEL screening is preserved and the fidelity of the inspection locations is maintained.
The IPEEE included a review of the five safety functions and the identification of systems and equipment including support systems and equipment. Additionally, the NMP2 PRA addresses all these functions. Since the SEL is based on the PRA and IPEEE, these functions, systems and equipment have been addressed.
As an additional means to ensure that the five safety functions were fully addressed, a comparison of the SWELl scope was compared to the "Systems to Support Safety Functions" outlined in Appendix E, "Systems to Support Safety Functions", of EPRI 1025286, [Ref. 1]. Each system was deemed to be adequately addressed.
As described in the EPRI guidance [Ref. 1], major equipment in the Nuclear Steam Supply
.System (NSSS) scope that is located inside containment can be excluded from the SWEL. Also, Seismic Category I racks and cabinets were added to the SEL to ensure completeness; during the SPRA most of these will likely be screened as not necessary to support the above functions. As a result the SWEL will favor selections from those Racks and Cabinets identified by the IPEEE.
- 4. Sample Considerations
- a. Types of Systems: equipment was selected to cover the 5 functions and associated system, including support systems. This includes front-line systems and support systems including those which support AC, DC, service water, and room cooling functions.
- b. Major New/Replacement: the following summarizes new/replacements since the IPEEE.
Any risk significant modifications are addressed in the station PRA through the design change process. However, an additional review of the modifications conducted since 1995 was conducted and identified the following potentially relevant modifications:
Uninterruptable Power Supplies 2VBA*UPS2C and 2VBA*UPS2D are new (CB El 240). This modification was deemed seismically significant and was added to SWEL 1.
Appendix R Battery Packs (2LAD-PNLNO0-38, 2LAD-PNLN02-13, and 2LAD-PNLN01-42) in divisions 1, 2, and 3 EDG Rooms were relocated and will be addressed by the EDG area walk-by.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Installed seismic restraint on emergency switchgear (2EJS*USI, 2EJS*US3, 2BYS*SWG002A, and 2BYS*SWG002B) overhead lifting devices.
This was also identified as a vulnerability and weakness in the IPEEE analysis.
2EJS*USI was included on the SWELl component list.
Secondary cooling water connection of the HPCS diesel from the diesel fire water pump.
- c.
Equipment Types: The number of components for each equipment type was estimated such that it could be assured that each type was represented and that the number of selections was representative of the total population count for each type. Table 4.1 documents the selection counts and locations.
- d. Environments: Equipment located in diverse areas of the plant [service water pump area, reactor building, primary containment, control building, Emergency Diesel Generator (EDG)]
were selected to ensure that different operating environments are considered.
- e.
IPEEE Enhancements: the following summarizes enhancements and selections:
IPEEE indicates that a storage rack near a RCIC MOV was secured to prevent toppling onto MOV. The valve (21CS*MOV129) is included in the SWEL.
4.2.2 SWEL2 - Spent Fuel Pool Related Items In order to establish the SWEL2, a review of the Spent Fuel Pool Cooling (SFC) system components and flow paths was conducted to identify significant components. A similar screening method was applied for SWEL2 as was with SWELl. According to EPRI 1025286 [Ref. 1], all Seismic Category I equipment must be included for evaluation in SWEL2 as well as any SSC that could cause rapid drain down. The areas to be addressed in SWEL2 are:
Seismic Category I is the first filter per EPRI. For both units, the spent fuel pool cooling systems are safety related Seismic Category 1. The support systems (safety related AC, DC and ventilation) are already considered in SWEL I.
Equipment and Systems is the second EPRI filter similar to SWEL I except there is really only one system (spent fuel pool cooling).
Sample Considerations is the third filter similar to SWELl except the single system is located in one area.
Rapid Drain Down is the fourth filter. A suction line break would only drain the pool to the level of the skimmers which are approximately 6-inches below the normal pool level. A return line break is limited in draining the spent fuel pool as siphon breakers are installed on the return lines to prevent siphoning of water from the spent fuel pool. The only penetrations lower than the skimmer and return line is the fuel transfer gate which is a passive Seismic Category I structure.
In addition to these components, the following component/system groups were added to ensure that all of the SWEL2 sample considerations were satisfied:
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT
- The Service Water MOV (2SWP*MOV2 1) associated with emergency water makeup to the spent fuel pool was added for consideration.
The Service Water MOVs (2SWP*MOV14A & 2SWP*MOVI8A) and Reactor Building Closed Loop Cooling (CCP) system MOVs (2CCP*MOV17A and 2CCP*MOV18A) which provide the normal and safety related backup cooling medium to the spent fuel pool heat exchanger were added for consideration.
The list excludes components that are:
Non-Seismic Category 1 components Components solely dependent upon offsite power Major pieces of equipment in the Nuclear Steam Supply System (NSSS) located inside containment Components that are routinely inspected under other established programs that evaluate structural integrity and adequacy Seismic Category 1 Structures Containment penetrations Piping within Seismic Category I Piping Systems.
This includes manual valves, check valves, expansion joints, strainers, flow elements, filters, rupture discs, and dryers. These elements are considered passive and do not pose significantly more risk to system operation during a seismic event than the piping itself. These components are expected to operate normally and do not result in a significant stress on the pipe during a seismic event NSR -Screened since they are not safety related and not modeled in the SPRA 4.2.3 Rapid Drain-Down The reactor internals pit line at NMP2 comes off the top of the internals pit. The reactor internals storage pit at NMP2 has an eight inch line used during drain down, however, the line uses manual valves
(*V1)for isolation and control. This was included in the SWEL2 Base list, but was determined to not be required for inspection.
The spent fuel pool (SFP) gates are considered to be part of the SFP structure. The SFP at NMP2 have been analyzed as Seismic Category 1 structures and therefore per the guidance of EPRI 1025286, [Ref. 1],
the SFP is assumed to be seismically adequate for the purposes of this program.
4-6
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 4 SWELl By Equipment Class Components suitable Components selected for Classes of Equipment for inspection per inspection for SWELI EPRI 1025286 0
Other 12 2
1 MCCs and wall-mounted contactors 8
3 2
Low voltage switchgear and break panels 132 3
Medium voltage, metal-clad switchgear 3
1 4
Transformers 8
1 5
Horizontal pumps 10 3
6 Vertical pumps 11 3
7 Pneumatic-operated valves 60 11 8
Fans 6
0 10 Air handlers 19 2
11 Chiller 2
1 12 Air Compressors 3
0 13 Motor Generators 0
0 14 Distribution panels and Auto Transfer Switches 55 7
15 Battery Racks 3
1 16 Battery chargers and inverters 10 2
17 Engine Generators 3
1 18 Instrument Racks 31 7
19 Temperature sensors 17 2
20 Instrumentation and Control panels 137 9
21 Tanks and heat exchangers 37 6
Total 614 99 4-7
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 5
Seismic Walkdowns and Area Walk-Bys 5.1 Overview Seismic Walkdowns and Area Walk-Bys were conducted by two-person teams of trained Seismic Walkdown Engineers in accordance with the EPRI Seismic Walkdown Guidance [Ref. 1] during the week of July 16, 2012. The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sections.
5.2 Seismic Walkdowns The components included in the seismic walkdowns are shown on the SWELl in Attachment 2. A Seismic Walkdown Checklist (SWC) from Appendix C of Reference I was completed for each item on the SWEL. SWCs for the deferred items identified are not included in Appendix C. The completed SWC for these items will be added at a later date (deferred items are discussed further below).
Additionally, photos are included with most SWCs to provide a visual record of the walkdowns.
Seismic walkdowns were completed for 93 of the 99 items on the NMP2 SWELl with 6 items being deferred. Table E-1 in Attachment E includes the list deferred walkdown equipment items. Walkdowns were completed on all 8 items on the SWEL2 list. As discussed in Section 5.4 there are 17 equipment items that will require supplemental internal inspection.
5.2.1 Anchorage Configuration Confirmation As required by Reference I (page 4-3), 50% of the items were confinned to have anchorage configurations consistent with plant documentation. The table of contents for Appendix C indicates the anchorage verification status for components as follows:
N/A: components that are line-mounted and/or are not anchored to the civil structure and therefore do not count in the anchorage confirmation total.
It is noted that EPRI guidance document, Technical Report 1025286 [Ref. 1] includes Question 6 on the SWC's which asks, "Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?" and only provides for a Yes, No or Unknown answer choice. The answer for question 6 is therefore given a "Yes" when the answers to questions I to 5 on the check list are "N/A".
Y: components that are anchored to the civil structure which were confirmed to be consistent with plant configuration documentation.
N: components for which anchorage drawings were not designated for retrieval because they were not included in the 50% sample or they did not have specific anchorage associated with them because they were in-line equipment items.
The approach taken was to have at least half of each equipment class where anchorage evaluations were applicable (eliminating line-mounted items that are N/A from the population). In general if there were an even number of items in an equipment class, half were included for anchorage configuration confirmation.
When there was an odd amount of items for a given class, the number of anchorage verifications to be conducted was rounded up. There were 53 equipment items in the combined SWELl and SWEL2 lists that were in the population eligible for anchorage verification. Of these, 30 were chosen for anchorage verification.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT 5.2.2 Issues Identification during Seismic Walkdowns None of the anomalies or issues identified by the SWEs during the equipment walkdowns was ultimately judged to be a "Potentially Adverse Seismic Condition" because in all cases it was concluded that the anomaly or issue would not prevent the equipment from performing its safety-related function during or after a seismic event. Table 5-1 presents a summary of all of the issues identified during the Seismic Walkdowns. These issues all occurred in SWEL I equipment items.
5.3 Area Walk-Bys In accordance with Reference 1, Area Walk-by Checklists (AWC) were performed for each room or area within a large room (35 foot radius) which included one or more items on the SWEL. Attachment 4 provides a description of the area walk-by. All completed AWCs are included in Attachment 4 with attached photos. These include overhead areas and other equipment items not on the SWELs in the area.
A total of 41 AWCs were completed for NMP2.
5.3.1 Issue Identification during Area Walk-bys None of the anomalies or issues identified by the SWEs during the area walk-bys was ultimately judged to be a "Potentially Adverse Seismic Condition" because in all cases it was concluded that the anomaly or issue would not prevent the equipment from performing its safety-related function during or after a seismic event. Table 5-2 provides a summary of the issues identified in the Area Walk-bys.
5.4 Supplemental Information On Electrical Cabinet Internal Inspections Based on feedback from the NRC staff, all electrical cabinets included on the Seismic Walkdown Equipment List (SWEL) should be opened during the NTTF 2.3 seismic walkdowns. The purpose for opening these cabinets is to inspect for evidence of:
internal components not being adequately secured whether fasteners securing adjacent cabinets together are in place, and other adverse seismic conditions.
Walkdowns at NMP2 were completed prior to this NRC direction and cabinets with external anchorages were not opened. Internal inspection of these cabinets will be performed at a later date. Attachment 5 of this report includes Table E-2 which identifies components in the specified equipment classes that would be considered as electrical cabinets:
Equipment Classes Considered as Electrical Cabinets
- 1.
Motor Control Centers and Wall-Mounted Contactors
- 2.
Low Voltage Switchgear and Breaker Panels
- 3.
Medium Voltage, Metal-Clad Switchgear
- 14. Distribution Panels and Automatic Transfer Switches
- 16. Battery Chargers and Inverters
- 20. Instrumentation and Control Panels 5-2
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table E-2 indicates internal accessibility of each cabinet.
There are 17 components in Table E-2.
Cabinets that have been identified as requiring these supplemental internal inspections are those with doors or panels with latches or thumbscrews and can be readily opened during normal maintenance activities.
Also provided for each cabinet is a proposed schedule for performing these internal inspections and the associated station tracking record (CR-2012-009635).
There are no components identified on Table E-2 in Attachment E that are also identified on Table E-1 which lists outage (deferred) equipment items. There are three items on Table E-2 that do require completion of anchorage verifications as required by the seismic walkdown guideline (Ref. 1) and they are noted as such.
The SWCs for the components identified in Table E-2 that are to be opened for internal inspections will be revised at the time of the supplemental walkdown to indicate the results of these internal inspections and will be submitted with the updated report when all such deferred walkdowns are complete.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-1: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile Unit 2 Identified During Walkdowns SWEL Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status Item #
SWELl Items 59 2HVR*UC401F Surface corrosion on some of the anchor bolts.
Surface corrosion issue entered into the Work Order CAP in CR-2012-006822.
C91941224 being implemented.
67 2VBA*UPS2C Panels not bolted together, could result in CR-2012-009688 and CR-2012-010259 Work Order pounding/rattling.
initiated to evaluate the panel C92057302 being configuration.
implemented 5-4
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-1: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile Unit 2 Identified During Walkdowns SWEL Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status Item #
85 2CES*PNL405 Light behind panel has open "S" hook.
This issue was entered into the site CAP in Work Order CR-2012-008907 documenting a generic C92035954 being issue associated with S-hooks.
implemented.
This configuration is documented on Site determined Seismic interaction with cart &
Reference Document MASP N2-12111, configuration is in 2CEC*DISPL61 1.
Seismic Eval#650.
accordance with site programs.
Work Order Could not confirm that panels are bolted Panel to be opened for supplemental C92057302 together, which could result in walkdowns under CR-2012-009635 to initiated for pounding/rattling. Per Calculation MS-1971, determine that panels bolted together.
supplemental "Supplemental Calc. for Remote Shutdown inspections. Need Panel-2CES*PNL405 Spec. C06 I G panels to confirm bolting are to be bolted together when this is performed.
65 2BYS*BAT2A Spacers are not provided in the front of the Documents identified that this Corrective Action frames between frame and batteries, unless configuration is per design. Entered into created to enhance tested as is.
CAP as CR-2012-007229 to evaluate the configuration improving the seismic robustness.
and provide the spacers around the battery cells.
5-5
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-1: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile Unit 2 Identified During Walkdowns SWEL Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status Item #
99 2HVK*CHLIA Chain hanging off upper elevation can impact Potential interaction issue entered in CAP Work Order panel (w/controls).
CR-2012-009019 C92037854 being implemented.
78 2CEC*PNL622 Metal egg crate diffusers in the Control Room This issue was captured in the CAP in CR-Work Order are not clipped/restrained.
2012-007408.
C91965917 being implemented.
Also, minor oxidation on back right corner Oxidation does not require further action.
weld, not a seismic concern.
81 2CEC*PNL894 2SVV*IPNL 140 is not tied to 2 CEC*PNL894 This issue was entered into o the station Evaluation and insufficient space is provided for CAP in CR-2012-00723 1.
concluded that the interaction, current configuration is per design and is acceptable because the panel does not contain relays or switches.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-1: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile Unit 2 Identified During Walkdowns SWEL Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status Item #
79 2CEC*PNL828 Temporary test equipment on cart can impact Test cart removed. Temporary equipment Evaluation panel.
is allowed per the work processes with performed and appropriate restrictions however, identified that restrictions were not observed. Issue conditions for addressed in CR-20 12-008949.
temporary storage for work in accordance with AP-913 and the Maintenance Rule are acceptable.
82 2CEC*PNL896 Lighting has open "S" hooks in the chains This issue was entered into the site CAP in Work Order holding the light fixtures in place above the CR-2012-008907 documenting a generic C92035954 being panel.
issue associated with S-hooks.
implemented.
7 2ENS*SWG1OI Need documents for embedded plates. Not Request made to licensee to supply design Embedded plates accessible during the walkdowns, internal documentation of appropriate verified per DWG anchorage inaccessible and could not be configuration.
EE-038DNA_1.0 verified.
with changes per C42842.
5-7
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-1: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile Unit 2 Identified During Walkdowns SWEL Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status Item #
66 2VBA*UPS2A Procedure binders mounted on side of panel This issue was entered into the CAP in Evaluation and may interfere with function of sensitive CR-2012-08947.
concluded that the equipment. The concern with the binders is procedure holders input of additional high-frequency vibration to have no potential the panel not considered in the IPEEE-344-for damaging 1975 testing.
seismic interaction and are acceptable.
Light "S" hooks open on right most 2 lights Work Order above panel 2EHS*MCC103C.
This issue was entered into the site CAP in C92035954 being CR-2012-008907 documenting a generic implemented.
issue associated with S-hooks.
6 2EJS*US 1 Attached hoist above 2EJS*USI is free to Issue addressed in CR-2012-00741 1.
Work Order move laterally and could interact with function C91965923 being of panel.
implemented.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-1: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Equipment Items at Nine Mile Unit 2 Identified During Walkdowns SWEL Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status Item #
2 2SWP*STR4A Surface rust should be cleaned and re-Further bolt degradation to be arrested by Six Work Orders evaluated by owner for bolts seismic integrity, issuance of CR-2012-006770.
were generated (one for each strainer based on Area Walk By results):
C91941158, C91962537, C91962538, C91962540, C91962541 and C91962542 all being implemented.
5-9
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-2: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Area Walk-bys at Nine Mile Unit 2 Identified During Walkdowns.
Area #
Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status or Area Description 2
CB-EL. 261'-
Lights "S" hooks behind Panel 2CES*PNL405.
This issue was entered into tile site CAP in Work Order Remote CR-2012-008907 documenting a generic C92035954 being Shutdown Room issue associated with S-hooks.
implemented.
Also an interaction with the display monitor Display monitor removed.
The display monitor and cabinet set up next to a panel was noted.
has been removed.
4 Area 04 - CSA, A potential interaction with the Switchgear Jack issue addressed in Training Review Jack removed from 261'-0" - Div I Jack (a long hooked metal rod); jack was Request TRR-2012-483.
basket and safe Switchgear hooked to a basket behind Panel 2EJS*USI and distance from Room could fall during an earthquake.
equipment.
Lights have open "S" hooks above Panel 2EHS*MCCI03C.
This issue was entered into the site CAP in Work Order CR-2012-008907 documenting a generic C92035954 being issue associated with S-hooks..
implemented.
5 CCL - 261'-
A ladder was not laterally restrained and could Ladder moved and restrained.
Ladder moved and Control building hit SWP piping and valves during a strong restrained.
HVAV Room earthquake.
5-10
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-2: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Area Walk-bys at Nine Mile Unit 2 Identified During Walkdowns.
Area #
Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status or Area Description 8
CCR-EL. 281 -
Lighting has open S-hooks near panels 828 and This issue was entered into the site CAP in Work Order Relay Room 896.
CR-2012-008907 documenting a generic C92035954 being issue associated with S-hooks.
implemented.
Cart has been removed. Temporary Also, temporary carts should be addressed for equipment is allowed per the work Evaluation potential interactions, processes with appropriate restrictions performed and including 'Work In Progress' identification identified that to an open WO and proper restraints conditions for (chocks, etc). Spacing addressed in CR-temporary storage 2012-008949 to prevent seismic for work in interactions, accordance with AP-913 and Maintenance Rule are acceptable.
5-11
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-2: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Area Walk-bys at Nine Mile Unit 2 Identified During Walkdowns.
Area #
Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status or Area Description 9
CCR - 306' -
Egg-crate diffusers were not clipped in and This issue was captured in the CAP in CR-Work Order Control could adversely affect the Operators during an 2012-007408.
C91965917 being Building (Adj.
implemented.
to 2CEC*PNL622)
Temporary equipment (Cadillac - core test Cart removed. Temporary equipment is Evaluation cabinet) should be stored away from panels.
allowed per the work processes with performed and appropriate restrictions however, identified that restrictions were not observed. Addressed conditions for in CR-20120008949.
temporary storage for work in accordance with AP-913 and Maintenance Rule This issue was entered into the CAP in are acceptable.
Procedure folders are mounted on panels.
CR-2012-08947.
Evaluation concluded that the procedure holders have no potential for damaging seismic interaction and are acceptable.
5-12
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-2: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Area Walk-bys at Nine Mile Unit 2 Identified During Walkdowns.
Area #
Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status or Area Description 10 DG - EL. 261' -
Lights in area need to have hooks closed.
This issue was entered into the site CAP in Work Order Division I DG CR-2012-008907 documenting a generic C92035954 being Control Room issue associated with S-hooks.
implemented.
13 SW - EL - 224' -
There was surface rust seen on anchor bolts for Further bolt degradation to be arrested by Work Order Div. I Service Service Water Pump 2SWP-P IC.
issuance of CR-2012-006807 issued.
C91962535 being Building Pump implemented.
Bay A 14 SW - EL - 261' -
There was surface rust seen on some anchor Further bolt degradation arrested by Work Order s Div. I Service bolts.
issuance of CR-2012-006807 and CR-C91962535 and Building Pump 2012-006770.
C91941169 being Bay A implemented.
15 SW - EL - 261'-
The strainer anchors had surface rust issues Further bolt degradation arrested with the Six Work Orders Div. 2 Service like Bay A.
issuance of CR-2012-006807 and CR-were generated (one Building Pump 2012-006770.
for each strainer Bay B based on Area Walk Vacuum by Service Water train observed.
Vacuum was moved later in the day.
By results):
C91941158, C91962537, C91962538, C91962540, C91962541, and C91962542 all being implemented.
5-13
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 5-2: Table of Potentially Degraded, Nonconforming or Unanalyzed Conditions for Area Walk-bys at Nine Mile Unit 2 Identified During Walkdowns.
Area #
Component ID Potentially Adverse Seismic Condition Action Taken to Address the Condition Current Status or Area Description 20 SC - EL. 175'-
There was some surface rust on bolts of fans in Further bolt degradation arrested with Work Order RCIC Room room.
issuance of CR-20 12-006820.
C91941216 being implemented.
27 SC - EL. 215' -
There was an unanchored Monitor cart with Cart removed. Temporary equipment is Evaluation S-W Quadrant monitor and equipment placed adjacent to allowed per the work processes with performed and some safety related equipment.
appropriate restrictions however, identified that restrictions were not observed. Addressed conditions for in CR-20120008949.
temporary storage for work in accordance with AP-913 and Maintenance Rule are acceptable 41 SC - EL. 184' -
Surface rust identified on 2HVR*UC412B.
Further bolt degradation arrested with Work Order RCIC Room (by.
issuance of CR-2012-006820 issued.
C91941216 being Valves implemented.
21CS* 115, 120
& 150) 5-14
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 6
Licensing Basis Evaluations As noted in Section 5, the issues identified during the Seismic Walkdowns and Area Walk-Bys were not determined to be "Potentially Adverse Seismic Conditions". In all cases the anomaly or issue would not prevent the equipment from performing its safety-related function. Therefore, no formal Licensing Basis Evaluations are necessary and none were performed.
6-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 7
IPEEE Vulnerabilities Resolution Report A number of benefits were derived from the IPEEE. The improvements or initiatives were identified during the IPEEE and resolved summarized in Table 7-1.
Table 7-1 NMP2 IPEEE Seismic Improvement Initiatives I
J SWELl RESOLUTION/
CONFIGURATION SELI WHEN COMPLETED MAINTENANCE It was noted that several safety related electrical cabinets included a hoist assembly located on the top of the panel.
I A plant deviation event report (DER 2-95-0245) was written to document this finding. The DER has been dispositioned which required the installation of a number of rail stops.
Installed seismic restraints on emergency switchgear overhead lifting under WO's 2960572700 and 2950663600. Work was completed 8/15/96 and 10/4/95, respectively.
Configuration has been maintained as described in the resolution section.
Included 2EJS*USI, and 2BYS*SWG002A During the The IPEEE indicates that The rack is currently walkdown, a the rack was better analyzed and deemed material storage secured during the IPEEE adequately installed per rack near 21CS*MOV 29 process. There are no the station material 2
date/time or work storage process.
2ICS*MOV129 was identified as documents specified. The Reference storage permit having the penta toe f rack is installed properly N2-1208 and seismic and impact the per the station material exception evaluation MOV.
storage process.
0365.
7-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 8
Peer Review 8-1 Peer Review Introduction The peer review was performed in accordance with the walkdown guidance document [Ref. 1].
Each element within and the entire process of this Seismic Walkdown was reviewed by the peer Review Team.
This effort included the following activities:
A review of the selection of the SSCs included on the SWEL Observation of seismic walkdown activities on July 19, 2012 by Peer Review Team Leader, Mr. Walter Djordjevic A review of a sample of the checklists completed for the Seismic Walkdowns and Area Walk-Bys A review of the licensing basis evaluations A review of the decisions for entering or not entering the potentially adverse seismic conditions into the Corrective Action Process (CAP) process A review of the submittal report The inclusion of a summary of the peer review process in the submittal report The Peer Review Report including the checklist is included in Attachment 5.
This section of this report documents the independent peer review for the Near Term Task Force (NTTF)
Recommendation 2.3 Seismic Walkdowns performed by Stevenson & Associates (S&A) for NMP2.
The peer reviewers for the NMP2 Plant are Misters Walter Djordjevic and Antonio Perez of S&A.
R6sum~s are provided in Appendix A.
Mr. Djordjevic led the seismic peer review activities and Mr.
Perez led the SWEL selection peer review. All peer review activities were performed by both engineers.
The SWEL development was performed by Mr. Andrew Scheg in consultation with Mr. James Moody.
The peer review of the SWEL development began on July 10, 2012 and was completed on July 12, 2012.
There were a few observations noted on the SWEL Peer Review Checklist but no findings were cited.
The completed SWEL Peer Review Checklist is found in Attachment 5. The discussion for the SWEL development peer review is found in Section 8.2.
The peer review of the seismic walkdown inspection started on July 19, 2012 with a peer check of the actual walkdowns.
Mr. Djordjevic joined the walkdown team for a portion of the day's planned walkdowns to observe the conduct of walkdowns and adherence to the Seismic Walkdown Guidance (SWG), [Ref. I]. In addition, an interview was conducted by Misters Djordjevic and Perez with the SWE inspection team after review of a sample of the Seismic Walkdown Checklists (SWC) and Area Walk-By Checklists (AWC) to ascertain the quality and procedural compliance with the SWG. A discussion of the sample SWC and AWC is provided in Section 8.3.
8-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT The assessment of condition reports against the current licensing basis is provided in Section 8.4. These assessments and their outcomes were also discussed with the SWE inspection team in order to completely understand the issues.
8.2 Peer Review - Selection of SSCs 8.2.1 Purpose The purpose of this section is to describe the process used to perform the peer review of the selected SSCs that were included in the SWEL.
This section documents the Peer Review - Selection of SSCs performed for NMP2.
8.2.2 Peer Review Activity - Selection of SSCs The guidance in Section 3 of EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3.: Seismic, dated June 2012 [Ref. 1]:
"Selection of SSCs" was used as the basis for this review.
This peer review was based on reviews of the following documents:
SWEL Scope Development - Section 4 of this report NMP2 SWELl Base List (Table B.1)
NMP2 SWEL2 Base List (Table B.2)
NMP2 SWELl and SWEL2 (Table B.3 and B.4)
This peer review was based on interviews with the following individual who was directly responsible for development of the SWEL:
Andrew Scheg, Nine Mile Point Nuclear Station-PRA Engineering This peer review utilized the checklist shown in Reference 1, Appendix F: Checklist for Peer Review of SSC Selection.
For SWELl development, the following actions were completed in the peer review process:
Verification that the SSCs selected represented a diverse sample of the equipment required to perform the following five safety functions:
o Reactor Reactivity Control (RRC) o Reactor Coolant Pressure Control (RCPC) o Reactor Coolant Inventory Control (RCIC) o Decay Heat Removal (DHR) o Containment Function (CF)
This peer review determined that the SSCs selected for the seismic walkdowns represent a diverse sample of equipment required to perform the five safety functions.
8-2
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Verification that the SSCs selected include an appropriate representation of items having the following sample selection attributes:
o Various types of systems o
Major new and replacement equipment o
Various types of equipment o
Various environments o
Equipment enhanced based on the findings of the IPEEE o
Risk insight consideration Note: For accessibility reasons, some equipment has been deferred to Outage.
For SWEL2 development, the following actions were completed in the peer review process:
Verification that spent fuel pool related items were considered and appropriately added to SWEL2.
This peer review determined that spent fuel pool related items were given appropriate consideration.
The spent fuel pool cooling system is safety related Seismic Category 1 and SWEL2 was sufficiently populated as appropriate. There were no items identified as related to rapid drain down.
Verification that appropriate justification was documented for spent fuel pool related items that were not added to the SWEL2.
This peer review determined that an appropriate level of justification was documented for those items related to the spent fuel pool that were not added to SWEL2.
8.2.3 Peer Review Findings - Selection of SSCs This peer review found that the process for selecting SSCs that were added to the SWEL was consistent with the process outlined in [Ref. 1]. Section 3: Selection of SSCs.
The peer review checklist is attached to this document with additional observations documented as appropriate.
One of the observations was that no equipment located in the primary containment was represented on the final SWEL. A subsequent decision (to the development of final SWEL) was made based on industry input and benchmarking to include components within the Primary Containments at both Units of Nine Mile Station. Those which were selected, are included in Table E-1, Attachment E and included in WO C92017457 written to track completion of the seismic walkdowns and area walk by's.
This peer review resulted in no additional findings.
8.2.4 Resolution of Peer Review Comments - Selection of SSCs All comments requiring resolution were incorporated prior to completion of this peer review.
8-3
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 8.2.5 Conclusion of Peer Review - Selection of SSCs This peer review concludes that the process for selecting SSCs to be included on the seismic walkdown equipment list appropriately followed the process outlined in [Ref. 1], Section 3: Selection of SSCs. It is further concluded that the SWEL sufficiently represents a broad population of plant Seismic Category I equipment and systems to meet the objectives of the NRC 50.54(f) Letter [Ref. 10].
8.3 Review of sample Checklist & Area Walk-bys 8.3.1 Overview of Walkdowns A site visit was made on July 19, 2012 by Mr. Walter Djordjevic to perform peer review of the seismic walkdown inspection. The SWE trained walkdown engineers were Mr. George G. Thomas and Ms. Neda Stoeva. In addition, after a review of the SWC and AWC samples was completed, an interview was conducted by Misters Djordjevic and Perez with the SWE inspection team on August 16, 2012 in accordance with the SWG requirements to discuss and clarify completion of the SWE, AWC and licensing basis evaluations. It was concluded that the walkdown team performed their assessments and evaluations properly.
8-4
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 8.3.2 Walkdown Review and Review of Sample Checklists Tables 8-1 and 8-2 list the SWC and AWC sampling which represent 27% of the SWC and15% of the AWC.
Table 8-1: Table of SWC Samples from Seismic Walkdown Inspection for NMP2 No.
Equipment Walkdown Item Location Observations (GIP) Class 2CEC*PNL622 20 Relay Panel Control Room, El Seismic housekeeping 306 ft issues correctly identified - corrective action issued 2CEC*PNL894 20 Auxiliary Relay Relay Room, El.
Not connected to Panel 288 ft 2SVV*IPNL140 but found to contain no relays 2CEC*PNL859 20 Auxiliary Relay Relay Room, El.
None noted Panel 288 ft 2CEC*PNL828 20 Auxiliary Relay Relay Room, El.
Seismic interactions Panel 288 ft with temporary cart correctly identified. Cart subsequently removed.
2CEC*PNL896 20 Auxiliary Relay Relay Room, El.
Seismic interactions Panel 288 ft correctly identified:
Overhead light mounted with open s-hooks.
Corrective action issued.
2SCM*PNLI03A 20 Wall mounted West Cable Chase None noted panel Area, El. 288.5 ft 2HVK*V1O0 11 Chiller lA Control Bldg, El.
Conclusion that adjacent 261' chain fall poses no credible hazard is accepted.
2EJS*X2 4
HPCS 4160/600V Control Bldg, El.
None noted Transformer 261' 8-5
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 8-1: Table of SWC Samples from Seismic Walkdown Inspection for NMP2 No.
Equipment Walkdown Item Location Observations (GIP) Class 2VBA*UPS2C 16 UPS Control Bldg, El.
Cabinets not tied Rectifier/Inverter 237' together, however, not a Cabinet concern as cabinet contains no essential relays 2BYS*SWG002A 3
Switchgear Control Bldg, El.
None noted 261' 2EJA*PNLIO1A 14 Wall mounted Control Bldg, El.
None noted panel 261' 2EJS*PNLIOOA 14 Wall mounted Control Bldg, El.
None noted panel 261' 2BYS*BAT2A 15 Station batteries Control Bldg, El.
Batteries missing Div 1 261' spacers. This issue was identified as a potentially adverse seismic condition.
Calculation on file addressed this situation.
Spacers are being installed per corrective action.
2CES*PNL405 20 Remote Shutdown Control Bldg, El.
Seismic interactions:
Panel 261' 1.Adjacent desk 2.Overhead light mounted with open s-hooks.
2CES*IPNL407 20 125V DC Control Diesel Generator, Adjacent light mounted Panel El. 261 ft with open s-hooks impact hazard.
Confirmed no essential relays in cabinet.
2CES*PNL504 20 Service Water SA, El. 261 ft Drawing is referenced as Strainer Control recommended.
Panel 2CES*RAK004 18 RRS Instrument SC, El. 261 ft None noted Rack 8-6
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 8-1: Table of SWC Samples from Seismic Walkdown Inspection for NMP2 No.
Equipment Walkdown Item Location Observations (GIP) Class 2CES*RAK026 18 RV Level SC, El. 261 ft None noted Instrument Rack 2CES*RAK105 18 SFC/CMS SC, El. 261 ft None noted Instrument Rack 2CSH*MOVIOI 8
MOV SC, El. 177 ft None noted 2CSH*PI 6
HPCS Pump SC, El. 178 ft None noted 2EJS*USI 2
600V Emergency Control Bldg, El.
Unsecured hoist poses Switchgear 261' an interaction hazard is correct conclusion.
Closed to work order.
2ENS*SWGIOI 3
4160V Emergency Control Bldg, El.
None noted Switchgear 261' 2HVK-CHL1A 12 Control Building Control Bldg, El.
None noted Chilled Water 261' Compressor 2HVR*UC401F 10 RHR Pump Rm. A ABN, El. 261 ft None noted
- Unit Cooler 2HVR*UC403A 10 HPCS Pump Room SC, El. 276 ft None noted Cooler Table 8-2: Table of AWC Samples from Seismic Walkdown Inspection for NMP2 Area Area Walkdown Location Peer Review Comments Description I
Control Building adjacent Control Bldg, El. 237' None noted to 2VBA-UPS2C 2
Remote Shutdown Panel Control Bldg, El. 261' Open s-hooks and desk next to panel Room pose potential seismic interaction hazards.
Cabinet determined not to contain essential relays; however, corrective actions issued.
3 Standby Battery Room Control Bldg, El. 261' None noted 8-7
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Table 8-2: Table of AWC Samples from Seismic Walkdown Inspection for NMP2 Area Area Walkdown Location Peer Review Comments Description 4
Div I Switchgear Room Control Bldg (CSA), El.
Potential seismic interaction hazards 261' noted were open s-hooks and racking rod stored behind switchgear. Corrective actions issued.
5 Control Bldg HVAC Control Bldg (CCL), El.
None noted Room 261' 6
Div 3 Switchgear Room Control Bldg (CSA), El.
None noted 261' 8.3.3 Evaluation of Findings In all cases the anomaly or issue would not prevent the equipment from performing its safety-related function. Two issues merit some further discussion: 1) the missing spacers in the station battery racks, and 2) selected instances of seismic interaction with control panels in the control room, auxiliary relay room and the remote shutdown panel room:
- 1) The batteries (and supporting rack) are seismically tested in accordance with the IEEE 344 Standard with the spacers in place. They should be maintained in that manner as properly configured with spacers inserted in place and not "justified" to function in a configuration that they were not qualified for.
- 2) The issue with adherence to seismic housekeeping procedures is properly dispositioned by reinforcing training and awareness.
This was an uncovered weakness or gap in the knowledge of the appropriate seismic considerations for temporary carts for on-line maintenance in that personnel were not adhering to the requirements and were unaware of the same.
Condition Report CR-2012-008949 was issued to address these conditions.
In addition a training review request has been issued (TRR-2012-483) for this purpose.
8.4 Review of Licensing Basis Evaluations 8.4.1 Overview of Licensing Basis Evaluations Because none of the issues identified during the Seismic Walkdowns or Area Walk-Bys were determined to be a "Potentially Adverse Seismic Condition" in that the anomalies or issues that were identified would not prevent the equipment from performing its safety-related function, no formal Licensing Basis Evaluations were required.
8-8
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 8.4.2 Insights and Recommendations There is one general concern at Nine Mile Point Nuclear Station, namely the disposition of the seismic housekeeping issues not in conformance with Station Procedures GAP-INV-02, [Ref. 11] and GAP-HSC-01 [Ref. 12]. The immediate concerns with storage of items not in accordance with these procedures were resolved; however, this is potentially indicative of a broader issue in lack of awareness to keep tools and temporary (portable) equipment stored properly in a manner that seismic interaction issues do not arise. As a solution to this awareness concern, a Training Review Request (TRR) to emphasize and improve seismic housekeeping awareness has been requested. The Station issued CR-2012-008949 and TRR-2012-483 to address this concern.
8.5 Review of Final Submittal Report & Sign-off The entire final submittal report has been reviewed by Misters W. Djordjevic and A. Perez and is found to meet the requirements of the EPRI 1025286 - Seismic Walkdown Guidance [Ref. 1].
8-9
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 9
References Note: Reference drawings related to SWEL items are provided in the Seismic Walkdown Checklists and if applicable, in the Area-Walk-by Checklists.
- 1.
EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.
- 2.
US NRC DOCKET 50-410, Updated Safety Analysis Report (USAR) Rev. 19, Nine Mile Point Unit 2, October 2010.
- 3.
Newmark, N. M., Blume, J. A., and Kapur, K. K. Design Response Spectra for Nuclear Power Plants, Journal of Power Division, Proceedings of American Society of Civil Engineers, Vol. 99, No. P02, November 1973.
- 4.
USNRC Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants", Rev. 1, 1973.
- 5.
USNRC Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants",
Rev. 1, March 2007.
- 6.
USNRC Regulatory Guide 1.92, "Combining Modal Responses and Spatial Components in Seismic Response Analysis", Rev. 1, Feb. 1976.
- 7.
IEEE Standard 344-1975, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations", 1975.
- 8.
EPRI Report NP-604 1, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin."
Rev. 1.
- 9.
Nine Mile Point Nuclear Station - Unit 2, "Individual Plant Examination for External Events (IPEEE)", June 1975.
- 10.
NRC (E Leeds and M Johnson) Letter to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3: Seismic."
- 11.
Nine Mile Point Nuclear Station Administrative Procedure, GAP-INV-02, CONTROL OF MATERIAL STORAGE AREAS, REVISION 02700.
- 12.
Nine Mile Point Nuclear Station Administrative Procedure, GAP-HSC-01, HOUSEKEEPING, TOURS, AND INSPECTIONS, Revision 01601.
- 13.
IEEE Standard 344-1971, "Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations", 1971.
- 14.
USNRC Regulatory Guide 1.100, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants", Rev. 1, Aug. 1977.
9-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Project Personnel Resumes and SWE Certificates Resumes and certificates (where applicable) for the following people are found in Appendix A:
G. Thomas, SWE, Licensing Basis Reviewer, IPEEE Reviewer............................
A-2 N. Stoeva, SWE, Licensing Basis Reviewer, IPEEE Reviewer........................
A-9 W. Djordjevic, Peer Review Team Leader.......................................................
A-i 1 A. Perez, Peer R eview er............................................................................
A -14 A. Scheg, Equipm ent Selection......................................................................
A -17 J, M oody, Equipm ent Selection.....................................................................
A -19 A-1
ATTACHMENT 1 SEISMIC WALKDOWN REPORT George G. Thomas, P.E.
EDUCATION:
B.S. Civil Engineering - Purdue University, 1976 M.S. Civil Engineering - Purdue University, 1978 PROFESSIONAL REGISTRATION:
P.E., State of Texas, (ASME N626 and ASME BPVC,Section III Appendix XXIII Certified)
PROFESSIONAL HISTORY:
Stevenson & Associates., Cleveland, Ohio, Consulting Engineer, 1982 - Present Cleveland State University, Cleveland Ohio, Engineering Instructor, 1981 - 1987 Davy McKee Company, Cleveland, Ohio, Lead Engineer, 1980 - 1982 Exxon Production Research Company, Houston, Texas, Research Engineer, 1978 - 1980 McDermott-Hudson Engineering Con., Engineer/Draftsman, 1976 - 1977 PROFESSIONAL EXPERIENCE:
Stevenson and Associates, Cleveland Ohio Mr. Thomas is a Consulting Engineer with Stevenson and Associates, having over 30 years experience on a multiple of projects involving the design, evaluation, and qualification of nuclear safety-related structures, equipment and piping. He has been responsible for the detailed seismic analysis, testing and qualification of a variety of mechanical and electrical equipment and piping (buried and above ground) systems, including anchorage and support structure evaluations. He has performed analysis of safety-related structures subject to extreme loadings of earthquake,. tornado wind, blast, and missile impact. He is an expert in the application of the ACI 349 and ACI 318 Industry Standards for concrete design. In addition he has a significant experience in the application of the AISC-Steel Construction Manual, Uniform and International Building Codes, AISC-N690, ASCE-7, ASCE-4 and the ASME BPVC Section III and B31 series piping codes. He has developed complete design change (modification) packages and FSAR changes for multiple nuclear utilities, including all design, analysis and safety reviews (including IOCFR50.59 screening) documentation supporting the change.
Mr. Thomas is also a SQUG trained Seismic Capacity Engineer.
Significant accomplishments in this position include:
Mr. Thomas served as the Chief Civil Engineer for the design and implementation of USNRC mandated security upgrades at the Wolf Creek Nuclear Station.
In this position he was responsible for design criteria development, design of Steel and Concrete Structures, and all necessary field engineering support during construction.
A-2
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Mr. Thomas was the primary author of a new revision (2002) to the Structural Design Chapter of the Engineering Manual for Los Alamos National Laboratory.
The new manual incorporated the requirements and provisions of the International Building Code IBC-2000.
Mr. Thomas developed a large portion of the Generic Implementation Procedure, GIP, for the Seismic Qualification Utilities Group, SQUG which defines the generic walkdown requirements for USI A-46.
Mr. Thomas was a walkdown participant for both the SQUG Zion and Nine Mile Point I trial plant walkdowns for SQUG. Mr. Thomas prepared and presented the training modules on the GIP for the SQUG training program, and was one of the Subject Matter Experts for the development of the training program and the training program tapes.
Mr. Thomas was the Lead Walkdown Engineer on the Seismic Review Teams for the D.C. Cook Nuclear Station Units I and 2 for USI A-46, Arkansas Nuclear One Units 1 and 2 for a combined US] A-46 and Seismic Margins Assessment for IPEEE, and Waterford 3, Grand Gulf 1 and V.C. Summer I for the Seismic Margins Assessment for IPEEE. In addition, Mr. Thomas was the Lead Walkdown Engineer for Turkey Point Units 3 and 4 as well as St. Lucie Units I and 2 USI A-46 and seismic IPEEE efforts. Mr.
Thomas was the Lead Walkdown Engineer for the seismic IPEEE Probabilistic Risk Assessment for Beaver Valley Unit 2. Mr. Thomas has also performed equipment evaluations at several other facilities using the SQUG-GIP methodology since the completion of USI A-46 issue in order to expand the list of seismically evaluated equipment.
Mr. Thomas has performed numerous evaluations at several nuclear power plants using a walkdown screening approach. This screening approach includes identifying areas of potential seismic vulnerability by inspection and selecting "worst case" systems and supports for more detailed evaluation.
Cleveland State University, Cleveland Ohio Mr. Thomas has served as a part time instructor in the School of Civil Engineering and Engineering Technology at Cleveland State University. On the undergraduate level, he has taught Statics, Dynamics, Material Science, Structural Analysis and Concrete Design.
At the graduate level, he has taught Advanced Steel Design. In all of the teaching assignments he was responsible for developing the course outline, lecture notes, problems and tests.
Davy McKee Company, Cleveland, Ohio Mr. Thomas served as Lead Engineer in the Piping Engineering Group of Davy McKee Company. His work consisted of the design supervision and design of B31.3 piping networks in a number of different petrochemical facilities. His responsibilities comprised the following:
Designing and analyzing piping networks subjected to thermal, weight, wind, earthquake, and pressure loadings using both manual and computerized techniques.
A-3
ATTACHMENT 1 SEISMIC WALKDOWN REPORT While in this role, Mr. Thomas prepared design and analysis packages of pipe supports and pipe support structures. He was also responsible for preparing specifications for expansion joints, and providing an overall support and expansion joint packages. Finally, Mr. Thomas prepared hydrotest procedures and executed the planning of hydrotest circuits.
Exxon Production Research Company, Houston, Texas Mr. Thomas served as a Research Engineer in the Offshore Structures Division of Exxon Production Research Company. His work consisted of development of design and analysis procedures for the Guyed Tower, a type of deepwater offshore production platform. He performed the dynamic, structural, and fatigue analysis necessary for the Guyed Tower design of three proposed structures. He also wrote, revised, and maintained computer programs used in the Guyed Tower analysis and design procedures.
Publication Listing 2007 PVP Conference, San Antonio, TX, PVP2007-26798, "Seismic and Concurrent Load Design Criteria for Buried High Density Polyethylene Pipe in ASME BPVC Section II, Division L, Applications Part I - Piping Design Basis Criteria, Adams, T.M., Spanner, J., Scavuzzo, R. J., Thomas, G.G.
2007 PVP Conference, San Antonio, TX, PVP2007-26799, "Seismic and Concurrent Load Design Criteria for Buried High Density Polyethylene Pipe in ASME BPVC Section I11, Division 1, Applications Part 2 -
Piping Soil Interaction Design Basis Criteria, Adams, T.M., Thomas, G.G., Spanner, J.,
Scavuzzo, R.J.
2007 PVP Conference, San Antonio, TX, PVP2007-26800, "Seismic and Concurrent Load Design Criteria for Buried High Density Polyethylene Pipe in ASME BPVC Section III, Division 1, Applications Part 3 - Sample Problem, Thomas, G.G., Spanner, J., Adams, T.M., Hall, S.
NUREG/CR-5733, August 1999 "Reevaluation or Regulatory Guidance Provided in Regulatory Guides 1.142 and 1.143", Adams, T.M., Stevenson, J.D., Thomas, G.G., Harstead, G.A.
1998 PVP Conference, San Diego, CA., "A Proposed Design Procedure for Buried Safety Related Piping at Nuclear Power Plant Facilities", Adams, T.M., Thomas, G.G., and Knott, R.O.
6th Symposium on Current Issues to Nuclear Power Plant Structures, Equipment and Piping, Raleigh NC, December 4-6, 1996, "Resolution of Flat Bottom Tank Outlier", Thomas, G.G. and Ghiocel, D.M.
6th Symposium on Current Issues to Nuclear Power Plant Structures, Equipment and Piping, Raleigh NC, December 4-6, 1996, "Soil Structures Interactions in Deep Foundation Soils", Ghiocel, D.M., Wilson, P.R., and Thomas, G.G.
A-4
ATTACHMENT 1 SEISMIC WALKDOWN REPORT ASCE Specialty Conference on Probabilistic Mechanics and Structural Reliability, Worcester, MA August 7-9, 1996; "Structural Fragility Analysis Using Finite Element Models", Ghiocel, D.M.; Wilson, P.R.; Thomas G.G.; Stevenson, J.D.
ASCE Specialty Conference on Probabilistic Mechanics and Structural Reliability, Worcester, MA, August 7-9, 1996; "Probabilistic Seismic Analysis Including Soil Structure Interaction", Ghiocel, D.M.;
Wilson, P.R.; Thomas, G.G.
The 13"' International Conference on Structural Mechanics in Reactor Technology, SMIRT-13, Vol. 7, Perto Alegre, July 1995; "Probabilistic Finite Element Analysis for Structural Fragility Evaluation",
Ghiocel, D.M.; Wilson, P.R., Thomas, G.G., and Stevenson, J.D.
Nuclear Engineering and Design, Vol. 123 (1990), Nos. 2&3, October (II) 1990, Pgs 225-231, "Overview of SQUG Generic Implementation Procedure (GIP)", Thomas, G.G. and Starck, R.G.
Second Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment, and Piping with Emphasis on Resolution of Seismic Issues in Low-Seismicity Regions, EPRI NP-6437-D Proceedings, May 1989, "Overview of SQUG Generic Implementation Procedure (GIP)," Thomas, G.G.
and Starck, R.G.
4th Offshore North Sea Technology Conference in Stavanger, Norway, 1980, "A Guyed Tower for North Sea Production," Thomas, G.G. and Finn, L.D.
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Certificate of Completion Gary Thomas Success{ullyj Completed Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns 1
,1I ADA)
Date: 06/26/12 Bruce M. Lo6 - Instructor NTTF 2.3 Seismic Walkdown Course F
ATTACHMENT I SEISMIC WALKDOWN REPORT Neda T. Stoeva EDUCATION:
M.S. Civil Engineering, State University of New York at Buffalo, 2009 B.S. Civil Engineering, State University of New York at Buffalo, 2008 PROFESSIONAL HISTORY:
Stevenson & Associates, Cleveland, Ohio, 2009 - present REGISTRATION/CERTIFICATION:
New York Engineer in Training (EIT)
ASCE Associate Member Certificate of Completion of Introduction to ANSYS Part I and 2 ASME Certificate of Completion of Advanced Finite Element Analysis ASCE Certificate of Completion of Design and Installation of Buried Pipes EXPERIENCE:
Stevenson & Associates, Cleveland, Ohio Ms. Stoeva serves as a staff engineer at the Cleveland Office of Stevenson & Associates. Her primary responsibilities are conducting structural and civil engineering calculations. She has extensive experience modeling complex nuclear structural buildings and components using ANSYS, Solvia, and PDSTRUDL structural analysis programs.
She has also used PIPESTRESS to model and analyze nuclear piping systems. In addition, she has generated and reviewed design calculations consistent with the detailed quality assurance requirements of nuclear power plants. She has experience with the AISC-SCM steel design, ACI-318, ACI-349, and ASME Boiler and Pressure Vessel Code Section NE for containment design.
More specifically Ms. Stoeva has been working under senior staff supervision on projects such as AEP Containment Pressure Reanalysis for Power Up-rate, AEP Auxiliary Building Floor Evaluation for Dry Cask Storage Operation Loadings and Prairie Island's Turbine Building Flooding SDP Seismic Assessment In addition she has been involved in detailed soil design and analysis for a Safety Related Class 3 HDPE installation.
Ms. Stoeva's work also involves the design and analysis of Duke's Buried Class I HDPE Piping, assisting FENOC with the seismic evaluation of the Decontamination and Spent Fuel Pool Buildings for upcoming Dry Cask Storage Operations, in depth nonlinear dynamic analysis and seismic qualification of a PSC designed Tendon Surveillance Frame at ANO.
Ms. Stoeva is also currently the responsible Quality Assurance Software Error Evaluation engineer in the Cleveland office of Stevenson & Associates.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Her previous coursework at SUNY at Buffalo included Advanced Solid Mechanics, Advanced Concrete Structures, Dynamics and Earthquake Engineering I & I1, Advanced Steel Structures, Aseismic Base Isolation, Finite Element Methods, Construction Estimating, Pavement Materials and Design, and Wood Design.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Walter Djordjevic EDUCATION:
B.S. - Civil Engineering, University of Wisconsin at Madison, 1974 M.S. - Structural Engineering, Massachusetts Institute of Technology, 1976 PROFESSIONAL REGISTRATION:
State of California, State of Wisconsin, Commonwealth of Massachusetts, State of Michigan, State of Arizona, State of Missouri PROFESSIONAL HISTORY:
Stevenson & Associates, Inc., President 1996 - present; Vice President and General Manager of the Boston area office, 1983 - 1995 URS/John A.
Blume
& Associates, Engineers,
- Boston, Massachusetts, General
- Manager, 1980 - 1983; San Francisco, California, Supervisory Engineer, 1979 - 1980 Impell Corporation, San Francisco, California, Senior Engineer, 1976 - 1979 Stone & Webster Engineering Corporation, Boston, Massachusetts, Engineer, 1974 - 1976 PROFESSIONAL EXPERIENCE:
- Structural Engineering
- Structural Dynamics
- Seismic Engineering
" Construction
" Vibration Engineering
- Expert Witness
" Committee Chairman Mr. Djordjevic founded the Stevenson & Associates Boston area office in 1983 and serves as President and General Manager. Mr. Djordjevic is expert in the field of structural engineering - more specifically, in the areas of structural vulnerabilities to the effects of seismic and other extreme loading phenomena.
As a structural dynamicist, Mr. Djordjevic also heads the Vibration Engineering Consultants corporate subsidiary of Stevenson & Associates for which he has overseen numerous designs of vibration sensitive microelectronics facilities for such clients as IBM, Intel, Motorola and Toshiba. He has personally been involved in such projects as resolving vibration problems due to construction activities for the Central A-12
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Artery Project (Big Dig) in Boston for which he was retained by Massport. Finally, Mr. Djordjevic has been personally retained as an Expert Witness a number of times relating to cases involving construction, structural and mechanical issues.
He has performed over a thousand hours of onsite seismic and other natural phenomena (including tornados, hurricanes, fire, and flooding) inspection walkdowns to assess structural soundness and vulnerabilities. He has inspected microelectronics fabrication facilities, power facilities, and hazardous material government and military reservations. He is one of the most experienced seismic walkdown inspection screening and verification engineers having personally participated in seismic walkdowns at over 50 U.S. nuclear units.
In recent years, he has concentrated on screening inspection walkdowns and assessments for resolution of the USI A-46 and seismic IPEEE issues, on numerous facilities. The following provides a partial list of recent projects:
American Electric Power - D.C. Cook Station Boston Edison Co. - Pilgrim Nuclear Power Station (SPRA)
Commonwealth Edison Company-Braidwood StationPm, Byron StationP"", Dresden StationPM Quad Cities StationPM Consumers Power Co. - Palisades Nuclear StationPM Entergy - Arkansas Nuclear One Florida Power & Light - Turkey Point Station New York Power Authority - James A. Fitzpatrick Nuclear Power Plant Niagara Mohawk Power Corporation - Nine Mile Point Nuclear Station PM Northern States Power Co. - Monticello Nuclear Generating Plant Northern States Power Co. - Prairie Island Nuclear Generating Plant Omaha Public Power District - Fort Calhoun Station (SPRA)
Public Service Electric & Gas - Salem Nuclear Station Rochester Gas & Electric - R.E. Ginna Station Wisconsin Electric - Point Beach Nuclear StationpM (SPRA)
Wisconsin Public Service - Kewaunee Nuclear Power PlantPM (SPRA)
P"' Indicates projects where Mr. Djordjevic served as Project Manager Hanford Reservation Savannah River Plant Reservation Rocky Flats Reservation Tooele US Army Depot Anniston US Army Reservation Umatilla US Army Reservation Newport US Army Reservation Aberdeen US Army Reservation A-13
ATTACHMENT 1 SEISMIC WALKDOWN REPORT He is a member of the IEEE 344 Standards Committee, Chairman of the ASCE Working Group for Seismic Evaluation of Electrical Raceways, and Chairman of the IES Committee for Microelectronics Cleanroom Vibrations Representative projects include overseeing the SEP shake-table testing of electrical raceways, in-situ testing of control panels and instrumentation racks at various nuclear facilities, equipment anchorage walkdowns and evaluations at various nuclear facilities. He is the principal author of the CERTIVAL VE software package to evaluate nuclear service valves, and contributing author in the development of the ANCHOR and EDASP software packages commercially distributed by S&A.
Mr. Djordjevic is an expert in the area of seismic fragility analysis and dynamic qualification of electrical and mechanical equipment. He has participated in and managed over twenty major projects involving the evaluation and qualification of vibration sensitive equipment and seismic hardening of equipment. As demonstrated by his committee work and publications, Mr. Djordjevic has participated in and contributed steadily to the development of equipment qualification and vibration hardening methodology.
PROFESSIONAL GROUPS Member, Institute of Electrical and Electronics Engineers, Nuclear Power Engineering Committee Working Group SC 2.5 (IEEE-344)
Chairman, Institute of Environmental Sciences, Working Group for Standardization of Reporting and Measuring Cleanroom Vibrations PARTIAL LIST OF PUBLICATIONS 1979 ASME PVP Conference, San Francisco, California, "Multi-Degree-of-Freedom Analysis of Power Actuated Valves", Paper No. 79-PVP-106 1983 ASME PVP Conference, Portland, Oregon, "A Computer Code for Seismic Qualification of Nuclear Service Valves", Paper No. 83-PVP-81 1983 ASME PVP Conference, Portland, Oregon, "Qualification of Electrical and Mechanical Equipment at Rocky Flats Reservation Using Prototype Analysis" 1984 ANS Conference, "Qualification of Class IE Devices Using In-Situ Testing and Analysis" 1986 Testing of Lithography Components for Vibration Sensitivity, Microelectronics, Cahners Publishing A-14
ATTACHMENT 1 SEISMIC WALKDOWN REPORT 1990 Nuclear Power Plant Piping and Equipment Conference, "Development of Generic Amplification Factors for Benchboard and Relay Cabinet Assemblies", Paper No. 106, Structures and Components Symposium, held by North Carolina State University 1991 Electric Power Research Institute, "Development of In-Cabinet Response Spectra for Benchboards and Vertical Panels," EPRI Report NP-7146 A-15
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Antonio Perez, P.E.
SUMMARY
Mr. Perez has ten years of experience in project management, project engineering, equipment design, and mechanical systems layout for nuclear and industrial facilities.
PROFESSIONAL EXPERIENCE Stevenson & Associates, Minneapolis, MN March 2007 - Present Project Manager Leading design team efforts at the Kewaunee Power Station on multiple projects that include Auxiliary Feedwater flow control modifications, Auxiliary Feedwater flow monitoring instrumentation modifications, and Auxiliary Building roof modifications.
" Performing various Project Management duties such as developing project plans, identification of resource needs, estimating task durations, developing project schedules, and monitoring budgets.
Dominion Energy Kewaunee (formerly Nuclear Management Company 2001 - 2005)
Kewaunee Power Station, Kewaunee, WI Shift Technical Advisor (trainee)
January 2006 - March 2007 Trainee in a 9 month Senior Reactor Operator Certificate training program.
Engineering Supervisor-ME/CE/SE Design May 2004 - January 2006 Supervising a staff of 12 to 15 engineers (mechanical, civil, and structural design) who are charged with developing design changes, maintaining design and licensing basis documentation and supporting maintenance.
Integrated the civil/structural engineering group and the mechanical engineering group into a cohesive unit that has resulted in gained efficiency and a net reduction of one full time equivalent engineer.
Substantially increased the quality of engineering products developed and published by the ME/CE/SE Design Engineering group through coaching and feedback as a result of increased supervisory over-site of engineering products.
Developed a work management system for the group that provides a means for prioritizing activities, estimating the level of effort, and scheduling of activities. This system has allowed for an increased understanding of workload and has become an invaluable tool for prioritizing work and managing resources.
Increased communications within the group by holding daily 15 minute meetings where station messages are delivered and where the group's resources are assessed and redirected as A-16
ATTACHMENT 1 SEISMIC WALKDOWN REPORT necessary to meet commitments. This has resulted in an increase in morale and an increase in commitments met.
Increased communications with other departments by establishing a central point of contact for the group and by assuring that the ME/CE/SE Design Engineering group was represented at Planning and Scheduling meetings.
Motor Operated Valve Engineer June 2001 - May 2004
" Established a project plan and led the implementation effort that re-organized the Motor-Operated Valve Program at KPS. This effort consisted of developing a Program Manual, developing controlled calculations, performing Design Basis Reviews, and compiling and/or establishing plant positions on known industry issues.
The result of this effort was a reduction of full time equivalent engineers, from 3 to 1, required to maintain the Program.
Performed and reviewed MOV safety related calculations including Minimum Required Stem Thrust, Weak Link Analysis, and Available Margin.
Assisted in MOV testing by providing engineering support to maintenance personnel.
DISTRIBUTION PLANNING, INC., Grandville, MI Systems Mechanical Engineer 2000 - 2001 Integrated mechanical systems and designed equipment for material handling systems.
Procured equipment and coordinated delivery schedules with vendors.
SMS SANDMOLD SYSTEMS, INC., Newaygo, MI Project Engineer /Manager 1998 -2000 Led multi-disciplinary project design teams for several projects that ranged in size from a few thousand dollars up to $2.2 million.
Coordinated efforts with engineering, manufacturing, and installation groups to establish and maintain project schedules that met or exceeded the client's expectations.
Procured equipment and coordinated delivery schedules with vendors.
Acted as the company's liaison with clients to work through issues that arose during projects.
Provided project status updates to clients and management.
Designed equipment such as sand storage bins - up to 540-ton live load capacity, bucket elevators, belt conveyors, screw conveyors, and mixers.
Most of this equipment was for handling of bulk solids (foundry sand).
Analyzed and designed structural support members for various types of equipment such as vibratory conveyors, mixers, and conveyors. Designed access structures such as stair towers, service platforms and catwalks.
" Calculated foundation loads and point loads of equipment support points.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT LIFT-TECH INTERNATIONAL, Muskegon, MI Project Engineer 1997-1998 Performed engineering analyses, wrote critiques, and recommended design modifications of structural members for the purpose of upgrading bridge cranes and hoists.
Implemented engineering design changes to enhance product development.
EDUCATION BS Mechanical Engineering Michigan Technological University, Houghton, MI Magna cum Laude LICENSES: Professional Engineer, Wisconsin: September 2002 A-1 8
ATTACHMENT 1 SEISMIC WALKDOWN REPORT Andrew J. Scheg PROFESSIONAL EXPERIENCE:
Nine Mile Point Nuclear Station, Oswego, NY (January 2011 - Current)
Probabilistic Risk Assessment Engineer Attended 6 week EPRI Education of Risk Professionals Course. Risk Informed In Service Inspection evaluation. Performed significance determination evaluations. Mitigating System Performance Index (MSPI) updates and evaluations. Developed and coordinated execution of NRC NTTF actions 2.1 (Seismic PRA) and 2.3 (Seismic Equipment Walkdowns). Qualified to conduct Seismic Equipment Walkdowns by EPRI/NRC. Maintenance Rule Expert Panel Member.
Nine Mile Point Nuclear Station, Oswego, NY (March 2006-December 2011)
Systems Engineer Managed and maintained the control rod drive (12 months), reactor water clean-up (12 months),
reactor building closed loop cooling (6 months), containment spray (9 months), Mitigating System Performance Index (4 years), and service water systems (2 years) for a dissimilar dual unit BWR site.
Aided in the response to INPO SOER 07-02, NRC Generic Letter 08-01, multiple INPO SER's, and triennial ultimate heat sink inspections.
Led responses to IER 10-1, SER-2-10, SER 10-1, and numerous apparent cause investigations.
Participated in numerous issue response teams for rectification of plant conditions which required rapid solutions.
Generated state of the art performance monitoring techniques for the control rod drive systems at each unit. Authored the CRD 2011 BWROG Technical Position Paper "Standard for CRD Stroke Timing". Instructed 6-week engineering orientation classroom training for BWR Systems Fundamentals.
Attended GE CRD Hydraulic System Training. Worked as a period of extended operation aging management evaluator.
Acted as the primary representative for the CRD and the Reactor Water Cleanup performance improvement committees.
Markin Tubing, Warsaw, NY (August 2004-March 2005)
Continuous Improvement Engineer Performed product audits, helped design new tooling for destructive testing, created process control charts, used statistical process control tools, dealt with customer complaint issues, analyzed methods of evaluating quantity of product delivered, created instruction manuals for many different operations.
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT WORK SKILLS:
Microsoft Office Suite, Microsoft Visio, problem solving via analytical methodologies (i.e. Koepner-Tregoe, FMEA, etc.), solid modeling, MathCAD, CAFTA, EOOS, HRA Calculator, OSI P1 Systems, INPO Consolidated Data Entry.
EDUCATION:
Rochester Institute of Technology, Rochester, New York Mechanical Engineering Technology Bachelor of Science (May 2006)
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT James H. Moody Summary and Background Mr. Moody has over twenty years of experience in the power industry, specializing in risk management, decision-making, probabilistic risk assessment, and reliability engineering. He has been a leader in both the development and application of risk assessment at numerous facilities. He is developing PRA models at AREVA for the European PWR to be licensed in the US, continues to support EPRI with risk-informed ISI projects and Constellation Energy with fire PRA and internal events PRA updates to meet the ASME Standard and Regulatory Guide 1.200.
Mr. Moody has worked to improve the effective integration of risk and reliability into plant operations and maintenance. The scope of these projects included on-site training and technical support to improve the risk assessment program and its interfaces with engineering, operations, and maintenance.
These projects have reduced plant outage time, reduced capital expenditures, provided an overall improvement in decision-making, and are preparing the plant for risk-informed regulation. While working at the Nine Mile plants, he developed their PRAs, added external and shutdown events to their models, incorporated risk assessment techniques into planning & scheduling, supported life extension evaluations, and supported equipment reliability program developments.
Additionally, Mr. Moody was a principal investigator in the development of the EPRI risk informed in-service inspection process.
This process has been approved by NRC and is being implemented at several plants to reduce the cost of pipe weld inspections while at the same time improving safety. He also worked with Electric Power Research Institute to extend the scope of Risk Informed Inservice Inspection to include break exclusion region augmented programs.
Mr. Moody's has been a technical lead in the development of Seismic PRA as follows:
Seabrook Station (1983)
Yankee Plant (1985)
Nine Mile Point Unit 2 (1995)
Nine Mile Point Unit 1 (1996)
Seabrook Station Seismic PRA Update (2005)
" AREVA EPR US (2008-2009)
KKM (Switzerland) Seismic PRA Peer Review (2010)
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ATTACHMENT 1 SEISMIC WALKDOWN REPORT Mr. Moody holds a Bachelor of Science degree from the University of Lowell and a Master of Science degree from Northeastern University.
Highlights of Recent Experience:
Mr. Moody has been supporting AREVA in developing a PRA to support design certification of their EPR plant. He is a key contributor to the initiating event analysis, several systems analyses, accident sequence modeling, success criteria analysis, low power shutdown modeling, and the seismic margins analysis.
He also supports EPRI with risk-informed ISI projects at several nuclear plants.
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ATTACHMENT (2)
EQUIPMENT LISTS Constellation Energy Nuclear Group, LLC November 27, 2012
ATTACHMENT 2 EQUIPMENT LISTS Appendix B contains the developed equipment lists and final SWELs. Note that because no Rapid Drain-Down items exist for NMP2, there is no Rapid Drain-Down Equipment List.
The following contents are found in Appendix B:
Table B-i, Nine Nile Point Unit 2 SW EL-1 Base List...........................................
B-2 Table B-2, Nine Nile Point Unit 2 SW EL-2 Base List...........................................
B-67 Table B-3, Nine M ile Point - 2 SW EL-1............................................................
B-85 Table B-4, Nine M ile Point - 2 SW EL-2............................................................
B-95 B-I
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2BYS*BAT2B 125V DC EMER. BAT DIV II BATTERY I
CBR 261 AE 15 1,2,3,4,5 EMERGENCY DC DISTRIBUTION 125 VDC 2BYS*BAT2C BATTERY DIV 3 BATTERY I
CSH 261 AB 15 1,2,3,4,5 BATTERY 2BYS*CHGR2A1 125V BAT CHGR DIV I CHARGER I
CSA 261 0
16 1,2,3,4,5 125V BAT CHGR STANDBY BATTERY 2BYS*CHGR2A2 DIV I CHARGER I
CSA 261 AE 16 1,2,3,4,5 BATTERY 2BYS*CHGR2B1 125V BAT CHGR.
CHARGER I
CSB 261 AG 16 1,2,3,4,5 125V BAT. CHGR. STAND BY BATTERY 2BYS*CHGR2B2 DIV. II CHARGER I
CSB 261 AE 16 1,2,3,4,5 EMERGENCY DC DISTRIBUTION 125V BATTERY 2BYS*CHGR2C1 BATTERY CHGR CHARGER I
CSH 261 AB 16 1,2,3,4,5 EMERGENCY DC DISTRIBUTION 125V BATTERY 2BYS*CHGR2C2 BATTERY CHGR CHARGER I
CSH 261 AB 16 1,2,3,4,5 2BYS*PNL201A 125VDC DIST PNL PNL I
CTR 288 AD 14 1,2,3,4,5 2BYS*PNL201B 125VDC DIST PNL PNL I
CTR 288 AD 14 1,2,3,4,5 2BYS*PNL202A 125VDC DIST PNL PNL I
CTR 288 AG 14 1,2,3,4,5 2BYS*PNL202B 125VDC DIST PNL PNL I
CRR 288 AE 14 1,2,3,4,5 B-2
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2BYS*PNL204B 125VDC DIST PNL PNL I
DG 261 AA 14 1,2,3,4,5 2BYS*SWG002B 125VDC SWITCHGEAR SWITCHGEAR I
CSB 261 AG 14 1,2,3,4,5 CCP AOV to Seal Cooler for RHR Pump, Fails Closed to allow SWP to provide cooling AIR OPERATED 2CCP*AOV37B to RHR Pump.
VALVE ABS 177 92 7
3,4,5 CCP AOV to Seal Cooler for RHR Pump, Fails Closed to allow SWP to provide cooling AIR OPERATED 2CCP*AOV38A to RHR Pump.
VALVE ABN 184 99 7
3,4,5 CCP AOV to Seal Cooler for RHR Pump. Fails Closed to allow SWP to provide cooling AIR OPERATED 2CCP*AOV38B to RHR Pump.
VALVE ABS 177 93 7
3,4,5 REDUNDANT REACTIVITY 2CEC*PO01 CONTROL PANEL PNL I
CRR 288 0
20 1
REDUNDANT REACTIVITY 2CEC*P002 CONTROL PANEL PNL I
CRR 288 0
20 1
2CEC*PNL601 PGCC PANEL PNL I
CCR 306 AE 20 1,2,3,4,5 REAC WTR CLEAN-UP &
RECIRCULATION BENCH 2CEC*PNL602 BOARD PNL I
CCR 306 AE 20 0
B-3
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions REACTOR CONTROL 2CEC*PNL603 BENCH BOARD PNL I
CCR 306 AE 20 1,2,3,4 RADN MONITORING 2CEC*PNL606 CABINET A PNL I
CCR 306 AG 20 5
CONTROL PANEL 2CEC*PNL608 (105E1505TYTYG001)
PNL I
CCR 306 AG 20 1,2,3,4,5 TRIP SYS A RPS VERT 2CEC*PNL609 BOARD PNL I
CCR 306 AH 20 1,2,3,4,5 TRIP SYS B RPS VERT 2CEC*PNL611 BOARD PNL I
CCR 306 AH 20 1,2,3,4,5 DIV 2 RESIDUAL HEAT PNL REMOVAL B & C RELAY 2CEC*PNL618 PANEL I
CCR 306 AF 20 3,4,5 REAC CORE ISOLATED PNL 2CEC*PNL621 COOLING RELAY PANEL I
CCR 306 AF 20 2,3,4,5 OUTBOARD VALVE RELAY PNL 2CEC*PNL623 PANEL I
CCR 306 AH 20 5
HIGH PRESS CORE SPRAY PNL 2CEC*PNL625 RELAY PANEL I
CCR 306 AE 20 3
AUTO DEPRESS SYSTEM A PNL 2CEC*PNL628 RELAY PANEL I
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions DIV I LOW PRESS CORE PNL SPRAY AND RHS A RELAY 2CEC*PNL629 PANEL I
CCR 306 AF 20 3,4,5 AUTO DEPRESS SYS B RLY PNL 2CEC*PNL631 PNL I
CCR 306 AF 20 2,3 2CEC*PNL632 DIV 1 LEAK DETECTION PNL PNL I
RADIATION MONITORING PNL 2CEC*PNL633 CABINET B I
CCR 306 AG 20 5
DIV 2 LEAK DETECTION PNL 2CEC*PNL642 PANEL I
PGCC TERMINATION 2CEC*PNL700 CABINET PNL I
CCR 306 AE 20 0
PGCC TERMINATION 2CEC*PNL701 CABINET PNL I
CCR 306 AE 20 0
PGCC TERMINATION 2CEC*PNL702 CABINET PNL I
CCR 306 AE 20 0
PGCC TERMINATION 2CEC*PNL704 CABINET PNL I
CCR 306 AG 20 0
PGCC TERMINATION 2CEC*PNL705 CABINET PNL I
CCR 306 AG 20 0
PGCC TERMINATION 2CEC*PNL706 CABINET PNL I
CCR 306 AG 20 0
B-5
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PGCC TERMINATION 2CEC*PNL707 CABINET PNL I
CCR 306 AG 20 0
PGCC TERMINATION 2CEC*PNL708 CABINET PNL I
CCR 306 AG 20 0
PGCC TERMINATION 2CEC*PNL709 CABINET PNL I
CCR 306 AG 20 0
PGCC TERMINATION 2CEC*PNL730 CABINET PNL I
CRR 288 AG 20 0
PGCC TERMINATION 2CEC*PNL731 CABINET PNL I
CRR 288 AG 20 0
2CEC*PNL733 PGCC TERM CABINET PNL I
CRR 288 AG 20 0
PGCC TERMINATION 2CEC*PNL734 CABINET PNL I
CRR 288 AG 20 0
PGCC TERMINATION 2CEC*PNL736 CABINET PNL I
CRR 288 AG 20 0
PGCC TERMINATION 2CEC*PNL737 CABINET PNL I
CRR 288 AG 20 0
PGCC TERMINATION 2CEC*PNL741 CABINET PNL I
CCR 306 AG 20 0
PGCC TERMINATION 2CEC*PNL742 CABINET PNL I
CCR 306 AG 20 0
B-6
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PGCC TERMINATION 2CEC*PNL745 CABINET PNL I
CRR 288 AE 20 0
PGCC TERMINATION 2CEC*PNL748 CABINET PNL I
PGCC TERMINATION 2CEC*PNL752 CABINET PNL I
CRR 288 AE 20 0
PGCC TERMINATION 2CEC*PNL753 CABINET PNL I
CRR 288 AE 20 0
PGCC TERMINATION 2CEC*PNL754 CABINET PNL I
CRR 288 AE 20 0
BOP INSTRUMENT PNL PNL 2CEC*PNL829 DIV1 I
CRR 288 AJ 20 3,4,5 BOP INSTRUMENT PNL PNL 2CEC*PNL830 DIV2 I
CRR 288 AJ 20 3,4,5 BOP INSTRUMENT PNL PNL 2CEC*PNL831 DIV2 I
CRR 288 AJ 20 3,4,5 DIV I BOP ISOLATION PNL 2CEC*PNL837 CABINET I
CRR 288 AE 20 5
DIV II BOP ISOLATION PNL 2CEC*PNL838 CABINET I
CRR 288 AE 20 5
TURB GEN STEAM &
WATER CONTROL BENCH 2CEC*PNL851 BOARD PNL I
B-7
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions ELECTRICAL CONTROL 2CEC*PNL852 BENCH BOARD PNL I
CCR 306 AC 20 1,2,3,4,5 DIV II AUXILIARY RELAY PNL 2CEC*PNL861 PANEL I
CRR 288 AE 20 1,2,3,4,5 HEATING, VENTILATION &
PNL AIR CONDITIONING CONT 2CEC*PNL870 PANEL A I
CCR 306 AG 20 0
HEATING, VENTILATION &
PNL AIR CONDITIONING CONT 2CEC*PNL871 PANEL B I
CCR 306 AG 20 0
PRIMARY CONTAINMENT PNL 2CEC*PNL873 PURGE PANEL A I
CCR 306 AG 20 5
2CEC*PNL874 BOP ISOLATION CABINET PNL I
CRR 288 AE 20 3,4,5 PRIMARY CONTAINMENT PNL 2CEC*PNL875 PURGE PANEL B I
CCR 306 AG 20 5
PROCESS AREA RADIATION PNL 2CEC*PNL880 MONITORING PANEL I
CCR 306 AE 20 5
BOP INSTRUMENT PANEL PNL 2CEC*PNL883 DIV 3 1
CRR 288 AJ 20 3
BOP INSTRUMENT PANEL PNL 2CEC*PNL890 DIV 1 1
CRR 288 AJ 20 3,4,5 BOP INSTRUMENT PANEL PNL 2CEC*PNL891 DIV 2 I
CRR 288 AJ 20 3,4,5 B-8
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions DIV 2 SUPPRESSION POOL PNL 2CEC*PNL895 TEMP MONITORING PANEL I
CRR 288 AF 20 3,4,5 BOP INSTRUMENT PANEL PNL 2CEC*PNL897 DIV 2 1
CRR 288 AJ 20 2,3,4 POST ACCIDENT PNL 2CEC*PNL898 MONITORING PANEL I
CCR 306 AE 20 0
2CEC*PNL899 ERF ISOLATOR PANEL PNL I
CRR 288 AG 20 0
2EGS*EG3 CONTROL PNL PANEL (ECPC/CONTROL 2CES*IPNL408 VOLTAGE 25 VDC)
I DG 261 AA 20 1,2,3,4,5 2EGS*EG3 CONTROL PNL PANEL (EGPC/CONTROL 2CES*IPNL412 VOLTAGE 125 VDC)
I DG 261 AA 20 1,2,3,4,5 125 VDC HPCS DIESEL GENERATOR CONTROL 2CES*IPNL413 PANEL PNL I
C.R. FIRE DISCONNECT 2CES*PNL415 PNL DIV I PNL I
CB 306 AC 20 1,2,3,4,5 C.R. FIRE DISCONNECT 2CES*PNL416 PNL DIV II PNL 1
CB 306 AE 20 1,2,3,4,5 SERVICE WATER STRAINERS CONTROL 2CES*PNL505 PANEL PNL I
SA 261 M
20 3,4,5 B-9
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions STARTUP TESTING/TRANSIENT ANAL RECORDING SYSTEM 2CES*PNL517 PANEL PNL CB 237 AG 20 0
STARTUP TESTING/TRANSIENT ANAL RECORDING SYSTEM 2CES*PNL519 PANEL PNL CB 237 AG 20 0
STARTUP TESTING/TRANSIENT ANAL RECORDING SYSTEM 2CES*PNL520 PANEL PNL CB 244 AB 20 0
POST ACCIDENT SAMPLING ISOLATION VALVES 2CES*PNL554 CONTROL PANEL PNL I
CTR 237 AE 20 0
RACK (LOW PRESSURE CORE SPRAY SYSTEM 2CES*RAK001 INSTRUMENTATION)
RAK SC 175 54 18 3
RACK (RWCU 2CES*RAK002 INSTRUMENTATION)
RAK SC 289 45 18 5
RACK (RWCU 2CES*RAK003 INSTRUMENTATION)
RAK SC 289 70 18 5
RACK (RPS/WCS RAK 2CES*RAK005 INSTRUMENTATION)
SC 261 53 18 1,2,3,4,5 B-10
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions RACK (RECIRC PUMP A RAK 2CES*RAK006 INSTRUMENTATION)
SC 215 71 18 0
RACK - LOCAL PANEL A (
RAK JET PUMP LOOP B 2CES*RAK009 INSTRUMENTATION)
SC 215 74 18 0
RACK-LOCAL PANEL B JET PUMP LOOP A 2CES*RAK010 INSTRUMENTATION)
RAK SC 215 74 18 0
RACK (SLS 2CES*RAK011 INSTRUMENTATION)
RAK SC 289 75 18 1
RACK (RHS 2CES*RAK018 INSTRUMENTATION)
RAK SC 175 80 18 3,4,5 RACK (RHS 2CES*RAK021 INSTRUMENTATION)
RAK SC 175 80 18 3,4,5 RACK (RECIRCULATION 2CES*RAK022 PMP B INSTRUMENTATION)
RAK SC 215 55 18 0
RACK (MAIN STEAM FLOW 2CES*RAK025 A/B INSTRUMENTATION)
RAK SC 215 57 18 0
RACK (RV LEVEL/PRESS INSTRUMENTAATION/RACK 2CES*RAK027 B)
RAK SC 261 53 18 1,2,3,4 RACK (SRM/IRM PRE-AAMP 2CES*RAK031 INSTRUMENTATION)
RAK SC 240 60 18 1,2,3,4,5 B-1I
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions RACK (SRM/IRM PRE-AMP 2CES*RAK032 INSTRUMENTATION)
RAK SC 240 64 18 1,2,3,4,5 RACK (SRM/IRM PRE-AMP 2CES*RAK033 INSTRUMENTATION)
RAK SC 240 64 18 1,2,3,4,5 RACK 9MAIN STEAM FLOW 2CES*RAK041 INSTRUMENTATION)
RAK SC 215 55 18 0
RACK (SFC/CMS 2CES*RAK105 INSTRUMENTATION)
RAK SC 261 52 18 4,5 RACK (MSS 2CES*RAK231 INSTRUMENTATION)
RAK I
MST 277 W
18 0
RACK (MSS 2CES*RAK232 INSTRUMENTATION)
RAK I
MST 277 Y
18 0
CONTMT ATM LEAKAGE 2CMS*CAB10A RADN CABINET CAB SC 289 68 20 5
CONTMT ATM LEAKAGE 2CMS*CAB10B RADN CABINET CAB I
SC 289 67 20 5
2CMS*PNL66A H.2 ANALYZER PNL A PNL I
SC 240 0
20 5
2CMS*PNL66B H.2 ANALYZER PNL B PNL I
SC 240 0
20 5
2CMS*PNL73A H2/02 REMOTE PNL A PNL I
ABN 240 97 20 5
2CMS*PNL73B H2/02 REMOTE PNL B PNL I
ABS 240 97 20 5
0-2 CALIBRATION BOTTLE 2CMS*PNLX66A RACK PNL I
ABN 240 91 20 0
B-12
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 0-2 CALIBRATION BOTTLE 2CMS*PNLX66B RACK PNL I
ABS 240 92 20 0
H-2 CALIBRATION BOTTLE 2CMS*PNLY66A RACK PNL I
ABN 215 89 20 0
H-2 CALIBRATION BOTTLE 2CMS*PNLY66B RACK PNL I
ABS 215 89 20 0
100 OHM @ ODEG C PLATINUM RESISTANCE TEMP DETECTOR RESISTANCE TEMP DETECTOR, MONITORS 2CMS*TE101 DRYWELL TEMPERATURES TE I
PC 307 30 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR RESISTANCE TEMP DETECTOR, MONITORS 2CMS*TE102 DRYWELL TEMPERATURE PC 289 36 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR RESISTANCE TEMP DETECTOR, MONITORS 2CMS*TE103 DRYWELL TEMPERATURE PC 283 36 19 5
B-13
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS DRYWELL 2CMS*TE1 19 TEMPERATURE PC 262 41 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE 2CMS*TE121 TEMP DETECTOR PC 244 46 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE67A TEMPERATURE PC 223 46 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE67B TEMPERATURE PC 223 46 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE68A TEMPERATURE PC 223 46 19 5
B-14
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE68B TEMPERATURE PC 223 46 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE69A TEMPERATURE PC 223 46 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE69B TEMPERATURE PC 223 46 19 5
100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE70A TEMPERATURE PC 223 46 19 5
B-15
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 100 OHM @ ODEG C TE PLATINUM RESISTANCE TEMP DETECTOR, MONITORS SUPPRESSION POOL WATER 2CMS*TE70B TEMPERATURE PC 223 46 19 5
2CPS-FN1 PURGE INLET TO SUPPRESSION CHAMBER OUTSIDE AUTOMATIC AIR OPERATED 2CPS*AOV105 ISOLATION VALVE VALVE SC 220 56 7
5 2CPS-FN1 PURGE INLET TO DRYWELL INSIDE AUTOMATIC ISOLATION AIR OPERATED 2CPS*AOV106 VALVE VALVE PC 294 33 7
5 PURGE INLET TO SUPPRESSION CHAMBER INSIDE AUTOMATIC AIR OPERATED 2CPS*AOV107 ISOLATION VALVE VALVE PC 220 44 7
5 PURGE EXHAUST FROM SUPPRESSION CHAMBER INSIDE AUTOMATIC AIR OPERATED 2CPS*AOV109 ISOLATION VALVE VALVE PC 218 44 7
5 B-16
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 1
2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PURGE EXHAUST FROM
- DRYWELL OUTSIDE AUTOMATIC ISOLATION AIR OPERATED 2CPS*AOV110 VALVE VALVE I
SC 295 44 7
5 2CPS*SOV109 SUPPR DISCH INBD ISOL V SOLENOID VALVE I
PC 218 44 8
5 CONTAINMENT PURGE TO SUPPRESSION CHAMBER OUTSIDE AUTOMATIC 2CPS*SOV1 19 ISOLATION VALVE SOLENOID VALVE I
SC 222 58 8
5 CONTAINMENT PURGE TO DRYWELL OUTSIDE AUTOMATIC ISOLATION 2CPS*SOV120 VALVE SOLENOID VALVE I
SC 296 55 8
5 CONTAINMENT PURGE TO SUPPRESSION CHAMBER.
INSIDE AUTOMATIC 2CPS*SOV121 ISOLATION VALVE SOLENOID VALVE I
PC 217 43 8
5 CONTAINMENT PURGE TO DRYWELL INSIDE AUTOMATIC ISOLATION 2CPS*SOV122 VALVE SOLENOID VALVE I
PC 296 34 8
5 NITROGEN TO 2CPS*AOV109 OUTSIDE AUTOMATIC ISOLATION 2CPS*SOV133 VALVE SOLENOID VALVE I
SC 217 0
8 5
B-17
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MOTOR OPERATED VALVE, MOTOR TEST RETURN TO COND.
OPERATED 2CSH*MOV110 TANK VALVE I
SC 198 54 8
0 CSH TEST RETURN TO SUPPRESSION POOL MOTOR OUTSIDE AUTOMATIC OPERATED 2CSH*MOV111 ISOLATION VALVE VALVE SC 218 79 8
3 MOTOR OPERATED VALVE, MOTOR TEST RETURN TO COND OPERATED 2CSH*MOV112 TANK VALVE I
SC 198 74 8
0 CORE SPRAY PUMP TEST, LPCS TEST RET TO SUPPR 2CSL*FV114 POOL FLOW VALVE I
SC 203 B
8 0
MOTOR OPERATED 2CSL*MOV107 CSL Min flow line VALVE I
ABN 178 99 8
3 2CSL*P1 LP CORE SPRAY PUMP PUMP I
ABN 175 W
6 3
DER LINE FROM DRYWELL MOTOR INSIDE AUTOMATIC OPERATED 2DER*MOV119 ISOLATION VALVE VALVE I
PC 217 44 8
5 DER LINE FROM DRYWELL MOTOR OUTSIDE AUTOMATIC OPERATED 2DER*MOV120 ISOLATION VALVE VALVE I
SC 217 58 8
5 B-18
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions DER VENT LINE INSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2DER*MOV130 VALVE VALVE PC 243 44 8
5 DER VENT LINE OUTSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2DER*MOV131 VALVE VALVE SC 243 B
8 5
DFR DRAIN TANK LINE MOTOR INSIDE AUTOMATIC OPERATED 2DFR*MOV121 ISOLATION VALVE VALVE PC 218 44 8
5 DFR VENT LINE OUTSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2DFR*MOV139 VALVE VALVE SC 241 B
8 5
DFR VENT LINE INSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2DFR*MOV140 VALVE VALVE I
PC 257 40 8
5 2DMS*MCCB1 125VDC MCC MCC I
ABS 240 98 14 1,2,3,4,5 2EGA*TK1 B COMP AIR RECEIVER TANK Tank I
DG 261 0
21 1,2,3,4,5 2EGA*TK2A COMP AIR RECEIVER TANK Tank I
DG 261 0
21 1,2,3,4,5 2EGA*TK2B COMP AIR RECEIVER TANK Tank I
DG 261 0
21 1,2,3,4,5 COMPRESSED AIR 2EGA*TK3 RECEIVER TANK, 64 CU FT Tank I
DG 261 0
21 3
COMPRESSED AIR 2EGA*TK4 RECEIVER TANK, 64 CU FT Tank I
DG 261 0
21 3
B-19
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions FUEL OIL TRANSFER 2EGF*IPNL112 CONTROL PANEL PNL I
DG 261 AA 20 1,2,3,4,5 2EGF*P1 B FUEL OIL TRANSFER PUMP Pump I
DG 261 A
6 1,2,3,4,5 2EGF*P1C FUEL OIL TRANSFER PUMP Pump I
DG 261 A
6 1,2,3,4,5 2EGF*P1 D FUEL OIL TRANSFER PUMP Pump I
DG 261 A
6 1,2,3,4,5 2EGF*P2A FUEL OIL TRANSFER PUMP Pump I
DG 261 A
6 3
2EGF*P2B FUEL OIL TRANSFER PUMP Pump I
DG 261 A
6 3
STDBY DIESEL GEN FUEL 2EGF*TK3B TK (DAY TANK) 660 GAL.
Tank I
DG 275 0
21 1,2,3,4,5 HPCS DIESEL GEN FUEL 2EGF*TK4 OIL DAY TANK 660 GAL Tank I
DG 275 0
21 3
DSL GEN DIV 1 GETARS 2EGP*PNL101 INPUT SIGNALS PNL I
DSL GEN DIV 2 GETARS 2EGP*PNL103 INPUT SIGNALS PNL I
ENGINE 2EGS*EG2 DIESEL GENERATOR 2 GENERATOR I
ENGINE 2EGS*EG3 DIESEL GENERATOR 3 GENERATOR I
DG 261 AA 17 1,2,3,4,5 PANEL (HPCS DG 2EGS*PNLO28 2EGS*EG2 PROTECTION)
PNL I
CSH 261 AA 20 3
B-20
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PANEL (HIGH VOLTAGE DIESEL GENERATOR 2EGS*PNL11 2EGS*EG1 CONTROL)
PNL I
DG 261 AA 20 1,2,3,4,5 PANEL (HIGH VOLTAGE DIESEL GENERATOR 2EGS*PNL31 2EGS*EG3 CONTROL)
PNL I
DG 261 AA 20 1,2,3,4,5 MOTOR CONTROL 2EHS*MCC103 STANDBY MCC CLASS 1E CENTER I
CSA 261 AD 1
1,2,3,4,5 MOTOR HPCS MOTOR CONTROL CONTROL 2EHS*MCC201 CENTER CENTER I
CSH 261 AB 1
3 MOTOR CONTROL 2EHS*MCC301 EMER MCC 301 CENTER I
SW 261 L
1 1,2,3,4,5 MOTOR CONTROL 2EHS*MCC302 EMERG MCC CENTER I
ABS 240 W
1 1,2,3,4,5 MOTOR CONTROL 2EHS*MCC303 EMER MCC 303 CENTER I
CSB 261 AD 1
1,2,3,4,5 REACTOR BLDG 120/280V 2EJA*PNL100A HEATER PANEL PNL I
ABN 240 W
14 0
B-21
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions REACTOR BLDG 120/280V 2EJA*PNL300B HEATER PANEL PNL I
ABS 240 W
14 0
2EJA*PNL301B 120/240V AC DIST PANEL PNL I
CSB 261 AG 14 0
SWITCHGEAR RM A 2EJS*PNL101A EMERGENCY 600V PANEL PANEL I
ABN 240 W
14 1,2,3,4,5 SWITCHGEAR ROOM A 2EJS*PNL102A EMERGENCY 600V PANEL PNL I
CCL 261 AA 2
1,2,3,4,5 2EJS*PNL103A EMERGENCY 600V PANEL PNL I
ABN 240 W
2 1,2,3,4,5 EMERGENCY 600V PANEL 2EJS*PNL300B SWGR RM B PANEL I
CSB 261 AG 2
1,2,3,4,5 600V EMERGENCY DIST 2EJS*PNL301B PANEL PNL I
CCL 261 AA 2
1,2,3,4,5 2EJS*PNL302B EMERGENCY 600V PANEL PANEL I
ABS 240 E
2 1,2,3,4,5 2EJS*PNL303B EMERGENCY 600V PANEL PNL I
ABS 240 W
2 1,2,3,4,5 AB-S EMERGENCY 600V 2EJS*PNL304B PANEL PNL I
ABS 240 W
2 1,2,3,4,5 UNIT 2EJS*US3 600V US EMER SWGR SUBSTATION I
CSB 261 AE 2
1,2,3,4,5 4160/600V EMER XFMR 1A LOCATED IN 2EJS*US1 CUB 2EJS*X1A 2
TRANSFORMER I
CSA 261 AE 4
1,2,3,4,5 B-22
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 4160/600V EMER XFMR 1B LOCATED IN 2EJS*US1 2EJS*X1B CUB10 TRANSFORMER I
CSA 261 AG 4
1,2,3,4,5 4160/600V EMER XFMR 3A LOCATED IN 2EJS*US3 CUB 2EJS*X3A 2
TRANSFORMER I
CSB 261 AG 4
1,2,3,4,5 4160/600V EMER XFMR 3B LOCATED IN 2EJS*US3 CUB 2EJS*X3B 10 TRANSFORMER I
CSB 261 AE 4
1,2,3,4,5 4160 EMER SWGR 102 2ENS*SWG102 (HPCS)
SWITCHGEAR I
CSH 261 AB 3
1,2,3,4,5 2ENS*SWG103 4160 EMER SWGR 103 SWITCHGEAR I
CSB 261 AD 3
1,2,3,4,5 FEEDWATER TO RPV MOTOR OUTSIDE REMOTE MANUAL OPERATED 2FWS*MOV21A ISOLATION VALVE VALVE I
MST 257 74 8
5 FEEDWATER TO RPV MOTOR OUTSIDE REMOTE MANUAL OPERATED 2FWS*MOV21B ISOLATION VALVE VALVE I
MST 257 74 8
5 BUTTERFLY OR AIR OPERATED 2GTS*AOV2B TRICENTRIC V VALVE SG 269 F
7 5
BUTTERFLY OR AIR OPERATED 2GTS*AOV3A TRICENTRIC V VALVE SG 277 H
7 5
B-23
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions BUTTERFLY OR AIR OPERATED 2GTS*AOV3B TRICENTRIC V VALVE SG 277 H
7 5
PANEL (FLTR TRN FAN 2GTS*FN1A ELAPSED TIME 2GTS*PNL101 INDICATOR)
PNL I
ABN 240 0
20 0
PANEL (FLTR TRN FAN 2GTS*FN1B ELAPSED TIME 2GTS*PNL102 INDICATOR)
PNL I
ABS 240 0
20 0
REMOTE CONTROL PANEL 2GTS*PNL30A FOR 2GTS*CH1A PNL SG 268 E
20 5
REMOTE CONTROL PANEL 2GTS*PNL30B FOR 2GTS*CH 1B PNL SG 268 E
20 5
RB IN/OUT DIFF PRESS 2GTS*PNL5A PANEL PNL ET 220 EX 20 0
RB IN/OUT DIFF PRESS 2GTS*PNL5B PANEL PNL ET 220 AG 20 0
RX BLDG IN/OUT DIFF PRESSURE 2GTS*PV5A PRESS VALVE SG 275 H
7 0
RX BLDG IN/OUT DIFF PRESSURE 2GTS*PV5B PRESS VALVE I
SG 275 H
7 0
B-24
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PANEL (HYDROGEN RECOMBINER 2HCS*RBNR1A POWER 2HCS*PNL22A CABINET)
PNL I
ABN 240 W
20 5
PANEL (HYDROGEN RECOMBINER 2HCS*RBNRIB POWER 2HCS*PNL22B CABINET)
PNL I
ABS 240 E
20 5
PANEL (HEAT TRACING 2HTS*PNL001 SYSTEM)
PNL I
ABN 240 NW 14 0
PANEL (HEAT TRACING 2HTS*PNLOO3 SYSTEM)
PNL I
ABS 240 SW 14 0
CONT/RLY RMS INTAKE RADIATION, MONITORS CONTROL ROOM AIR IN 2HVC*CAB18A TAKE "A" CAB I
CCR 306 AB 20 1,2,3,4,5 CONT/RLY RMS INTAKE RADIATION, MONITORS CONTROL ROOM AIR IN 2HVC*CAB18B TAKE "B" CAB I
CCR 306 AB 20 1,2,3,4,5 CONT/RLY RMS INTAKE RADIATION, MONITORS CONTROL ROOM AIR IN 2HVC*CAB18C TANK "C" CAB I
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions CONT/RLY RMS INTAKE RADIATION, MONITORS CONTROL ROOM AIR IN 2HVC*CAB18D TAKE "D" CAB I
CCR 306 AB 20 1,2,3,4,5 PANEL (FLTR TRN FAN 2HVC*FN2A ELAPSED TIME 2HVC*PNL301 INDICATOR)
PNL I
CSA 261 AD 20 1,2,3,4,5 PANEL (FLTR TRN FAN 2HVC*FN2B ELAPSED TIME 2HVC*PNL302 INDICATOR)
PNL I
CSB 261 AS 20 1,2,3,4,5 2HVC*PNLCH1 1 CONTROL PANEL FOR A
2HVC*CH11A PNL I
CCA 306 AB 20 1,2,3,4,5 2HVC*PNLCH1 1 CONTROL PANEL FOR B
2HVC*CH 11B PNL I
CCA 306 AB 20 1,2,3,4,5 2HVC*PNLCH12 CONTROL PANEL FOR A
2HVC*CH12A PNL I
CRA 277 AB 20 1,2,3,4,5 2HVC*PNLCH12 CONTROL PANEL FOR B
2HVC*CH12B PNL I
CRA 288 AB 20 1,2,3,4,5 CONTROL PANEL FOR 2HVC*PNLCH7A 2HVC*CH7A PNL I
CRA 288 AC 20 1,2,3,4,5 CONTROL PANEL FOR 2HVC*PNLCH7B 2HVC*CH7B PNL I
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions LOCAL CONTROL PANEL 2HVK*PNL21A FOR 2HVK*TV21A PNL I
CRA 288 AA 20 1,2,3,4,5 LOCAL CONTROL PANEL 2HVK*PNL21B FOR 2HVK*TV21B PNL I
CCA 306 AA 20 1,2,3,4,5 LOCAL CONTROL PANEL 2HVK*PNL22A FOR 2HVK*TV22A PNL I
CRA 288 AA 20 1,2,3,4,5 LOCAL CONTROL PANEL 2HVK*PNL22B FOR 2HVK*TV22B PNL I
CCA 306 AA 20 1,2,3,4,5 AIR OPERATED 2HVP*AOD4A INLET DMPR DAMPER I
DG 284 A
7 1,2,3,4,5 AIR OPERATED 2HVP*AOD4B INLET DMPR DAMPER I
DG 284 A
7 1,2,3,4,5 AIR, OPERATED 2HVP*AOD4C INLET DMPR DAMPER I
DG 284 A
7 1,2,3,4,5 AIR OPERATED 2HVP*AOD4D INLET DMPR DAMPER I
DG 284 A
7 1,2,3,4,5 AIR OPERATED 2HVP*AOD5A INLET DMPR DAMPER I
DG 284 A
7 1,2,3,4,5 AIR OPERATED 2HVP*AOD5B INLET DMPR DAMPER I
DG 284 A
7 1,2,3,4,5 AXIAL FANS (ROOM 1 EXCH 2HVP*FN1A FAN 1A)
FAN I
1,2,3,4,5 B-27
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2HVP*FN1B AXIAL FAN - DG FAN I
1,2,3,4,5 2HVP*FN1D AXIAL FAN - DG FAN I
1,2,3,4,5 AXIAL FANS (ROOM 2 EXH 2HVP*FN2A FAN 2A)
1,2,3,4,5 AXIAL FANS (ROOM 2 EXH 2HVP*FN2B FAN 2B)
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD1A DAMPER DAMPER DG 279 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD1B DAMPER DAMPER DG 279 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD1D DAMPER DAMPER DG 279 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD2A DAMPER DAMPER DG 279 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD2B DAMPER DAMPER DG 279 AA 8
1,2,3,4,5 B-28
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MOTOR MOTOR OPERATED OPERATED 2HVP*MOD6A DAMPER DAMPER DG 280 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD6B DAMPER DAMPER DG 280 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD6D DAMPER DAMPER DG 280 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD7A DAMPER DAMPER DG 280 AA 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD7B DAMPER DAMPER DG 280 AA 8
1,2,3,4,5 INDICATING TEMPERATURE SWITCH, 2EGS*G2 CONT Temperature 2HVP*TIS120 RM TEMP Indicating Switch I
DG 269 AA 19 1,2,3,4,5 OIL-FILLED CAPILLARY TEMPERATURE SWITCH TEMP INDICATING SWITCH, Temperature 2HVP*TIS13B 2EGS*G3 CONT RM TEMP Indicating Switch I
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions UNIT COOLER FOR STANDBY DIESEL 2HVP*UC1B GENERATOR ROOM (DG3)
UNIT COOLER I
DG 280 AA 10 1,2,3,4,5 UNIT COOLER FOR STANDBY DIESEL 2HVP*UC2 GENERATOR ROOM (DG2)
UNIT COOLER I
ABOVE REFUEL FL 2HVR*CAB14A RADIATION CABINET CAB SC 328 79 20 0
ABOVE REFUEL FL 2HVR*CAB14B RADIATION CABINET CAB SC 328 71 20 0
RB BELOW REFUEL FL 2HVR*CAB32A RADIATION CABINET CAB SC 289 60 20 0
RB BELOW REFUEL FL 2HVR*CAB32B RADIATION CABINET CAB I
SC 289 62 20 0
2HVR*UC401B RHR PUMP RM C-UNIT CLR UNIT COOLER I
ABS 183 E
10 3,4,5 2HVR*UC401C RHR PUMP RM B-UNIT CLR UNIT COOLER I
ABS 175 W
10 3,4,5 2HVR*UC401D RHR PUMP RM A-UNIT CLR UNIT COOLER I
ABN 176 E
10 3,4,5 2HVR*UC401E RHR PUMP RM C-UNIT CLR UNIT COOLER I
ABS 177 E
10 3,4,5 2HVR*UC401F RHR PUMP RM B-UNIT CLR UNIT COOLER I
ABS 177 W
10 3,4,5 2HVR*UC402A LPCS PUMP RM UNIT CLR UNIT COOLER I
ABN 176 W
10 3
2HVR*UC402B LPCS PUMP RM UNIT CLR UNIT COOLER I
ABN 177 W
10 3
2HVR*UC403B HPCS PUMP RM UNIT CLR UNIT COOLER I
SC 203 B
10 3
B-30
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2HVR*UC408A ELEC MCC AREA UNIT CLR UNIT COOLER I
ABN 250 E
10 1,2,3,4,5 2HVR*UC408B ELEC MCC AREA UNIT CLR UNIT COOLER I
ABN 250 E
10 1,2,3,4,5 2HVR*UC4o9A ELEC MCC AREA UNIT CLR UNIT COOLER I
ABS 250 W
10 1,2,3,4,5 2HVR*UC409B ELEC MCC AREA UNIT CLR UNIT COOLER I
ABS 250 W
10 1,2,3,4,5 RCIC PUMP ROOM UNIT 2HVR*UC412A CLR UNIT COOLER I
SC 186 B
10 2,3,4 RCIC PUMP ROOM UNIT 2HVR*UC412B CLR UNIT COOLER I
SC 176 B
10 2,3,4 ADS HEADER B N2 SUPPLY OUTSIDE AUTOMATIC 21AS*SOV165 ISOLATION VALVE SOLENOID VALVE I
SC 294 43 8
2,3,5 IAS TO MSS SAFETY RELIEF VALVE OUTSIDE AUTOMATIC ISOLATION 21AS*SOV166 VALVE SOLENOID VALVE I
SC 294 B
8 2,3,5 INSTRUMENT AIR TO TESTABLE CHECK INSIDE AUTOMATIC ISOLATION 21AS*SOV180 VALVE SOLENOID VALVE I
PC 294 B
8 2,3,5 IAS TO MSS SAFETY RELIEF VALVE INSIDE AUTOMATIC ISOLATION 21AS*SOV184 VALVE SOLENOID VALVE I
PC 294 B
8 2,3,5 B-3.1
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions ADS HEADER B PRESSURESOLENOID SOLENOID VALVE 21AS*SOVX186 OPERATED VALVE AUXILIARY I
SC 296 46 8
2,3 ADS HEADER A SOLENOID VALVE PRESSURESOLENOID 21AS*SOVY181 OPERATED VALVE I
SC 294 47 8
2,3 21AS*SOVY186 ADS HEADER B PRESSURE SOLENOID VALVE I
SC 296
- 46 8
2,3 21AS*TK4 ADS ACC AIR SAFETY VALVE 21AS*SV19A RCVG TANK SC 289 50 8
2,3 21AS*TK5 ADS ACC AIR SAFETY VALVE 21AS*SV19B RCVG TANK I
SC 289 50 8
2,3 21AS*SV20A 21AS*TK4 ADS VALVE SAFETY VALVE I
SC 289 46 7
2,3,5 21AS*SV20B 21AS*TK5 ADS VALVE SAFETY VALVE I
SC 294 46 7
2,3,5 MS S/R VALVE 21AS*TK14 ACCUMULATOR TANK PC 289 0
21 2,3 MS S/R VALVE 21AS*TK15 ACCUMULATOR TANK PC 289 0
21 2,3 MS S/R VALVE 21AS*TK16 ACCUMULATOR TANK PC 289 0
21 2,3 MS S/R VALVE 21AS*TK18 ACCUMULATOR TANK PC 289 0
21 2,3 B-32
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MS SIR VALVE 21AS*TK19 ACCUMULATOR TANK I
PC 289 0
21 2,3 MS S/R VALVE 21AS*TK20 ACCUMULATOR TANK I
PC 289 0
21 2,3 MS S/R VALVE 21AS*TK23 ACCUMULATOR TANK I
PC 289 0
21 2,3 MS S/R VALVE 21AS*TK26 ACCUMULATOR TANK I
PC 289 0
21 2,3 MS S/R VALVE 21AS*TK30 ACCUMULATOR TANK I
PC 289 0
21 2,3 MS S/R VALVE 21AS*TK31 ACCUMULATOR TANK I
PC 289 0
21 2,3 21AS*TK32 ADS VALVE ACCUMULATOR TANK I
PC 289 0
.21 2,3 21AS*TK33 ADS VALVE ACCUMULATOR TANK I
PC 289 0
21 2,3 21AS*TK35 ADS VALVE ACCUMULATOR TANK I
PC 289 0
21 2,3 21AS*TK36 ADS VALVE ACCUMULATOR TANK I
PC 289 0
21 2,3 21AS*TK37 ADS VALVE ACCUMULATOR TANK I
PC 289 0
21 2,3 21AS*TK38 ADS VALVE ACCUMULATOR TANK I
PC 289 0
21 2,3 21AS*TK5 ADS ACCUM AIR RECEIVER TANK I
SC 289 0
21 2,3 TERRY TURBINE 21CS*T1 HEAT 21CS*E1 LUBE OIL COOLER EXCHANGER I
SC 180 0
21 2,3,4 B-33
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions EQUIPMENT 21CS*ED1 DRAIN POT DRAIN I
SC 189 0
0 2,3,4 EQUIPMENT 21CS*ED2 DRAIN POT DRAIN I
SC 178 0
0 2,3,4 MOTOR RCIC LUBE OIL WATER OPERATED 21CS*MOV116 SUPPL VALVE I
SC 188 62 8
2,3,4 RCIC STEAM SUPPLY MOTOR OUTSIDE AUTOMATIC OPERATED 21CS*MOV121 ISOLATION VALVE VALVE I
SC 263 51 8
2,3,4,5 RCIC STEAM SUPPLY MOTOR INSIDE AUTOMATIC OPERATED 21CS*MOV128 ISOLATION VALVE VALVE I
PC 264 37 8
2,3,4,5 ICS SUCTION FROM SUPPRESSION POOL MOTOR OUTSIDE REMOTE MANUAL OPERATED 21CS*MOV136 ISOLATION VALVE VALVE SC 199 53 8
2,3,4,5 PANEL ( LUBE OIL COOLER PRESS CONT VALVE 21CS*PNL115 21CS*PCV115 )
PNL I
ABN 240 71 20 2,3,4 21SC*RAK001A RACK ISC BACKFILL RAK I
SC 309 52 18 2,3 21SC*RAK001B RACK ISC BACKFILL RAK I
SC 293 43 18 2,3 21SC*RAK001C RACK ISC BACKFILL RAK I
SC 293 48 18 2,3 B-34
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 21SC*RAK001D RACK ISC BACKFILL RAK I
SC 293 75 18 2,3 CONTROL ROOM A EMERGENCY LIGHTING 2LAC*PNL100A PANEL PANEL I
CSA 261 AE 2
1,2,3,4,5 CONTROL ROOM B EMERGENCY LIGHTING 2LAC*PNL300B PANEL -600V PANEL I
CSB 261 AG 2
1,2,3,4,5 2LAC*PNLE01 LIGHTING PANEL PNL I
CSA 261 AD 14 0
2LAC*PNLE02 LIGHTING PANEL PNL I
CSB 261 AD 14 0
2LAC*PNLE03 LIGHTING PANEL PNL I
CSH 261 AA 14 0
2LAC*PNLE04 LIGHTING PANEL PNL I
CRR 288 0
14 0
2LAC*PNLE05 LIGHTING PANEL PNL I
CRR 288 0
14 0
2LAC*PNLE06 LIGHTING PANEL PNL I
CCR 306 0
14 0
2LAC*PNLE07 LIGHTING PANEL PNL I
CCR 306 0
14 0
INSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV6A AUTOMATIC VALVE 1
0 0
0 7
2,3,5 INSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV6B AUTOMATIC VALVE 1
0 0
0 7
2,3,5 B-35
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions INSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV6C AUTOMATIC VALVE 1
0 0
0 7
2,3,5 INSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV6D AUTOMATIC VALVE 1
0 0
0 7
2,3,5 OUTSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV7A AUTOMATIC VALVE I
MST 251 0
7 2,3,5 OUTSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV7B AUTOMATIC VALVE I
MST 251 0
7 2,3,5 OUTSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV7C AUTOMATIC VALVE I
MST 251 0
7 2,3,5 OUTSIDE MAIN STEAM ISOLATION VALVE -
AIR OPERATED 2MSS*AOV7D AUTOMATIC VALVE I
MST 251 0
7 2,3,5 PRESSURE 2MSS*PSV120 SAFETY/RELIEF VALVE POWERED VALVE I
PC 297 20 7
2,3 PRESSURE 2MSS*PSV122 SAFETY/RELIEF VALVE POWERED VALVE I
PC 296 21 7
2,3 PRESSURE 2MSS*PSV123 SAFETY/RELIEF VALVE POWERED VALVE I
PC 296 22 7
2,3 B-36
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PRESSURE 2MSS*PSV126 SAFETY/RELIEF VALVE POWERED VALVE I
PC 297 24 7
2,3 PRESSURE 2MSS*PSV127 SAFETY/RELIEF VALVE POWERED VALVE I
PC 297 24 7
2,3 PRESSURE 2MSS*PSV129 SAFETY/RELIEF VALVE POWERED VALVE I
PC 297 24 7
2,3 PRESSURE 2MSS*PSV130 SAFETY/RELIEF VALVE POWERED VALVE I
PC 297 24 7
2,3 PRESSURE 2MSS*PSV134 SAFETY/RELIEF VALVE POWERED VALVE I
PC 297 20 7
2,3 2MSS*PSV137 SAFETY/RELIEF VALVE I
PC 296 23 7
2,3 2MSS*SOV121A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 296 B
8 2,3 2MSS*SOV121B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 296 B
8 2,3 2MSS*SOV126A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV126B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV127A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV127B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV129A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV129B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV130A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV130B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 B-37
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2MSS*SOV134A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV134B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV137A SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 296 B
8 2,3 2MSS*SOV137B SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 296 B
8 2,3 2MSS*SOV221 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 296 B
8 2,3 2MSS*SOV226 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV227 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV229 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV230 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV234 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 297 B
8 2,3 2MSS*SOV237 SAFETY/RELIEF VALVE SOLENOID VALVE I
PC 296 B
8 2,3 RADIATION DETECTOR 2NMP*RE1617D (LPRM) TO LPRM 2 Radiation Element I
PC 300 0
0 5
RADIATION DETECTOR 2NMP*RE2417D (LPRM) TO APRM 2 Radiation Element I
PC 300 0
0 5
RADIATION DETECTOR 2NMP*RE4025C (LPRM) TO LPRM 2 Radiation Element I
PC 300 0
0 5
SCRAM DISCHARGE VOLUME DRAIN -
AIR OPERATED 2RDS*AOV123 AUTOMATIC VALVE I
SC 240 59 7
1 B-38
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions SCRAM DISCHARGE VOLUME VENT -
AIR OPERATED 2RDS*AOV132 AUTOMATIC VALVE I
SC 283 74 7
1 ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV1 56 VALVE SOLENOID VALVE I
SC 261 75 8
ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV1 57 VALVE SOLENOID VALVE I
SC 261 75 8
ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV1 59 VALVE SOLENOID VALVE I
SC 261 75 8
ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV160 VALVE SOLENOID VALVE I
SC 261 75 8
ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV161 VALVE SOLENOID VALVE I
SC 261 75 8
B-39
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV162 VALVE SOLENOID VALVE I
SC 261 75 8
1 ALTERNATE ROD INSERTION VALVE, SOLENOID OPERATED 2RDS*SOV163 VALVE SOLENOID VALVE I
SC 261 75 8
1 CHECK VALVE SWP to RHR AIR OPERATED 2RHS*AOV150 x-connect VALVE I
ABS 181 99 7
3,4,5 HEAT EXCHANGER G.E.
HEAT 2RHS*E1B DESIGNATOR E12-B001B EXCHANGER I
ABS 198 116 21 3,4,5 RHR LOOP A TEST RETURN 2RHS*FV38B TO SUPPR POOL COOLING FLOW VALVE I
SC 218 B
8 0
RHR LOOP C TEST FLOW 2RHS*FV38C RETURN TO SUPPR POOL FLOW VALVE I
SC 218 B
8 0
SHUTDOWN COOLING SUPPLY OUTSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2RHS*MOV113 VALVE VALVE SC 247 B
8 3,4,5 RHR SERVICE WTR CROSS MOTOR TIE, MOTOR OPERATED OPERATED 2RHS*MOV116 GATE VALVE.
VALVE I
ABS 181 W
8 3,4,5 B-40
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MOTOR OPERATED 2RHS*MOV12B RHR HTX Discharge MOV VALVE I
ABS 177 W
8 3,4,5 CONTAINMENT SPRAY TO DRYWELL OUTSIDE MOTOR REMOTE MANUAL OPERATED 2RHS*MOV15B ISOLATION VALVE VALVE SC 292 B
8 5
RHS PMP P1 B SUCTION MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV1B ISOLATION VALVE VALVE I
SC 195 B
8 3,4,5 RHS PUMP P1C SUCTION MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV1C ISOLATION VALVE VALVE I
SC 195 B
8 3,5 RHS / LPCI TO RPV MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV24A ISOLATION VALVE VALVE I
SC 295 B
8 3,4,5 RHS / LPCI TO RPV MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV24B ISOLATION VALVE VALVE I
SC 292 B
8 3,4,5 RHS / LPCI TO RPV MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV24C ISOLATION VALVE VALVE I
SC 295 B
8 3,5 B-41
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions CONTAINMENT SPRAY TO DRYWELL OUTSIDE MOTOR REMOTE MANUAL OPERATED 2RHS*MOV25A ISOLATION VALVE VALVE SC 294 B
8 3,4,5 CONTAINMENT SPRAY TO DRYWELL OUTSIDE MOTOR REMOTE MANUAL OPERATED 2RHS*MOV25B ISOLATION VALVE VALVE SC 292 B
8 3,4,5 RHR A SHUT DOWN MOTOR COOLING SUCTION, OPERATED 2RHS*MOV2A MOTOR OPERATED VALVE VALVE I
ABN 183 E
8 3,4,5 RHR B SHT DN COOLING MOTOR SUCT, MOTOR OPERATED OPERATED 2RHS*MOV2B VALVE VALVE I
SC 197 B
8 3,4,5 RHS TEST LINE TO SUPPRESSION POOL MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV30A ISOLATION VALVE VALVE SC 206 B
8 5
RHS TEST LINE TO SUPPRESSION POOL MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV30B ISOLATION VALVE VALVE SC 206 B
8 5
RHS CONTAINMENT SPRAY MOTOR OUTSIDE AUTOMATIC OPERATED 2RHS*MOV33A ISOLATION VALVE VALVE I
SC 229 B
8 5
B-42
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-I1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions RHS CONTAINMENT SPRAY MOTOR OUTSIDE AUTOMATIC OPERATED 2RHS*MOV33B ISOLATION VALVE VALVE SC 229 B
8 5
SHUTDOWN COOLING RETURN OUTSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2RHS*MOV40A VALVE VALVE I
SC 250 B
8 3,4,5 SHUTDOWN COOLING RETURN OUTSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2RHS*MOV40B VALVE VALVE SC 249 B
8 3,4,5 MOTOR RHR B MIN FLOW BYPASS, OPERATED 2RHS*MOV4B MOTOR OPERATED VALVE VALVE I
ABS 184 W
8 3,4,5 MOTOR RHR C MIN FLOW BYPASS, OPERATED 2RHS*MOV4C MOTOR OPERATED VALVE VALVE I
ABS 184 E
8 3
RHR H.E. E1B INLET MOTOR BYPASS MOTOR OPERATED 2RHS*MOV8B OPERATED VALVE VALVE I
ABS 184 W
8 3,4,5 MOTOR RHR H.E. B SHELL-SIDE INL OPERATED 2RHS*MOV9B MOTOR OPERATED VALVE VALVE I
ABS 201 W
8 3,4,5 B-43
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions INCLUDES ALL ASSOCIATED RHR PUMPS, PUMPS, AUX, BWR, RHR PUMPS MOTORS, ELEC VERT MTD) ELECTRIC MOTORS & GENERAL G.E.
2RHS*P1B DESIGNATOR E12-C002B PUMP I
ABS 175 W
6 3,4,5 INCLUDES ALL ASSOCIATED RHR PUMPS, PUMPS, AUX, BWR, RHR PUMPS MOTORS, ELEC VERT MTD), ELECTRIC.
2RHS*P1C MOTORS & GENERAL PUMP I
ABS 175 E
6 3
2RHS*P2 RHS SYSTEM PRESS PUMP PUMP I
ABS 175 E
5 3,4,5 RHR STM VALVE CONTROL 2RHS*PNL100 PNL PNL I
SC 215 X
20 3,4,5 2RMC-PNLZ1
-X-ROD SELECT MODULE PNL I
CCR 306 0
20 0
NORMAL AC LOW VOLTAGE 2RPM*PNLA100 DISTRIBUTION PANEL PNL I
CTR 237 AG 14 0
NORMAL AC LOW VOLTAGE 2RPM*PNLB100 DISTRIBUTION PNL PNL I
CTR 237 AG 14 0
120/240V AC FUSE DIST 2SCM*PNL101A PNL PNL I
CRR 288 AE 14 1,2,3,4,5 2SCM*PNL102A 120/240V DIST PANEL PNL I
CRR 288 AD 14 1,2,3,4,5 B-44
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 120/240V AC FUSE DIST 2SCM*PNL104A PNL PNL I
CRR 288 AE 14 1,2,3,4,5 120/240V AC FUSE DIST 2SCM*PNL105A PNL PNL I
CRR 288 AE 14 1,2,3,4,5 120/240V AC FUSE DIST 2SCM*PNL301B PNL PNL I
CRR 288 AG 14 1,2,3,4,5 120/240V AC FUSE DIST 2SCM*PNL302B PNL PNL I
CRR 288 AG 14 1,2,3,4,5 2SCM*PNL303B 120/240V AC DIST PNL PNL I
CRR 288 AG 14 1,2,3,4,5 120/240V AC FUSE DIST 2SCM*PNL304B PNL PNL I
CRR 288 AG 14 1,2,3,4,5 120/240V AC FUSE DIST 2SCM*PNL305B PNL PNL I
CRR 288 AE 14 1,2,3,4,5 MISC 120/240V 2SCV*PNL101A DISTRIBUTION PANEL PNL I
ABN 240 W
14 1,2,3,4,5 HPCS 120V MISC DIST 2SCV*PNL200P PANEL PNL I
CSH 261 AA 2
3 MISC 120/240 VAC 2SCV*PNL301B DISTRIBUTION PANEL PNL I
ABS 240 W
14 1,2,3,4,5 GLOBE VALVE MOTOR MOTOR OPERATED SLC SUCTION OPERATED 2SLS*MOV1A TO 2SLS*P1A VALVE SC 290 B
8 1
B-45
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions GLOBE VALVE MOTOR MOTOR OPERATED SLS SUCTION OPERATED 2SLS*MOV1B TO 2SLS*P1B VALVE I
SC 290 B
8 1
SLS TO RPV OUTSIDE MOTOR REMOTE MANUAL OPERATED 2SLS*MOV5A ISOLATION VALVE VALVE I
SC 295 46 8
1 SLS TO RPV OUTSIDE MOTOR REMOTE MANUAL OPERATED 2SLS*MOV5B ISOLATION VALVE VALVE I
SC 295 47 8
1 STANDBY LIQUID CONTROL 2SLS*P1B PUMP 1B PUMP I
SC 289 B
5 1
VALVE -
2SLS*VEX3B SLS EXPLOSIVE VALVE EXPLOSIVE I
SC 296 B
8 1
SWP Alternate cooling to RHR AIR OPERATED 2SWP*AOV20A Pump VALVE I
ABN 183 96 7
3,4 SWP Alternate cooling to RHR AIR OPERATED 2SWP*AOV20B Pump VALVE I
ABS 179 93 7
3,4 SWP Alternate cooling to RHR AIR OPERATED 2SWP*AOV22B Pump VALVE I
ABS 177 95 7
3,4 2SWP*CAB146A SCRV WTR EFF A CABINET CAB I
SVP 245 AK 20 0
SCRV WTR EFF B 2SWP*CAB146B CABINNET CAB I
SVP 245 AK 20 0
B-46
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions RADIATION MONITOR-2SWP*CAB23A SERVICE WTR SYSTEM CAB I
ET 215 99 20 0
2SWP*CAB23B RHR SERV WTR B CAB I
ET 215 99 20 0
FLOW CONTROL VALVE 2SWP*FV47A SWP TO CIRC WATER ISOL FLOW VALVE I
SVP 245 AK 7
0 FLOW CONTROL VALVE 2SWP*FV47B FOR SWP FLOW VALVE I
SVP 254 AK 7
0 FLOW CONTROL VALVE FOR SWP A HEADER 2SWP*FV54A PRESS FLOW VALVE I
0 FLOW CONTROL VALVE FOR SWP B HEADER 2SWP*FV54B PRESS FLOW VALVE I
SVP 255 AK 7
0 MOTOR GATE VALVE - MOTOR OPERATED 2SWP*MOV15B OPERATED TO UC403B VALVE I
SC 197 B
8 3
MOTOR MTR OPER BUTTERFLY OPERATED 2SWP*MOV19B VALVE VALVE I
ABN 219 99 8
3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV33B MOTOR OPER VALVE I
ABS 181 W
8 3,4,5 B-47
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV3B MOTOR OPER VALVE I
SW 265 K
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV50B MOTOR OPER VALVE I
SW 264 L
8 1,2,3,4,5 MOTOR MOTOR OPERATED VALVE, OPERATED 2SWP*MOV66B SWP FR CLR 2EGS*EG3 VALVE I
DG 269 A
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV74A MOTOR OPERATED VALVE VALVE I
SW 265 K
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV74B MOTOR OPERATED VALVE VALVE I
SW 263 L
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV74C MOTOR OPERATED VALVE VALVE I
SW 264 K
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV74D MOTOR OPERATED VALVE VALVE I
SW 264 L
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV74E MOTOR OPERATED VALVE VALVE I
SW 264 K
8 1,2,3,4,5 B-48
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV74F MOTOR VALVE I
SW 265 L
8 1,2,3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV90B MOTOR OPER VALVE I
ABS 181 W
8 3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV93A Reactor building loads return VALVE I
3,4,5 MOTOR BUTTERFLY VALVE -
OPERATED 2SWP*MOV93B Reactor building loads return VALVE I
PT 247 AK 8
3,4,5 MOTOR SWP FR CLR 2EGS*EG2-OPERATED 2SWP*MOV94A MOTOR OPERATED VALVE VALVE I
DG 271 A
8 3
MOTOR SWP FR CLR 2EGS*EG2-OPERATED 2SWP*MOV94B MOTOR OPERATED VALVE VALVE I
DG 269 A
8 3
MOTOR SWP TO CLR 2EGS*EG2-OPERATED 2SWP*MOV95A MOTOR OPERATED VALVE VALVE I
DG 263 A
8 3
MOTOR MOTOR OPER VALVE SWP OPERATED 2SWP*MOV95B TO CLR 2EGS*EG2 VALVE I
DG 263 A
8 3
B-49
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2SWP*P1B SERVICE WATER PUMP PUMP I
SW 224 L
5 1,2,3,4,5 2SWP*P1C SERVICE WATER PUMP PUMP I
SW 224 K
5 1,2,3,4,5 2SWP*P1D SERVICE WATER PUMP PUMP I
SW 224 M
5 1,2,3,4,5 2SWP*P1 E SERVICE WATER PUMP PUMP I
SW 224 K
5 1,2,3,4,5 2SWP*P1F SERVICE WATER PUMP PUMP I
SW 224 L
5 1,2,3,4,5 2SWP*TV35A CONTROLLER 2SWP*PNL35A PNL PNL I
CCL 261 AA 20 0
2SWP*TV35B CONTROLLER 2SWP*PNL35B PNL PNL I
CCL 261 AA 20 0
SELF CLEAN STRAINER STRAINER -
2SWP*STR4B AND MOTOR PERMANENT I
SW 261 L
0 1,2,3,4,5 SELF CLEAN STRAINER STRAINER -
2SWP*STR4C AND MOTOR PERMANENT I
SW 261 K
0 1,2,3,4,5 SELF CLEAN STRAINER STRAINER -
2SWP*STR4D AND MOTOR PERMANENT I
SW 261 M
0 1,2,3,4,5 SELF CLEAN STRAINER STRAINER -
2SWP*STR4E AND MOTOR PERMANENT I
SW 261 K
0 1,2,3,4,5 SELF CLEAN STRAINER STRAINER -
2SWP*STR4F AND MOTOR PERMANENT I
SW 261 L
0 1,2,3,4,5 B-50
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions UNINTERRUPTABLE PWR SUPP INCLUDING REG UNINTERRUPTAB TRANSFORMER & MANUAL LE POWER 2VBA*UPS2B BYPASS SWITCH SUPPLY CSB 261 AD 16 1,2,3,4,5 UNINTERRUPTAB RECTIFIER/INVERTER/STAT LE POWER 2VBA*UPS2D IC SWITCH SUPPLY CB 237 AD 16 1,2,3,4,5 MAINTENANCE TRANSFORMER 2VBA*XD2C TRANSFORMER, UPS DISTRIBUTION I
CB 237 AD 4
1,2,3,4,5 MAINTENANCE TRANSFORMER 2VBA*XD2D TRANSFORMERUPS DISTRIBUTION I
CB 237 AD 4
1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNL102A 2VBA*UPS2A)
PANEL CTR 288 AE 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNL301B 2VBA*UPS2B)
PANEL CTR 288 AE 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNL302B 2VBA*UPS2B)
PANEL CTR 288 AE 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBB-2VBS*PNLA100 UPS3A)
PNL CB 237 AG 14 1,2,3,4,5 B-51
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PANEL (120 VAC POWER DISTRIBUTION FORM 2VBS*PNLA103 2VBS*PNLA100)
PNL I
CTR 306 AG 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNLA104 2VBS*PNLA100)
PNL I
CTR 306 AG 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNLA105 2VBS*PNLA100)
PNL I
ABN 240 W
14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNLA106 2VBS*PNLA100)
PNL I
ABS 240 W
14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION TO 2VBS*PNLA110 2CEC*PNL709)
PNL I
CB 237 AE 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBB-2VBS*PNLB100 UPS3B)
PNL I
CB 237 AD 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNLB103 2VBS*PNLB100)
PNL I
CTR 306 AG 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNLB104 2VBS*PNLB100)
PNL I
CTR 306 AG 14 1,2,3,4,5 B-52
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PANEL (120 VAC POWER DISTRIBUTION FORM 2VBS*PNLB105 2VBS*PNLB100)
PNL I
ABN 240 W
14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM 2VBS*PNLB106 2VBS*PNLB100)
PNL I
ABS 240 W
14 1,2,3,4,5 PANEL (DISTRIBUTION OF 120 VAC POWER SUPPLIED 2VBS*PNLB110 FROM 2VBS*PNLB100)
PNL CB 237 AG 14 1,2,3,4,5 OVER PRESSURIZATION VENT PANEL (NON-2VNT*PNL1 ELECTRICAL EQUIPMENT)
PNL SC 196 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL2A ELECTRICAL EQUIPMNT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL2B ELECTRICAL EQUIPMT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL2C ELECTRICAL EQUIPMENT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL2D ELECTRICAL EQUIPMENT)
PNL I
MST 309 0
0 0
B-53
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL3A ELECTRICAL EQUIPMENT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL3B ELECTRICAL EQUIPMENT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL3C ELECTRICAL EQUIPMNT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL3D ELECTRICAL EQUIPMENT)
PNL I
MST 309 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL4A ELECTRICAL EQUIPMNT)
PNL I
SC 196 0
0 0
OVERPRESSURIZATION VENT PANEL (NON-2VNT*PNL4B ELECTRICAL EQUIPMENT)
PNL I
SC 196 0
0 0
WCS SUPPLY FROM RCS AND RPV INSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2WCS*MOV1 02 VALVE VALVE PC 245 40 8
5 B-54
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions WCS SUPPLY FROM RCS AND RPV OUTSIDE MOTOR AUTOMATIC ISOLATION OPERATED 2WCS*MOV1 12 VALVE VALVE I
SC 245 B
8 5
CCR 306 0
20 0
MOV-100-54 0
0 0
0 8
0 Z1A-2SLSA01 METER RELAY PANEL PNL I
CCR 306 0
20 0
Z1B-2SLSB01 METER RELAY PANEL PNL I
CCR 306 0
20 0
RADIATION DETECTOR 2NMP*RE3217D (LPRM) TO LPRM 1 PC 300 0
0 0
5 SELF CLEAN STRAINER STRAINER -
2SWP*STR4A AND MOTOR PERMANENT SW 261 K
9 0
1,2,3,4,5 MOTOR CONTROL 2EHS*MCC101 EMER MCC 101 CENTER SW 261 K
9.7 1
1,2,3,4,5 MOTOR CONTROL 2EHS*MCC102 EMER MCC 102 CENTER ABN 240 W
0 1
1,2,3,4,5 2EJS*PNL104A 600V EMERGENCY PANEL ABN 240 W
32 2
1,2,3,4,5 600V U.S EMERGENCY UNIT 2EJS*US1 SWITCHGEAR SUBSTATION CSA 261 AG 11.1 2
1,2,3,4,5 2ENS*SWG101 4160 EMER SWGR 101 SWITCHGEAR CSA 261 AD 11.5 3
1,2,3,4,5 B-55
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions 2EJS*X2 4160/600V HPCS XFMR TRANSFORMER CSH 261 AA 13 4
1,2,3,4,5 2CSH*P1 H.P.C.S. PUMP PUMP SC 178 W
12.5 6
3 RCIC PUMP; TURBINE PUMP 21CS*P1 SHAFT DRIVEN SC 175 B
9 5
2,3,4 STANDBY LIQUID CONTROL PUMP 2SLS*P1A PUMP PlA SC 289 B
8.3 5
1 2SWP*P1A SERVICE WATER PUMP PUMP SW 224 K
8.8 5
1,2,3,4,5 2EGF*P1A FUEL OIL TRANSFER PUMP PUMP DG 261 A
11.2 6
1,2,3,4,5 INCLUDES ALL ASSOCIATED RHR PUMPS, AUX, BWR, ELEC (VERT PUMP MTD) ELECTRIC MOTORS, GENERAL G.E.
2RHS*P1A DESIGNATOR E12-CO02A ABN 175 E
13.4 6
3,4,5 CCP AOV to Seal Cooler for RHR Pump, Fails Closed to AIR OPERATED allow SWP to provide cooling VALVE 2CCP*AOV37A to RHR Pump.
ABN 183 94 91 7
3,4,5 2CPS-FN1 PURGE INLET TO DRYWELL OUTSIDE AIR OPERATED AUTOMATIC ISOLATION VALVE 2CPS*AOV1 04 VALVE SC 294 44 133 7
5 B-56
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions PURGE EXHAUST FROM DRYWELL INSIDE AIR OPERATED AUTOMATIC ISOLATION VALVE 2CPS*AOV1 08 VALVE PC 299 32 337 7
5 PURGE EXHAUST FROM SUPPRESSION CHAMBER AIR OPERATED OUTSIDE AUTOMATIC VALVE 2CPS*AOV1 11 ISOLATION VALVE SC 222 53 330 7
5 PRIMARY CONTAINMENT AIR OPERATED 2GTS*AOV101 PURGE ISOLATION VALVE VALVE SC 319 0
42 7
5 BUTTERFLY OR AIR OPERATED 2GTS*AOV2A TRICENTRIC V VALVE SG 266 E
33.7 7
5 PRESSURE LUBE OIL CLR PRESS CONT CONTROL VALVE 21CS*PCV115 V
- SELF ACTUATED SC 186 60 167 7
2,3,4 PRESSURE 2MSS*PSV121 SAFETY/RELIEF VALVE POWERED VALVE PC 296 20 30 7
2,3 SCRAM DISCHARGE AIR OPERATED VOLUME VENT-VALVES 2RDS*AOV124 AUTOMATIC SC 283 82 21 7
1 SCRAM DISCHARGE AIR OPERATED VOLUME DRAIN-VALVES 2RDS*AOV130 AUTOMATIC SC 240 81 198 7
1 B-57
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions SWP Alternate cooling to RHR AIR OPERATED 2SWP*AOV22A Pump VALVE ABN 186 99 92 7
3,4 MOTOR HPCS Pump suction isolation OPERATED 2CSH*MOV101 for CST "B" (PID 33B @ D9)
VALVE SC 177 71 243 8
3 HPCS MIN FLOW BYPASS OUTSIDE REMOTE MANUAL OTOR OPERATED ISOLATION VALVE (PID 33B VALVE 2CSH*MOV1 05
@ G5)
SC 218 74 3,5 CSH TO RPV OUTSIDE MOTOR REMOTE MANUAL OPERATED 2CSH*MOV107 ISOLATION VALVE VALVE SC 292 39 215 8
3,5 CSH SUCTION FROM SP MOTOR OUTSIDE REMOTE MANUAL OPERATED 2CSH*MOV1 18 ISOLATION VALVE VALVE SC 195 36 220 8
3 CSL TO RPV OUTSIDE MOTOR REMOTE MANUAL OPERATED ISOLATION VALVE (PID VALVE 2CSL*MOV104 032A @ H3)
SC 295 B
7.3 3,5 CSL SUCTION FROM SP OUTSIDE REMOTE MANUAL OTOR OPERATED ISOLATION VALVE (PID VALVE 2CSL*MOV1 12 032A @ G9)
SC 195 B
4.7 83,5 B-5 8
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions DFR DRAIN TANK LINE MOTOR OUTSIDE AUTOMATIC OPERATED ISOLATION VALVE (PID 63E VALVE 2DFR*MOV120
@ E7)
SC 218 53 25 8
5 ADS HEADER A N2 SUPPLY OUTSIDE AUTOMATIC ISOLATION VALVE (PID 19D 21AS*SOV164
@ C10)
SC 294 43 58 8
2,3,5 ADS HEADER A PRESSURESOLENOID SOLENOID VALVE OPERATED VALVE (PID 19D AUXILIARY 21AS*SOVX181
@ J3)
SC 294 47 59 8
2,3 MOTOR RCIC STEAM SUPPLY OPERATED 21CS*MOV120 VALVE TO TURB VALVE SC 188 53 170 8
2,3,4 ICS TO RPV OUTSIDE MOTOR REMOTE MANUAL OPERATED 21CS*MOV126 ISOLATION VALVE VALVE SC 292 50 167 8
2,3,4,5 MOTOR OPERATED VALVE MOTOR FOR PUMP SUCT FROM OPERATED 21CS*MOV129 CNDS STORAGE TANK VALVE ABN 242 84 60 8
2,3,4 21CS*T1 TURB THROT MOTOR MOTOR OPERATED VALVE; OPERATED 21CS*MOV150 SUPPLIED W/EQP 21CS*T1 VALVE SC 184 57 160 8
2,3,4 B-59
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions DUAL SOLENOID OPERATED VALVE (3-WAY REDUNDANT SCRAM PILOT SOV VALVE ON 2RDS*SOV139 2RDS*HCU0219)
SC 261 0
0 8
1 ALTERNATE ROD INSERTION VALVE, SOLENOID VALVE SOLENOID OPERATED 2RDS*SOV158 VALVE SC 261 75 20 8
1 RHR LOOP A TEST RETURN TO SUPPR POOL COOLING FLOW VALVE 2RHS*FV38A (PID 31C @ B6)
SC 206 72 90 8
0 SHUTDOWN COOLING MOTOR SUPPLY INSIDE OPERATED AUTOMATIC ISOLATION VALVE 2RHS*MOV112 VALVE PC 256 26 171 8
3,4,5 RHR SERVICE WATER MOTOR CROSS TIE, MOTOR OPERATED 2RHS*MOV1 15 OPERATED GATE VALVE.
VALVE ABS 181 W
37 8
3,4,5 MOTOR "A" RHR HEAT EXCHANGER OPERATED 2RHS*MOV12A DISCHARGE VALVE VALVE ABN 181 E
37 8
3,4,5 B-60
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions CONTAINMENT SPRAY TO DRYWELL OUTSIDE OTOR REMOTE MANUAL OATE 2RHS*MOV15A ISOLATION VALVE SC 294 B
6 8
5 RHS PUMP PlA SUCTION MOTOR OUTSIDE REMOTE MANUAL OPERATED 2RHS*MOV1A ISOLATION VALVE VALVE SC 195 B
5.1 8
3,4,5 MOTOR RHR B MIN FLOW BYPASS, OPERATED 2RHS*MOV4B MOTOR OPERATED VALVE VALVE ABS 184 W
9 8
3,4,5 RHR H.E. ElA INLET MOTOR BYPASS MOTOR OPERATED 2RHS*MOV8A OPERATED VALVE VALVE ABN 181 E
38 8
3,4,5 RHR H.E. A SHELL SIDE INL MOTOR MOTOR OPERATED OPERATED 2RHS*MOV9A BUTTERFLY VALVE VALVE ABN 201 W
46 8
3,4,5 VALVE -
2SLS*VEX3A SLS EXPLOSIVE VALVE EXPLOSIVE SC 296 B
8.5 8
1 MOTOR OPERATED GATE MOTOR VALVE TO 2HVR*UC403A OPERATED (HPCS Pump Room Unit VALVE 2SWP*MOV15A Cooler)
SC 197 B
11.4 8
3 B-61
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions MOTOR Isolation to Reactor Building OPERATED 2SWP*MOV19A Balance of Plant Loads VALVE ABN 219 W
29 8
3,4,5 MOTOR SWP TO RHR HTX OUTLET OPERATED 2SWP*MOV33A VALVE VALVE ABN 181 E
36 8
3,4,5 MOTOR Isolation to Turbine Building OPERATED 2SWP*MOV3A Balance of Plant Loads VALVE SW 265 K
9.3 8
1,2,3,4,5 MOTOR Divisional Cross tie isolation OPERATED 2SWP*MOV50A valve VALVE SW 265 L
9.3 8
1,2,3,4,5
.MOTOR Turbine building BOP header OPERATED 2SWP*MOV599 return VALVE PT 255 AM 2.6 8
3,4,5 MOTOR SWP FR CLR 2EGS*EG1-OPERATED 2SWP*MOV66A MOTOR OPERATED VALVE VALVE DG 271 A
11 8
1,2,3,4,5 MOTOR SWP TO RHR HTX INLET OPERATED 2SWP*MOV90A VALVE VALVE ABN 180 E
48 8
3,4,5 2HVR*UC401F RHR PUMP RM B-UNIT CLR UNIT COOLER ABS 177 W
20 10 3,4,5 2HVR*UC403A HPCS PUMP RM UNIT CLR UNIT COOLER SC 176 B
11.8 10 3
B-62
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions CB 120/240V HEATER N
2EJA*PNL101A PANEL CSA 261 AG 11.5 14 1,2,3,4,5 SWGR RM A EMERGENCY PAE 2EJS*PNL100A 600V PANEL CSA 261 AG 11.5 14 1,2,3,4,5 120/240V AC DIST PNL (EE-PNL 2SCM*PNL103A 011A)
CRR 288 AD 10.5 14 1,2,3,4,5 PANEL (120 VAC POWER DISTRIBUTION FROM PANEL 2VBS*PNL101A 2VBA*UPS2A)
CTR 288 AE 10.5 14 1,2,3,4,5 2BYS*BAT2A 125V DC BAT.2A DIV I BATTERY CBR 261 AE 11.9 15 1,2,3,4,5 UNINTERRUPTIBLE PWR UNINTERRUPTAB SUPP INCLUDING REG LE POWER 2VBA*UPS2A TRPANSFOMRMNA SUPPLY CSA 261 AD 11.9 16 1,2,3,4,5 UNINTERRUPTAB RECTIFIER / INVERTER /
LE POWER 2VBA*UPS2C STATIC SWITCH SUPPLY CB 237 AD 12 16 1,2,3,4,5 STANDBY DIESEL ENGINE 2EGS*EG1 GENERATOR GENERATOR DG 261 AA 10.5 17 1,2,3,4,5 RACK (RRS/CSL RAK 2CES*RAK004 INSTRUMENTATION)
SC 261 52 82 18 1,3 RACK (MAIN STEAM FLOW RAK 2CES*RAK015 A INSTRUMENTATION)
SC 215 57 343 18 2
B-63
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions RACK (ICS RAK 2CES*RAK017 INSTRUMENTATION)
SC 175 79 135 18 2,3,4 RACK (CSH RAK 2CES*RAK024 INSTRUMENTATION RACK)
SC 175 80 205 18 3
RACK (RV LEVEL/PRESS INSTRUMENTATION/RACKC RAK 2CES*RAK026
)
SC 261 71 291 18 1,2,3,4 RACK (RCIC 2CES*RAK029 INSTRUMENTATION)
RAK SC 175 55 213 18 2,3,4 RACK (SRM/IRM PRE-AMP 2CES*RAK030 INSTRUMENTATION)
SC 240 64 270 18 1
100 OHM @ ODEG C PLATINUM RESISTANCE Temperature TEMP DETECTOR, Element MONITORS DRYWELL 2CMS*TE120 TEMPERATURE PC 253 41 167 19 5
INDICATING TEMPERATURE Temperature SWITCH, 2EGS*G1 CONT Indication Switch 2HVP*TIS13A RM TEMP DG 265 AA 10.2 19 1,2,3,4,5 INBOARD VALVE RELAY PNL 2CEC*PNL622 PANEL CCR 306 AH 12 20 5
BOP INSTRUMENT PNL PNL 2CEC*PNL828 DIV1 CRR 288 AJ 11 20 3,4,5 B-64
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions DIV I AUXILIARY RELAY PNL 2CEC*PNL859 PANEL CRR 288 AE 11 20 1,2,3,4,5 DIV 1 SUPPRESSION POOL 2CEC*PNL894 TEMP MONITORING PANEL CRR 288 AE 11 20 3,4,5 BOP INSTRUMENT PANEL N
2CEC*PNL896 DIV 1 CRR 288 AJ 11 20 2,3,4 2EGS*G1 CONTROL PANEL (ECPA CONTROL VOLTAGE PNL 2CES*IPNL406 125 VDC)
DG 261 AA 10.2 20 1,2,3,4,5 2EGS*EG1 CONTROL PANEL (EGPA/CONTROL PNL 2CES*IPNL407 VOLTAGE 125 VDC)
DG 261 AA 11 20 1,2,3,4,5 REMOTE SHUTDOWN PNL 2CES*PNL405 CONTROL PANEL C1 261 AC 12 20 1,2,3,4,5 SERVICE WATER STRAINERS CONTROL PNL 2CES*PNL504 PANEL SA 261 K
9 20 3,4,5 2EGA*TK1A COMP AIR RECEIVER TANK Tank DG 261 0
0 21 1,2,3,4,5 STDBY DIESEL GEN 2EGS*EG1 FUEL OIL DAY Tank 2EGF*TK3A TANK 660 GAL.
DG 275 0
0 21 1,2,3,4,5 21AS*TK34 ADS VALVE ACCUMULATOR TANK PC 289 0
0 21 2,3 21AS*TK4 ADS ACCUM AIR RECEIVER TANK SC 289 0
0 21 2,3 B-65
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit-2 Base SWEL-1 List 2.3 5 Safety Component ID Component Description Component Type Building Elevation Column Row Class Functions HEAT 2RHS*E1A HEAT EXCHANGER EXCHANGER ABN 198 0
0 21 3,4,5 STORAGE TANK FOR STANDBY LIQUID CONTROL TANK 2SLS*TK1 SYSTEM SC 289 0
0 21 1
2BYS*SWG002A 125VDC SWITCHGEAR SWITCHGEAR CSA 261 AG 11 14 1,2,3,4,5 2DMS*MCCA1 125VDC MCC MCC ABN 240 99 73 1
1,2,3,4,5 2BYS*PNL204A 125VDC DIST PNL PNL DG 261 AA 10.3 14 1,2,3,4,5 125 VDC HPCS DIESEL GENERATOR PNL 2CES*IPNL414 DISTRIBUTION PANEL DG 261 AA 13 14 3
MOTOR MOTOR OPERATED OPERATED 2HVP*MOD1C DAMPER DAMPER DG 279 AA 10.5 8
1,2,3,4,5 MOTOR MOTOR OPERATED OPERATED 2HVP*MOD6C DMAPER DAMPER DG 280 AA 11 8
1,2,3,4,5 CONTROL BUILDING 2HVK*CHL1A CHILLED WATER CHILLER.
CCL 261 AA 10.8 11 1,2,3,4,5 B-66
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC*AOV153 FILTER HDR INL ISOL VCH Sc 298 47 277 2SFC*AOV154 FILTER HDR INL ISOL VCH SC 298 45 277 2SFC*AOV19A 2SFC-FLT1A OUTLET, AIR OPERATED VALVE Sc 336 33 25 2SFC*AOV33A SKIMMER SURGE TANK LEVEL AIR OPERATED VALVE RB 351 37 60 2SFC*AOV19B 2SFC-FLT1B OUTLET SC 310 36 240 2SFC*AOV33B SKIMMER SURGE TANK LEVEL AIR OPERATED VALVE RB 351 29 122 2SFC-AOV11 A 2SFC-FLT1A, SOLENOID OPERATED VALVE SC 332 33 2
2SFC-AOV1 1 B 2SFC-FLT1 B INLET VALVE, AIR OPERATED VALVE SC 332 35 345 2SFC-AOV12A 2SFC-FLT1A, AIR OPERATED VALVE SC 330 42 359 2SFC-AOV12B 2SFC-FLT1B, AIR OPERATED VALVE Sc 330 43 348 2SFC-AOV13A 2SFC-FLT1A, AIR OPERATED VALVE Sc 328 34 11 2SFC-AOV13B 2SFC-FLT1 B, AIR OPERATED VALVE.
SC 328 36 338 2SFC-AOV134 2SFC-TK3 RESIN OUT VALVE, AIR OPERATED VALVE SC 335 50 327 B-67
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINEIRAD COL/AZ ID (X)
(Y) 2SFC-AOV39A 2SFC-FLT1A, AIR OPERATED VALVE SC 328 35 15 2SFC-AOV39B 2SFC-FLT1 B, AIR OPERATED VALVE SC 328 38 332 2SFC-AOV40A 2SFC-FLT1A, AIR OPERATED VALVE Sc 334 33 13 2SFC-AOV40B 2SFC-FLT1B, AIR OPERATED VALVE Sc 334 35 337 2SFC-AOV41A 2SFC-FLT1A, AIR OPERATED VALVE SC 342 36 23 2SFC-AOV41B 2SFC-FLT1B, AIR OPERATED VALVE SC 328 39 327 2SFC-AOV42A 2SFC-FLT1A, AIR OPERATED VALVE SC 342 33 342 2SFC-AOV42B 2SFC-FLT1B, AIR OPERATED VALVE Sc 342 34 342 2SFC-AOV43A 2SFC-FLT1A, AIR OPERATED VALVE SC 335 40 335 2SFC-AOV43B 2SFC-FLT1B, AIR OPERATED VALVE SC 335 43 335 2SFC-AOV44A 2SFC-FLT1A, AIR OPERATED VALVE SC 336 37 359 2SFC-AOV44B 2SFC-FLT1B, AIR OPERATED VALVE SC 336 38 347 2SFC-AOV109 2" AIR OPERATED VALVE FOR STR5 BLOW-DOWN SC 332 2SFC-CE146 SFC POOL CNDT Sc 298 B
15 B-68
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-CE46A CONDUCTIVITY ELEMENT 2SFC-F1A OUT CNDT Sc 337 30 355 2SFC-CE46B CONDUCTIVITY ELEMENT 2SFC-F1 B OUT CNDT SC 337 31 350 2SFC*E1A SPENT FUEL POOL HT EXCHGR SC 221 2SFC*E1B SPENT FUEL POOL COOLING SC 221 2SFC-E/1124 ELECTRONIC E/I CONVERTER CRR 288 AJ 11 2SFC-EDU1 EDUCTOR SC 336 2SFC-FCV1 32 SFC CNDS SUPPLY CONT, FLOW CONTROL VALVE SC 328 30 350 2SFC*FE36A FLOW ELEMENT, SF POOL CLG SYS FLOW L SC 232 64 90 2SFC*FE58A FLOW ELEMENT SFC PMP DISCH FLOW SC 302 52 289 2SFC-FE104 FLOW ELEMENT FOR SFC FLOW TO LWS OF CONDENSER CONN SC 228 69 82 130C; ORIFICE PLATE TYPE 2SFC*FE36B FLOW ELEMENT, SF POOL CLG SYS FLOW L SC 225 65 195 2SFC*FE58B FLOW ELEMENT, SFC PMP DISCH FLOW SC 302 49 265 2SFC-FE47A FLOW ELEMENT FOR 2SFC-FLT1A OUT FLOW; ORIFICE PLATE SC 342 30 1
TYPE B-69
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-FE47B FLOW ELEMENT FOR 2SFC-FLT1 B OUT FLOW; ORIFICE PLATE SC 342 32 353 TYPE 2SFC-FE156 FLOW ELEMENT - SFC FILTER BYPASS SC 331 2SFC*FT36A CAPACITANCE FLOW TRANSMITTER, SFP CLG SYS FLOW L SC 220 64 93 2SFC*FT58A CAPACITANCE FLOW TRANSMITTER, SFC PMP DISCH FLOW SC 261 B
15 2SFC-FT1 04 CAPACITANCE FLOW XMTR SC 228 2SFC*FT36B CAPACITANCE FLOW TRANSMITTER, SFP CLG SYS FLOW L SC 224 66 188 2SFC*FT58B CAPACITANCE FLOW TRANSMITTER, SFC PMP DISCH FLOW SC 289 B
13.8 2SFC-FT47A CAPACITANCE FLOW TRANSMITTER, 2SFC-F1A OUTLET FLOW SC 342 69 336 2SFC-FT47B CAPACITANCE FLOW TRANSMITTER, 2SFC-F1 B OUTLET FLOW SC 342 69 336 2SFC-FV113 FLT 1A & 1B BYPASS FLOW VALVE SC 336 32 353 2SFC-FV124 SF POOL TO COND/RADWASTE, FLOW VALVE SC 232 69 81 2SFC-FV47A 2SFC-F1A OUT FLOW, FLOW VALVE SC 342 36 23 2SFC-FV47B 2SFC-F1 B OUT FLOW, FLOW VALVE SC 342 34 334 B-70
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINEIRAD COL/AZ ID (X)
(Y) 2SFC*HV1 15 CASK AREA FILL VALVE SC 345 59 127 2SFC*HV116 CASK HOLDING TRANSFER PUMP SUCTION HAND VALVE RB 350 39 122 2SFC*HV1 21 CASK HOLDING TRANSFER PUMP DISCHARGE VALVE HAND RB 352 39 122 VALVE 2SFC*HV17A 2SFC-FLT1A BYPASS, HAND VALVE SC 300 53 293 2SFC*HV18A 2SFC-FLT1A INLET, HAND VALVE SC 298 52 285 2SFC*HV35A 2SFC-TK1A INLET VALVE SC 345 50 49 2SFC*HV37A 2SFC-HT EXCHGR XCONNECT HAND VALVE SWEL SC 232 66 185 2
2SFC*HV54A SKIMMER SURGE TANK OUTLET SC 328 37 36 2SFC*HV6A SF POOL SUCTION XCONN, HAND VALVE SC 300 48 273 2SFC*HV17B 2SFC-FLT1B BYPASS, HAND VALVE SC 298 41 263 2SFC*HV18B 2SFC-F1B INLET SC 298 51 280 2SFC*HV35B 2SFC-TK1B INLET V SC 345 46 130 2SFC*HV37B 2SFC-HT EXCHGR DISCH V HAND VALVE SC 232 65 190 B-71
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC*HV54B SKIMMER SURGE TANK OUTLET Sc 328 42 140 2SFC*HV6B SF POOL CLG WTR XCONN, HAND VALVE SWEL SC 300 52 250 2
2SFC*HV114 FUEL TRANSFER CANAL GATE A DRAIN VALVE SC 321 41 73 2SFC*HV148 CASK GATE DRAIN VALVE SC 320 44 44 2SFC*HV149 GATE DRAINS HEADER ISOLATION VALVE SC 320 41 39 2SFC-LG126 SFP LEAK DETECTION SC 290 77 70 2SFC-LG128 REFUELING CAV & SF POOL SC 314 63 296 2SFC*LT32A CAPACITANCE LEVEL TRANSMITTER, SFP SURGE TANK WATER SC 330 B
4 LEVEL 2SFC-LT2A ELECTRONIC LEVEL TRANSMITTER, SPENT FUEL POOL LVL H/L RB 355 70 90 2SFC*LT32B CAPACITANCE LEVEL TRANSMITTER, SFP SURGE TANK WATER SC 330 B
7 LEVEL 2SFC-LT2B ELECTRONIC LEVEL TRANSMITTER, SPENT FUEL POOL LVL H/L RB 355 71 101 2SFC*P1A SFC WATER CIRC PUMP 1A SC 290 B
14.6 B-72
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-P2 CASK HANDLING TRANS PUMP RB 352 B
7.3 2SFC*P1 B SFC WTR CIRC PUMP 1 B SWEL SC 290 B
13.5 2
2SFC-P4A SFP HOLDING PUMP SC 328 B
18.9 2SFC-P4B SFC HOLDING PUMP SC 328 B
18.7 2SFC-PCV1 31 SFC EDU1 DRIVE PRESS CONT VALVE SC 337 46 328 2SFC-PCV150 SEAL SPLY TO FLTR HLDG, PRESS CONT. VALVE SC 328 83 346 2SFC-PDT25A CAPACITANCE PRESSURE TRANSMITTER DIFF, 2SFC-FLT1A SC 332 B
18 2SFC-PDT25B CAPACITANCE PRESSURE TRANSMITTER DIFF, 2SFC-FLT1B SC 332 B
18 2SFC-PI14A BOURDON TUBE PRESSURE INDICATOR, 2SFC*E1A INL PRESS SC 230 68 68 2SFC-PI15A BOURDON TUBE PRESSURE INDICATOR, 2SFC*E1A OUT PRESS SC 232 68 68 2SFC-PI14B BOURDON TUBE PRESSURE INDICATOR, 2SFC*E1B INL PRESS SC 226 67 207 2SFC-PI15B BOURDON TUBE PRESSURE INDICATOR, 2SFC*EAB OUT PRESS SC 224 67 207 2SFC-PI60B BOURDON TUBE PRESSURE INDICATOR, 2SFC*P1B DISCH SC 291 58 244 PRESSURE B-73
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG ID COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINEIRAD COL/AZ (X)
(Y) 2SFC-PI136 BOURDON TUBE PRESSURE INDICATOR, SERVICE AIR HEADER SC 289 56 348 PRESSURE 2SFC-PI137 BOURDON TUBE PRESSURE INDICATOR, SFC EDU1 DRIVE SC 337 48 331 PRESSURE 2SFC-PI26A BOURDON TUBE PRESSURE INDICATOR, 2SFC-FLT1A FLT BED SC 306 59 328 TOP PRESSURE BOURDON TUBE PRESSURE INDICATOR, 2SFC-FLT1 B FLT BED 2SFC-PI26B TO RSUESC 306 61 335 TOP PRESSURE 2SFC-PI45A BOURDON TUBE PRESSURE INDICATOR, 2SFC-FLT1A PUMP P4A SC 333 42 358 DISCH PRESS 2SFC-PI45B BOURDON TUBE PRESSURE INDICATOR, 2SFC-FLT1 B PUMP P4B SC 333 43 350 DISCH PRESS 2SFC-PI53A BOURDON TUBE PRESSURE INDICATOR, 2SFC-FLT1A FLT BED SC 306 59 327 BOT PRESSURE 2SFC-PI53B BOURDON TUBE PRESSURE INDICATOR, 2SFC-FLT1B FLT BED SC 306 60 333 BOT PRESSURE 2SFC-PI60A BOURDON TUBE PRESSURE INDICATOR, 2SFC*P1A DISCH SC 291 57 295 PRESS B-74
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-PI133 BOURDON TUBE-DUAL RANGE PRESSURE INDICATOR, 2SFC-SC 336 50 343 TK3 OUTLET PRESSURE 2SFC-PI1142 PRESS. INDICATOR SC 289 67 232 2SFC-PNL141 SFC FLTR CONT PNL SC 328 48 313 2SFC-PT143 PNEUMATIC PRESSURE TRANSMITTER, CASK HDL PMP SUCT SC 333 65 62 PRESS 2SFC-PT144 PNEUMATIC PRESSURE TRANSMITTER, CASK HDL PMP DISCH SC 333 64 63 PRESS 2SFC*PT3B CAPACITANCE PRESSURE TRANSMITTER, SFP CIRC PMP SUCT SC 266 58 244 PRESS 2SFC*PT3OB CAPACITANCE PRESSURE TRANSMITTER, SFP CIRC PMP DISCH SC 266 58 244 PRESS 2SFC-SAS1 SFC SAMPLE SINK SC 328 2SFC-SOV1 14 FUEL TRANSFER CHANNEL GATE A DRAIN VALVE, SOLENOID SC 315 41 73 OPERATED VALVE 2SFC-S0V148 FUEL TRANSFER CHANNEL GATE A DRAIN VALVE, SOLENOID SC 320 44 44 OPERATED VALVE B-75
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List BLDG BLDG COMPONENT COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-S0V149 GATE DRAINS HEADER ISOLATION VALVE, SOLENOID OPERATED SC 320 41 39 VALVE 2SFC-SOV1 15 CASK AREA FILL VALVE, SOLENOID OPERATED VALVE SC 345 59 127 2SFC-50V1 16 CASK HOLDING TRANSFER PUMP SUCTION VALVE, SOLENOID RB 350 39 122 OPERATED VALVE 2SFC-S0V121 CASK HOLDING TRANSFER PUMP DISCHARGE, SOLENOID RB 352 39 122 OPERATED 2SFC*SOV153 FILTER HDR INL ISOL VCH, SOLENOID OPERATED VALVE SC 289 47 277 2SFC*SOV154 FILTER HDR INL ISOL VCH, SOLENOID OPERATED VAVEL SC 289 45 277 2SFC*SOV17A 2SFC-F1A BYPASS, SOLENOID OPERATED VALVE SC 289 53 293 2SFC*SOV18A 2SFC-F1A INLET, SOLENOID OPERATED VALVE SC 289 50 278 2SFC*SOV19A 2SFC-F1A OUTLET, SOLENOID OPERATED VALVE SC 306 33 25 2SFC*SOV33A SKIMMER SURGE TANK LEVEL, SOLENOID OPERATED VALVE SC 328 37 60 2SFC*SOV35A 2SFC-TK1A INLET V, SOLENOID OPERATED VALVE SC 328 50 49 2SFC*SOV37A 2SFC-HT EXCHGR DISCH V, SOLENOID OPERATED VALVE SC 306 66 185 B-76
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC*SOV54A SKIMMER SURGE TANK OUTLET SWEL SC 331 37 36 2
2SFC*SOV6A SF POOL CLG WTR XCONN, SOLENOID OPERATED VALVE SC 289 48 273 2SFC*SOV17B 2SFC-F1B BYPASS, SOLENOID OPERATED VALVE SC 289 41 263 2SFC*SOV1 8B 2SFC-F1 B INLET, SOLENOID OPERATED VALVE SC 289 50 276 2SFC*SOV19B 2SFC-F1B OUTLET, SOLENOID OPERATED VALVE SC 306 36 240 2SFC*SOV33B SKIMMER SURGE TANK LEVEL, SOLENOID OPERATED VALVE SC 351 29 122 2SFC*SOV35B 2SFC-TK1B INLET V, SOLENOID OPERATED VALVE SC 328 45 133 2SFC*SOV37B 2SFC-HT EXCHGR DISCH V, SOLENOID OPERATED VALVE SC 232 65 190 2SFC*SOV54B SKIMMER SURGE TANK OUTLET, SOLENOID OPERATED VALVE SC 328 42 140 2SFC*SOV6B SF POOL CLG WTR XCONN, SOLENOID OPERATED VALVE SC 289 52 250 2SFC-SOV11A 2SFC-FLT1A INLET V, SOLENOID OPERATED VALVE SC 332 33 2
2SFC-SOV1 1 B 2SFC-FLT1 B INLET V, SOLENOID OPERATED VALVE SC 332 35 345 2SFC-SOV12A 2SFC-FLT1A MAIN DRAIN VALVE, SOLENOID OPERATED VALVE SC 331 42 359 B-77
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List BLDG BLDG COMPONENT COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-SOV12B 2SFC-FLT1B MAIN DRAIN VALVE, SOLENOID OPERATED VALVE SC 331 43 348 2SFC-SOV13A 2SFC-FLT1A AIR SCOUR VALVE, SOLENOID OPERATED VALVE SC 328 34 11 2SFC-SOV13B 2SFC-FLT1B AIR SCOUR VALVE, SOLENOID OPERATED VALVE SC 328 36 338 2SFC-SOV134 2SFC-TK3 RESIN OUT V, SOLENOID OPERATED VALVE SC 335 50 327 2SFC-S0V39A 2SFC-FLT1A AIR BLOWDOWN VALVE, SOLENOID OPERATED SC 328 35 15 VALVE 2SFC-S0V39B 2SFC-FLT1 B AIR BLOWDOWN VALVE, SOLENOID OPERATED SC 328 38 332 VALVE 2SFC-SOV40A 2SFC-FLT1A PMP P4A, SOLENOID OPERATED VALVE SC 344 33 13 2SFC-SOV40B 2SFC-FLT1B PMP P4A, SOLENOID OPERATED VALVE SC 345 35 337 2SFC-SOV41A 2SFC-FLT1A BACKWASH/FILL VA, SOLENOID OPERATED VALVE SC 342 36 23 2SFC-SOV41B 2SFC-FLT1A BACKWASH/FILL VA, SOLENOID OPERATED VALVE SC 342 39 327 2SFC-SOV42A 2SFC-FLT1A PRECOAT SPLY VALVE, SOLENIOD OPERATED SC 328 33 342 VALVE 2SFC-SOV42B 2SFC-FLT1B PRECOAT SPLY VAL, SOLENOID OPERATED VALVE SC 328 34 342 B-78
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List BLDG BLDG COMPONENT COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-SOV43A 2SFC-FLT1A VENT/OVERFLOW VALVE, SOLENOID OPERATED SC 335 40 335 VALVE 2SFC-SOV43B 2SFC-FLT1 B VENT/OVERFLOW VALVE, SOLENOID OPERATED SC 335 43 335 VALVE 2SFC-SOV44A 2SFC-FLT1A DOME DRAIN VALVE, SOLENOID OPERATED VALVE SC 336 37 359 2SFC-SOV44B 2SFC-FLT1 B DOME DRAIN VALVE, SOLENOID OPERATED VALVE SC 336 38 347 2SFC-SOV47A 2SFC-FLT1A OUTLET FLOW, SOLENOID OPERATED VALVE SC 342 36 23 2SFC-SOV47B 2SFC-FLT1 B OUTLET FLOW, SOLENOID OPERATED VALVE SC 342 34 334 SOLENOID OPERATED VALVE FOR OPERATION OF 2SFC-2SFC-SOV1 09 AOV109; BLOWDOWN VALVE FOR 2SFC-STR5 SC 332 30 2SFC-SOV1 142 SOLENOID VALVE OPERATED SC 300 76 232 2SFC*TE31A 100 OHM PLATINUM @ 0 DEG CENTIGRADE RTD ( DUAL SC 332 37 2.8 ELEMENT), SFP SURGE TANK TEMP OUT 2SFC*TE8A 100 OHM PLATINUM RES. TEMP. DETECTOR, SFP HT EXCH OUT SC 221 B
4.6 TEMP B-79
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC-TE48A COPPER CONSTANTAN THERMOCOUPLE, MOT INBD SL BRG SC 294 B
14.6 TEMP 2SFC-TE49A COPPER CONSTANTAN TYPE T THERMOCOUPLE, MOT OUTBD SC 294 B
14.6 SL BRG TEMP 2SFC-TE52A COPPER CONSTANTAN THERMOCOUPLE, PUMP RADIAL BRG SC 294 B
14.6 TEMP 2SFC-TE57A COPPER CONSTANTAN TYPE T THERMOCOUPLE, PUMP SC 294 B
14.6 THRUST BRG TEMP 2SFC*TE31B 100 OHM PLATINUM @ 0 DEG CENTIGRADE RTD ( DUAL SC 334 B
7.8 ELEMENT), SFP SURGE TANK TEMP OUT 2SFC*TE8B 100 OHM PLATINUM RES. TEMP. DETECTOR, SFP HT EXCH OUT SC 224 B
11 TEMP 2SFC-TE48B COPPER CONSTANTAN TYPE T THERMOCOUPLE, MOT INBD SL SC 294 B
13.8 BRG TEMP 2SFC-TE49B COPPER CONSTANTAN THERMOCOUPLE, MOT OUTBD SL BRG SC 294 B
13.8 TEMP 2SFC-TE52B COPPER CONSTANTAN THERMOCOUPLE, PUMP RADIAL BRG SC 295 B
13.8 TEMP B-80
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINEIRAD COL/AZ ID (X)
(Y) 2SFC-TE57B COPPER CONSTANTAN TYPE T THERMOCOUPLE, PUMP SC 294 B
13.8 THRUST BRG TEMP 2SFC-TE1 10 100 OHM PLATINUM @ 0 DEGC RESISTOR TEMP DETECTOR, RB 353 73 105 SPENT FUEL POOL TEMP 2SFC-TE46A TEMPERATURE ELEMENT, 2SFC-FLT1A SC 342 31 244 2SFC-TE46B TEMPERATURE ELEMENT, 2SFC-FLT1B SC 342 30 2
2SFC-TI7A BIMETAL TEMPERATURE INDICATOR, HT EXCH 2SFC*E1A INL SC 230 67 73 TEMP 2SFC-TI9A BIMETAL TEMPERATURE INDICATOR, HT EXCH 2SFC*E1A OUT SC 232 66 76 TEMP 2SFC-TI7B BIMETAL TEMPERATURE INDICATOR, HT EXC 2SFC*E1B INL SC 227 64 203 TEMP 2SFC-TI9B BIMETAL TEMPERATURE INDICATOR, HT EXCH 2SFC*E1B OUT SC 225 66 207 TEMP 2SFC-TI1142 TEMP.INDICATOR SC 289 67 232 2SFC*TK1A FUEL POOL SKIM SURGE TANK RB 330 B-81
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2SFC*TK1 B FUEL POOL SKIM SURGE TANK RB 330 2SFC-TK3 SPENT FUEL POOL PRECOAT SC 328 F-4404-C MECHANICAL THIMBLE SC 240 61 205 W-7508-C MECHANICAL THIMBLE SC 331 34 359 2CEC*PNL828 BOP INSTRUMENT PNL DIV1 SWEL CRR 288 AJ 11 1
2CEC*PNL829 BOP INSTRUMENT PNL DIVI CRR 288 AJ 11 2CEC*PNL831 BOP INSTRUMENT PNL DIV2 CRR 288 AJ 12 2CEC*PNL837 DIV I BOP ISOLATION CABINET CRR 288 AE 11 2CEC*PNL838 DIV II BOP ISOLATION CABINET CRR 288 AE 12 2CEC*PNL859 DIV I AUXILIARY RELAY PANEL SWEL CRR 288 AE 11 1
2CEC*PNL861 DIV II AUXILIARY RELAY PANEL CRR 288 AE 12 2CEC*PNL873 PRIMARY CONTAINMENT PURGE PANEL A CCR 306 AG 11 2CEC*PNL875 PRIMARY CONTAINMENT PURGE PANEL B CCR 306 AG 12 B-82
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List BLDG BLDG COMPONENT COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2ENS*SWG101 4160 EMER SWGR 101 SWEL CSA 261 AD 11.5 1
2ENS*SWG103 4160 EMER SWGR 103 CSB 261 AD 12.4 2SCM*PNL101A 120/240V AC FUSE DIST PNL CRR 288 AE 10.2 2SCM*PNL103A 120/240V AC DIST PNL SWEL CRR 288 AD 10.5 1
2SCM*PNL105A 120/240V AC FUSE DIST PNL CRR 288 AE 10.5 2SCM*PNL302B 120/240V AC FUSE DIST PNL CRR 288 AG 14 2SCM*PNL303B 120/240V AC DIST PNL CRR 288 AG 14 2SCM*PNL305B 120/240VAC FUSE DIST PNL CRR 288 AE 14 2CES*RAK105 RACK (SFC/CMS INSTRUMENTATION)
SWEL SC 261 52 292 2
2SWP*MOV17A MOTOR OPERATED GATE VALVE SWEL SC 206 B
4.5 2
2SWP*MOV18A B-83
ATTACHMENT 2 EQUIPMENT LISTS Table B-2 Nine Mile Point Unit 2 Base SWEL-2 List COMPONENT BLDG BLDG C O COMPONENT DESCRIPTION SWEL2 BLDG ELEV.
LINE/RAD COL/AZ ID (X)
(Y) 2CCP*MOV14A GATE VALVE SFC*E1A INLET (MOTOR OPERATED VALVE)
SWEL SC 217 68 74 2
2CCP*MOV1 8A 2SWP*MOV21A SWP to SFC makeup MOV SWEL Sc 291 B
7.1 2
2FNT-GATE1 SFC Gate B-84
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI Safety NTTF LINE/RAD COL/AZ Sft No.
23 Component ID Comp Description BLDG ELEV (X)
(Y)
Function/
2.3 (X)
(y)
Notes Class 1 0 2NMP*RE3217D RADIATION DETECTOR (LPRM) TO PC 300 5
LPRM 1 2
0 2SWP*STR4A SELF CLEAN STRAINER AND SW 261 K
9 1,2,3,4,5 MOTOR 3
1 2EHS*MCC101 EMER MCC 101 SW 261 K
9.7 1,2,3,4,5 4
1 2EHS*MCC102 EMER MCC 102 ABN 240 W
0 1,2,3,4,5 5
2 2EJS*PNL104A 600V EMERGENCY PANEL ABN 240 W
32 1,2,3,4,5 600V U.S EMERGENCY 1,2,3,4,5 6
2 2EJS*US1 CSA 261 AG 11.1 SWITCHGEAR (Note 1) 7 3
2ENS*SWG101 4160 EMER SWGR 101 CSA 261 AD 11.5 1,2,3,4,5 8
4 2EJS*X2 4160/600V HPCS XFMR CSH 261 AA 13 1,2,3,4,5 9
6 2CSH*P1 H.P.C.S. PUMP SC 178 W
12.5 3
10 5
21CS*P1 RCIC PUMP; TURBINE SHAFT SC 175 B
9 2,3,4 DRIVEN 11 5
2SLS*PIA STANDBY LIQUID CONTROL PUMP SC 289 B
8.3 1
PlA 12 5
2SWP*P1A SERVICE WATER PUMP SW 224 K
8.8 1,2,3,4,5 13 6
2EGF*P1A FUEL OIL TRANSFER PUMP DG 261 A
11.2 1,2,3,4,5 B-85
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINEIRAD COL/AZ Safety No.
23 Component ID Comp Description BLDG ELEV
(
(y)
Function/
Class Notes INCLUDES ALL ASSOCIATED RHR PUMPS, AUX, BWR, ELEC (VERT 14 6
2RHS*P1A MTD) ELECTRIC MOTORS, ABN 175 E
13.4 3,4,5 GENERAL G.E. DESIGNATOR E12-C002A CCP AOV to Seal Cooler for RHR 15 7
2CCP*AOV37A Pump, Fails Closed to allow SWP to ABN 183 94 91 3,4,5 provide cooling to RHR Pump.
2CPS-FN1 PURGE INLET TO 16 7
2CPS*AOVl04 DRYWELL OUTSIDE AUTOMATIC SC 294 44 133 5
ISOLATION VALVE PURGE EXHAUST FROM DRYWELL 17 7
2CPS*AOVl08 INSIDE AUTOMATIC ISOLATION PC 299 32 337 5
VALVE PURGE EXHAUST FROM 18 7
2CPS*AOV1 11 SUPPRESSION CHAMBER222 53 330 OUTSIDE AUTOMATIC ISOLATION VALVE 19 7
2GTS*AOV1O1 PRIMARY CONTAINMENT PURGE SC 319 0
42 5
ISOLATION VALVE 20 7
2GTS*AOV2A BUTTERFLY OR TRICENTRIC V SG 266 E
33.7 5
B-86
ATTACHMENT 2
.EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINE/RAD COL/AZ Safety No.
Component ID Comp Description BLDG ELEV Function/
2.3 (X)
(Y)
Notes Class 21 7
21CS*PCV115 LUBE OIL CLR PRESS CONT V SC 186 60 167 2,3,4 22 7
2MSS*PSV121 SAFETY/RELIEF VALVE PC 296 20 30 2,3 23 7
2RDS*AOV124 SCRAM DISCHARGE VOLUME SC 283 82 21 1
VENT - AUTOMATIC 24 7
2RDS*AOV130 SCRAM DISCHARGE VOLUME SC 240 81 198 1
DRAIN - AUTOMATIC 25 7
2SWP*AOV22A SWP Alternate cooling to RHR Pump ABN 186 99 92 3,4 26 8
.2CSH*MOV101 HPCS Pump suction isolation for CST SC 177 71 243 3
"B" (PID 33B @ D9)
HPCS MIN FLOW BYPASS 27 8
2CSH*MOV105 OUTSIDE REMOTE MANUAL SC 218 74 5
3,5 ISOLATION VALVE (PID 33B @ G5) 28 8
2CSH*MOV107 CSH TO RPV OUTSIDE REMOTE SC 292 39 215 3,5 MANUAL ISOLATION VALVE CSH SUCTION FROM SP OUTSIDE 29 8
2CSH*MOV118 REMOTE MANUAL ISOLATION SC 195 36 220 3
VALVE CSL TO RPV OUTSIDE REMOTE 30 8
2CSL*MOV104 MANUAL ISOLATION VALVE (PID SC 295 B
7.3 3,5 032A @ H3)
B-87
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINEIRAD COL/AZ Safety No.
23 Component ID Comp Description BLDG ELEV (X)
(Y)
Function/
2.3
()
(y)
Notes Class CSL SUCTION FROM SP OUTSIDE 31 8
2CSL*MOV112 REMOTE MANUAL ISOLATION SC 195 B
4.7 3,5 VALVE (PID 032A @ G9)
DFR DRAIN TANK LINE OUTSIDE 32 8
2DFR*MOV120 AUTOMATIC ISOLATION VALVE SC 218 53 25 5
(PID 63E @ E7)
21AS*SOV164 OUTSIDE AUTOMATIC ISOLATION SC 294 43 58 2,3,5 VALVE (PID 19D @ C10)
21AS*SOVX181 PRESSURESOLENOID OPERATED SC 294 47 59 2,3 VALVE (PID 19D @ J3)
RCIC STEAM SUPPLY VALVE TO 35 8
21CS*MOV120 SC 188 53 170 2,3,4 TURB 36 8
21CS*MOV126 ICS TO RPV OUTSIDE REMOTE SC 292 50 167 2,3,4,5 MANUAL ISOLATION VALVE MOTOR OPERATED VALVE FOR 37 8
21CS*MOV129 PUMP SUCT FROM CNDS ABN 242 84 60 2,3,4 STORAGE TANK 21CS*T1 TURB THROT MOTOR 38 8
21CS*MOV150 OPERATED VALVE; SUPPLIED SC 184 57 160 2,3,4 W/EQP 21CS*T1 B-88
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINE/RAD COL/AZ Safety No.
Component ID Comp Description BLDG ELEV Function/
2.3 (X)
(Y)
Notes Class DUAL SOLENOID OPERATED VALVE (3-WAY 39 8
2RDS*SOV139 REDUNDANT SCRAM PILOT VALVE SC 261 0
0 1
ON 2RDS*HCU0219)
ALTERNATE ROD INSERTION 40 8
2RDS*SOV158 VALVE, SOLENOID OPERATED SC 261 75 20 1
VALVE RHR LOOP A TEST RETURN TO 41 8
2RHS*FV38A SUPPR POOL COOLING (PID 31C SC 206 72 90 0
@ B6)
SHUTDOWN COOLING SUPPLY 42 8
2RHS*MOV112 INSIDE AUTOMATIC ISOLATION PC 256 26 171 3,4,5.
VALVE 43 8
2RHS*MOV1 15 RHR SERVICE WATER CROSS TIE, ABS 181 W
37 3,4,5 MOTOR OPERATED GATE VALVE.
44 8"A" RHR HEAT EXCHANGER ABN 181 E
37 3,4,5 DISCHARGE VALVE CONTAINMENT SPRAY TO 45 8
2RHS*MOV15A DRYWELL OUTSIDE REMOTE SC 294 B
6 5
MANUAL ISOLATION VALVE B-89
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINEIRAD COL/AZ Safety No.
Component ID Comp Description BLDG ELEV Function/
2.3 (X)
(Y)
Notes Class RHS PUMP PlA SUCTION OUTSIDE 46 8
2RHS*MOV1A REMOTE MANUAL ISOLATION SC 195 B
5.1 3,4,5 VALVE 47 RB2RHS*MOV4B ABS 184 W
9 3,4,5 8 MOTOR OPERATED VALVE 48 2RHS*MOV8A RHR H.E. ElA INLET BYPASS ABN 181 E
38 3,4,5 MOTOR OPERATED VALVE RHR H.E. A SHELL SIDE INL 49 8
2RHS*MOV9A MOTOR OPERATED BUTTERFLY ABN 201 W
46 3,4,5 VALVE 50 8
2SLS*VEX3A SLS EXPLOSIVE VALVE SC 296 B
8.5 1
MOTOR OPERATED GATE VALVE 51 8
2SWP*MOV1 5A TO 2HVR*UC403A (HPCS Pump SC 197 B
11.4 3
Room Unit Cooler) 52 8
2SWP*MOV19A Isolation to Reactor Building Balance ABN 219 W
29 3,4,5 of Plant Loads 53 8
2SWP*MOV33A SWP TO RHR HTX OUTLET VALVE ABN 181 E
36 3,4,5 54 8
2SWP*MOV3A Isolation to Turbine Building Balance SW 265 K
9.3 1,2,3,4,5 of Plant Loads 55 8
2SWP*MOV50A Divisional Cross tie isolation valve SW 265 L
9.3 1,2,3,4,5 56 8
2SWP*MOV599 Turbine building BOP header return PT 255 AM 2.6 3,4,5 B-90
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINEIRAD COL/AZ Safety No.
Component ID Comp Description BLDG ELEV Function/
2.3 (X)
(Y)
Notes Class 57 2SWP*MOV66A SWP FR CLR 2EGS*EG1MOTOR DG 271 A
11 1,2,3,4,5 OPERATED VALVE 58 8
2SWP*MOV90A SWP TO RHR HTX INLET VALVE ABN 180 E
48
.3,4,5 59 10 2HVR*UC401F RHR PUMP RM B-UNIT CLR ABS 177 W
20 3,4,5 60 10 2HVR*UC403A HPCS PUMP RM UNIT CLR SC 176 B
11.8 3
61 14 2EJA*PNL101A CB 120/240V HEATER PANEL CSA 261 AG 11.5 1,2,3,4,5 62 14 2EJS*PNL100A SWGR RM A EMERGENCY 600V CSA 261 AG 11.5 1,2,3,4,5 PANEL 63 14 2SCM*PNL103A 120/240V AC DIST PNL (EE-011A)
CRR 288 AD 10.5 1,2,3,4,5 PANEL (120 VAC POWER 64 14 2VBS*PNL101A DISTRIBUTION FROM CTR 288 AE 10.5 1,2,3,4,5 2VBA*UPS2A) 65 15 2BYS*BAT2A 125V DC BAT.2A DIV I CBR 261 AE 11.9 1,2,3,4,5 UNINTERRUPTIBLE PWR SUPP 66 16 2VBA*UPS2A INCLUDINGCSA 261 AD 11.9 1,2,3,4,5 TRANSFORMER&MANUAL BYPASS SWITCH B-91
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI Safety NTTF LINE/RAD COLIAZ Sft No.
23 Component ID Comp Description BLDG ELEV (X)
(Y)
Function/
2.3 WX (y)
Notes Class RECTIFIER / INVERTER / STATIC 1,2,3,4,5/
67 16 2VBA*U PS2C SWTCCB 237 AD 12 Nt SWITCH Note 1 68 17 2EGS*EG1 STANDBY DIESEL GENERATOR DG 261 AA 10.5 1,2,3,4,5 69 18 2CES*RAK004 RACK (RRS/CSL SC 261 52 82 1,3 INSTRUMENTATION) 70 18 2CES*RAK015 RACK (MAIN STEAM FLOW A SC 215 57 343 2
INSTRUMENTATION) 71 18 2CES*RAK017 RACK (ICS INSTRUMENTATION)
SC 175 79 135 2,3,4 72 18 2CES*RAK024 RACK (CSH INSTRUMENTATION SC 175 80 205 3
RACK) 73 18 2CES*RAK026 RACKSC 261 71 291 1,2,3,4 INSTRUMENTATION/RACKC) 74 18 2CES*RAK029 RACK (RCIC INSTRUMENTATION)
SC 175 55 213 2,3,4 75 18 2CES*RAK030 RACK (SRM/IRM PRE-AMP SC 240 64 270 1
INSTRUMENTATION) 100 OHM @ ODEG C PLATINUM 76 19 2CMS*TE120 RESISTANCE TEMP DETECTOR, PC 253 41 167 5
MONITORS DRYWELL TEMPERATURE INDICATING TEMPERATURE 77 19 2HVP*TIS13A ITC EG TEMP DG 265 AA 10.2 1,2,3,4,5 SWITCH, 2EGS*G1 CONT RM TEMP B-92
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI NTTF LINE/RAD COLIAZ Safety No.
Component ID Comp Description BLDG ELEV Function/
2.3 (X)
(Y)
Notes Class 78 20 2CEC*PNL622 INBOARD VALVE RELAY PANEL CCR 306 AH 12 5
79 20 2CEC*PNL828 BOP INSTRUMENT PNL DIV1 CRR 288 AJ 11 3,4,5 80 20 2CEC*PNL859 DIV I AUXILIARY RELAY PANEL CRR 288 AE 11 1,2,3,4,5 81 20 2CEC*PNL894 DIV 1 SUPPRESSION POOL TEMP CRR 288 AE 11 3,4,5 MONITORING PANEL 82 20 2CEC*PNL896 BOP INSTRUMENT PANEL DIV 1 CRR 288 AJ 11 2,3,4 83 20 2CES*IPNL406 2EGS*GI CONTROL PANEL (ECPA DG 261 AA 10.2 1,2,3,4,5 CONTROL VOLTAGE 125 VDC) 2EGS*EG1 CONTROL PANEL 84 20 2CES*IPNL407 (EGPA/ CONTROL VOLTAGE 125 DG 261 AA 11 1,2,3,4,5 VDC)
REMOTE SHUTDOWN CONTROL 85 20 2CES*PNL405 CB 261 AC 12 1,2,3,4,5 PANEL 86 20 2CES*PNL504 SERVICE WATER STRAINERS SA 261 K
9 3,4,5 CONTROL PANEL 87 21 2EGA*TK1A COMP AIR RECEIVER TANK DG 261 0
0 1,2,3,4,5 88 21 2EGF*TK3A STDBY DIESEL GEN 2EGS*EG1 DG 275 0
0 1,2,3,4,5 FUEL OIL DAY TANK 660 GAL.
89 21 21AS*TK34 ADS VALVE ACCUMULATOR PC 289 0
0 2,3 B-93
ATTACHMENT 2 EQUIPMENT LISTS Table B-3: Nine Mile Point Unit 2 - SWEL-1 EPRI Safety NTTF LINEIRAD COL/AZ Sft No.
23 Component ID Comp Description BLDG ELEV (X)
(Y)
Function/
2.3 (X)
(y)
Notes Class 90 21 21AS*TK4 ADS ACCUM AIR RECEIVER SC 289 0
0 2,3 91 21 2RHS*E1A HEAT EXCHANGER ABN 198 0
0 3,4,5 STORAGE TANK FOR STANDBY 92 21 2SLS*TK1 LIQUID CONTROL STEM SC 289 0
0 1
LIQUID CONTROL SYSTEM 1,2,3,4,5/
93 14 2BYS*SWG002A 125VDC SWITCHGEAR CSA 261 AG 11 Note41 Note 1 94 1
2DMS*MCCA1 125VDC MCC ABN 240 99 73 1,2,3,4,5 95 14 2BYS*PNL204A 125VDC DIST PNL DG 261 AA 10.3 1,2,3,4,5 125 VDC HPCS DIESEL 96 14 2CES*IPNL414 GENERATOR DISTRIBUTION DG 261 AA 13 3
PANEL 97 8
2HVP*MOD1C MOTOR OPERATED DAMPER DG 279 AA 10.5 1,2,3,4,5 98 8
2HVP*MOD6C MOTOR OPERATED DMAPER DG 280 AA 11 1,2,3,4,5 99 11CONTROL BUILDING CHILLED CCL 261 AA 10.8 1,2,3,4,5 WATER CHILLER.
Notes:
(1)
These items were installed or modified since the IPEEE.
B-94
ATTACHMENT 2 EQUIPMENT LISTS Table B Nine Mile Point Unit 2 - SWEL2 EPRI No.
NTTF 2.3 Component ID Comp Description BLDG ELEV LINEIRAD COL/AZ (Y)
Class (X) 100 8
2SFC*HV37A 2SFC-HT EXCHGR XCONNECT SC 232 66 185 HAND VALVE 101 8
2SFC*HV6B SF POOL CLG WTR XCONN HAND SC 300 52 250 VALVE 102 5
2SFC*P1B SFC WTR CIRC PUMP 1B SC 290 B
13.5 103 8
2SFC*SOV54A SKIMMER SURGE TANK OUTLET SC 331 37 36 104 18 2CES*RAK105 RACK (SFC/CMS SC 261 52 292 INSTRUMENTATION) 105 8
2SWP*MOV17A MOTOR OPERATED GATE VALVE SC 206 B
4.5 106 8
2CCP*MOV14A GATE VALVE SFC*E1A INLET SC 217 68 74 (MOTOR OPERATED VALVE) 107 8
2SWP*MOV21A SWP to SFC makeup MOV SC 291 B
7.1 B-95