ML20117E635
| ML20117E635 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/31/1996 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20117E624 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 9605160277 | |
| Download: ML20117E635 (446) | |
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SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION IN RESPONSE TO:
NRC GENERIC LETTER 87-02/USI A-46 VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS PECO ENERGY COMPANY MAY 1996 D OCK O 277 P PDR
SEISMIC EVALUATION REPORT iO FOR PEACH BOTTOM ATOMIC POWER STATION i
TABLE OF CONTENTS l
j SECVON PAGE e
1.0 INTRODUCTION
1
1.1 BACKGROUND
1 i i 1.2 PURPOSE 1 2.0 SCOPE / METHOD 2 3.0 PLANT DESCRIPTION AND DESIGN BASIS 3
, 3.1 GENERAL PLANT DESCRIPTION 3 3.2 SITE LOCATION 4 l 3.3 SITE GEOLOGY AND SE:. MOLOGY 4 l
l 3.4 -STRUCTURES 6
, 3.5 PLANT SEISMIC DESIGN BASIS 6 l 3.6 SEISMIC DESIGN OF SYSTEMS AND COMPONENTS 12 i
l 3.7 A-46 SEISMIC INPUT 14
!' 4.0 SEISMIC EVALUATION OF EQUIPMENT 17 4.1 SEISMIC CAPACITY VS. DEMAND 17
- 4.2 EQUIPMENT SCREENING AND WALKDOWNS 20 4.3 TANKS AND HEAT EXCHANGERS EVALUATIONS 42
, 4.4 RACEWAYS EVALUATIONS 42 2
4.5 HYDRAULIC CONTROL UNITS 44 i
1
3 l SEISMIC EVALUATloM REPORT
'O eon esacs sorTou Arouic Powsa station i i
4.6 DESCRIPTION
OF OUTLIERS 44
)
5.0 REFERENCES
47 ATTACHMENTS A- RESUMES AND TRAINING RECORDS OF KEY PROJECT PERSONNEL l
- B THIRD PARTY AUDIT REPORT AND RESUME i
i C SVDS D OSVS E CABLE /CONDUlT RACEWAY SYSTEM AREA
SUMMARY
SHEETS O
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SEISMIC iD/ALUATION REPORT Q _
FOR PEACH BOTTOM ATOMIC POWER STATION
1.0 INTRODUCTION
1.1 Backaround The requirements for seismic design of nuclear power plants have evolved' over the years from the application of commercial building codes earlier in the 1960's, to more sophisticated methods being used today. In view of the extent of these changes in design reguliements, the NRC initiated Unresolved Safety Issue USl A-46, " Seismic Qualification of Equipment in Operating Plants," in December 1980. In early 1982, the Seismic Qualification Utility Group (SOUG) was formed to develop cost effective means of verifying the seismic adequacy of equipment in operating plants.
The results of the industry efforts in this area, have culminated in the issuance of Revision 2 of the Generic implementation Procedure (GlP) for seismic verification of nuclear plant equipment and a number of supporting .
documents and reports. Subsequently, the USNRC has documented its !
review of the GlP in Supplemental Safety Evaluation Report No. 2 (SSER-2)
(ref. 5.1.2) and issued Supplement No.1 to Generic Letter (GL) 87-02 (ref.
5.1.1). PECO Energy Company provided its response to GL 87-02 in a O letter dated September 18,1992 (ref. 5.1.6) outlining its proposed schedule and approach.
1.2 Purpose l
The purpose of this report is to document, in compliance with GL 87-02, the seismic evaluations performed to address USl A-46 at PBAPS Units.2 and 3 using the Generic Implementation Procedure (GIP) (ref. 5.2.2) developed by the Seismic Qualification Utility Group. The composite safe shutdown I equipment list and relay evaluations are documented in separate reports.
The Safe Shutdown Equipment List Report (ref. 5.3.1) has in it the composite SSEL and includes all of the equipment identified as being needed for safe shutdown of the plant including: (1) equipment which was reviewed for seismic adequacy; (2) equipment which could be adversely affected by relay chatter; and (3) other types of equipment needed for safe shutdown but which did not require a review for seismic adequacy or relay chatter (e.g., inherently rugged equipment like check valves or passive equipment like filters). -
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SEISMIC EVALUATION REPORT O Foa PE^cs sorTou ^Touic PowEa sTarion The Relay Evaluation Report (ref. 5.3.2) describes the results of the relay review performed in accordance with the GIP methodology. The essential
, relays were identified in the circuits of mechanical and electrical equipment i
needed for safe shutdown of the plant. The seismic capacity of the essential re!ays was compared to the seismic demand imposed on them and the results presented in the Relay Evaluation Report. Cabinets and
- panels which house essential relays were identified in the relay review and were evaluated for seismic adequacy and are included in this report.
This report describes the results of the seismic review of active mechanical and electrical equipment, tanks and heat exchangers, and raceways for i
cable and conduit.
PBAPS has complied with the SQUG commitments set forth in GIP-2 (ref.
5.2.2), including the clarifications, interpretations, and exceptions identified i
in SSER-2, No significant or programmatic deviations from the GIP have been made in the PBAPS USI A-46 program.
l O j U 2.0 SCOPE / METHOD 3 The essential features of the SQUG approach, for the resolution of A-46, are the use of earthquake experience data, generic equipment qualifications and equipment specific seismic qualification data, or data on similar equipment. To use these sources of data, SQUG and EPRI have collected and organized the associated information and developed guidelines and i criteria for its use. The GIP 2 summarizes the technical approach and
- provides detailed implementation and documentation requirements for the 1
application of experience data to verify the seismic adequacy of the safe j
, shutdown equipment.
The GIP approach for verifying the seismic adequacy of mechanical and electrical equipment is consistent with the intent of Generic Letter 87-02, j
" Verification of Seismic Adequacy of Mechanical and Electrical Equipment ;
in Operating Reactors, Unresolved Safety issue (USI) A-46", including NUREG-1030 (ref. 5.1.3) and NUREG-1211 (ref. 5.1.4). The approach is also consistent with the EPRI Seismic Margins Assessment Program (SMA) described in ref. 5.2.1. The four major steps used for the evaluation of the majority of the equipment are listed below:
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SEISMIC EVALUATION REPORT
- -O FOR PEACH BOTTOM ATOMIC POWER STATION i i
Selection of Seismic Evaluation Personnel Identification of Safe Shutdown Equipment ,
Screening Verification and Walkdown Outlier identification and Resolution j
- Several types of individuals were involved with this program, with the qualifications, and responsibilities described in GlP Section 2, part II. These 1
{ include: Systems engineers and Plant Operations personnel who have a j
- comprehensive understanding of the plant layout and the function and l operation of the equipment and systems in the plant, Seismic Capability engineers who perform the Screening Verification and Walkdown of the safe shutdown equipment, and Relay Evaluation personnel who perform the relay functionality review.
The Seismic Capability engineers must exercise sound engineering judgment during the Screening Verification and Walkdown. Therefore the selection and training of qualified Seismic Capability engineers for j participation on the Seismic Review Teams (SRTs) is an important element
- of the A-46 program. The resumes and training records of key individuals
. that participated in the completion of the USl A-46 effort for PBAPS are included as Attachment A.
4 The Third Party Audit was conducted by Mr. Harry Johnson, Mr. Luis Gonzalez and Mr. Gregory Rahner of Programmatic Solutions.
The Third Party Audit is summarized in Attachment B.
The identification of safe shutdown equipment is documented in the SSEL report. The screening verification and walkdown are described in Section 4 as are the equipment determined to be outliers.
l 3.0 PLANT DESCRIPTION AND DESIGN BASIS
- 3.1 General Plant Description PBAPS Units 2 and 3 are GE BWR4s with Mark I containments. Unit 2 and 3 are designed to operate at a rated core thermal power of 3458 Mwt.
(100% steam flow). Bechtel Power Corporation provided engineering and 4
construction services.
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g SEISMIC EVALUATION REPORT V FOR PEACH BOTTOM ATOMIC POWER STATION 3.2 Site Location The Peach Bottom Atomic Power Station is located partly in Peach Bottom Township - York County, partly in Drumore Township - Lancaster County and partly in Fulton Township - Lancaster County, in southeastern Pennsylvania on the westerly shore of Conowingo Pond at the mouth of 1 Rock Run Creek. It is about 38 miles north-northeast of Baltimore, l
Maryland and 63 miles west-southwest of Philadelphia, Pennsylvania.
PBAPS Units 2 and 3 are situated on a 620 acre property. The Units are co-owned by PECO Energy Company, Public Service Electric and Gas Company Delmarva Power and Light Company and Atlantic City Electric Company and operated by PECO Energy.
l Included in the Unit 2 and 3 exclusion zone is Unit 1. Unit 1 is now in SAFSTOR status which allows it to be safely stored and subsequently decontaminated to levels that permii release of the facility for unrestricted use.
Q O A 500 KV unattended substation is located within the site property about 2000' northwest of Unit 3. Another 500 KV unattended substation is located about 1600' south-southwest of Unit 2. Figures 2.2.9 and 2.2.10 ;
of the PBAPS UFSAR (ref. 5.2.3) show the general site plan.
Access to the site is via Maryland Route 623 which intersects U.S. Highway Route 1 about 8 miles south-southeast of the site. From this point,7 miles of bituminous all-weather road leads to the Atom Road, a bituminous all weather road, which leads to the Unit 1 plant area. Approximately 1.5 miles beyond Atom Road on Maryland Route 623 is Lay Road, a hard surfaced, bituminous road which leads to Units 2 & 3. This road passes close by the northern 500 KV substation.
3.3 Site Geoloav and Seismoloav Section 2.5 of the UFSAR (ref. 5.2.3) contains a detailed description of the geologic and seismologic studies performed at PBAPS. The following is a brief summary of the data presented in the UFSAR.
l The original site topography was characterized by rugged, heavy terrain.
Original elevations ranged from about 400' in the western portion of the site O
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SEISMIC EVALUATION REPORT
(] FOR PEACH BOTTOM ATOMIC POWER STATION to about 110' near Conowingo Pond. The ground surface generally slopes rather steeply downward in an easterly direction toward the river.
The most prominent site features include Unit 1, the Susquehanna River and Rock Run Creek. Rock Run Creek is a minor tributary of the Susquehanna and is located south of Units 2 & 3.
The site is mantled by residual soils derived by weathering of the underlying schist. These soils are compact and consist of sandy silt and silty sand with gravel. The underlying Peters Creek schist is greenish-gray to white chlorite schist interbedded with searns and bands of quartzite that range up to 6' in thickness.
~
The upper zone of the bedrock formation has been greatly altered by weathering to essentially a friable material containing ribs of relatively unweathered rock. The interface between the overlying residual soil and the highly weathered rock is transitional. Although rock structure generally is evident in the highly weathered material, some of it has been destroyed r~s by the weathering process. The zone of severe weathering ranges in V thickness from less than 10' to more than 60'. However, this zune is generally limited to thicknesses of 25' or less. The greatest thicknesses of highly weathered rock are encountered in the higher western portion of the construction area.
Below the highly weathered zone, the schist becomes harder and fresher.
The relatively fresh rock surface is encountered at depths ranging from 15' below original grade, near the Susquehanna River, to greater than 80' below grade in the higher western portion of the construction area.
i in the site area, the Peters Creek formation is characterized by thin lenticular bedding and strong flow cleavage resulting in a well developed schistosity.
A major cut into the formation was made in conjunction with the plant construction. Recent mapping of the schist exposed in this cut indicates that, along the face of the cut,in the vicinity of Units 2 & 3, the predominant strike of the schistosity is between North 55" East and North 65 East. The dip of the schistosity is between 60 and 70 to the southeast throughout the site.
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SEISMIC EVALUATION REPORT ,
Q FOR PEACH BOTTOM ATOMIC POWER STATION
[ . The exposed rocks exhibit different jointing patterns and " major" joint r
patterns were mapped in the area south of Plant Coordinate North 1350. In !
1 addition to the " major" joint patterns, other minor features are apparent. !
Neither the major nor the minor joints appear to be continuous over large 1 i
areas. The effect of the jointing is to produce numerous, rather small, blocks of rocks. Additional minor joint patterns have been mapped, but are
- j. discontinuous and considered to be unimportant.
I In 1978, a previously undetected shear zone and diabase dike were mapped in the vicinity of the Peach Bottom site by Stone & Webster i Engineering Company, investigation and analysis by both Stone & Webster
! and Dames & Moore concluded that these geological features were a common occurrence for the region and were of no consequence due to the
- age of the features.
I 3.4 Structures l The seismic Class I structures at PBAPS are described in Appendix C of l the UFSAR. They are the Primary Containment including drywell, vents, 1
l torus and penetrations; Reactor Building; Main Control room complex l including Cable Spreading room, Emergency Switchgear rooms and Battery 1 j- rooms, which are integral with the Radwaste building; Diesel Generator
- building; Pump structure (portion containing the critical service water i pumps); Emergency Heat Sink facility including Cooling Tower, Main Stack, i Spent Fuel Pool, Reactor Vessel support pedestal, N,-Tank building, Post-F LOCA CADS liquid, and Recombiner building. These structures house or support Class I equipment and, therefore, maintaining their structural
}. integrity is considered essential for the ability to safely shut down the plant
- in the event of a design basis earthquake.
l 3.5 Plant Seismic Desian Basis l
! A brief summary description of the PBAPS Seismic Design Basis is l presented here.
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PBAPS Units 2 and 3 were issued Operating Licenses on August 8,1973 and July 2,1974, respectively, following issuance of a construction permit i on January 31,1968. During the construction licensing process for PBAPS, i the units were evaluated against the current Atomic Energy Commission j (AEC) draft of the 27 General Design Criteria (GDC) for nuclear power Page 6 i
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SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION plants rather than the 70 criteria proposed in July,1967. By Staff ,
Requirements Memorandum (SRM) SECY-92-223, issued on September l 18,1992, the Commission (with all Commissioners agreeing) approved the Staff proposal to not apply the GDC to plants with construction permits issued prior to May 21,1971.
3.5.1 Original Design Basis Seismic Input A dynamic analysis of structures, systems and components was conducted for PBAPS. The site design ground response spectra used are illustrated
{
in Figure 3.5-1 and 3.5-2. These spectra are for the horizontal components I of the Design Earthquake (DE) and the Maximum Credible Earthquake !
(MCE). Throughout this report, the Design Earthquake will be identified as
~
l the OBE and the Maximum Credible Earthquake will be identified as the l
SSE.
The input time history for PBAPS is the July 12,1952, Taft, California, S69E Earthquake normalized to the 0.05g design earthquake. The response o spectrum of this time history is compared to the site design response V spectrum in Figure 3.5-3 for 2% of critical damping. Because the SSE (0.12g) is simply scaled from the OBE, this relationship also holds for that earthquake. The vertical OBE and SSE response spectra are assumed to be 2/3 of the corresponding horizontal ground response spectra.
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SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION
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l SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION
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g SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION 3.5.2 Original Design and Analysis of Structures The list of Class I (seismic design) structures, equipment, and systems is presented in paragraph C.1.2 of the UFSAR. All structures listed as Class I structures were seismically analyzed by the response spectra method, except the portion of the pump structure containing critical service water pumps which was seismically analyzed by the time-history method. The method used in the seismic analysis consists of the following four steps: Formulation of the mathematical model of the structure or structures to be analyzed , Determination of natural frequencies and mode shapes l Finding the accelere, tion (g) levels from the response spectra curves ; Determination of the response of the structure to the earthquake in terms of moments, shears, and displacements Since the seismic Class I structures are founded on competent bedrock, a soil spring approach to characterize soil structure interaction was not used in the dynamic analysis. A simplified lumped mass method using a fixed base model was used. To assure the seismic integrity of equipment, the OBE input time-history was applied at the base of the buildings to generate, at selected elevations, additional time-histories 'and Floor Response Spectrum (FRS) curves. These time-histories and floor response spectrum curves were then utilized to assure the seismic integrity of the equipment. To obtain FRS curves for the SSE, the values obtained from the 2% structural damping OBE curves were multiplied by 2.4 (0.12/0.05). Since higher structural damping values for the SSE were not considered, the resultant SSE FRS are very conservative. Page 10
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FREQUENCf (cys) i l l FIGURE 3.5-3 i RESPONSE SPECTRA COMPARISON, l DESIGN EARTHQUAKE 5%g,2% DAMPING ( TO TAFT S69E RESPONSE SPECTRUM
I SEISMIC EVALUATION REPORT l FOR PEACH BOTTOM ATOMIC POWER STATION
- 3.6 Seismic Desian of Systems and Components i
3.6.1 Mechanical and Electrical Components l Detailed descriptions of the seismic design of safety-related mechanical components, as well as Class I instrumentation and electrical equipment are provided in Appendix C of the PBAPS UFSAR. The seismic qualification of mechanical and electrical components is based , on 2-D combination. That is; the results of earthquakes acting in the X (horizontal) and Y (vertical) directions simultaneously, and Z (horizontal) and Y (vertical) directions simultaneously were computed as separate cases. Seismic Class I (Class 1E) equipment are required to perform their safety functions during and following specified dynamic loadings. Class 1E equipment were purchased from approved vendors via procurement specifications. These procurement specifications required certification that the supplied components met the specified performance requirements. The i vendor's certification included substantiation that the equipment has been dynamically analyzed or tested in accordance with the specification. , Seismic qualification of electrical equipment was performed by analysis, dynamic testing, or a combination of analysis and dynamic testing. Seismic qualification of equipment by analysis was utilized when the equipment could be adequate!y represented by a model and the analysis could i determine its structural and functional adequacy. The analysis was either an equivalent static analysis or a dynamic analysis. Seismic qualification of equipment by dynamic testing was performed when qualification by analysis was insufficient to determine either the structural and/or functional adequacy. The supplier's certification included substantiation that the component was dynamically analyzed, dynamically tested, or a combination thereof. , Mechanical equipment was usually designed based on tests and experience. Simple stress analyses were sometimes used to augment the design of these components, but the primary design work did not depend upon detailec stress analysis. The equivalent static coefficients for equipment were obtained from applicable floor response spectra. For most equipment, the peak value of the applicable floor response spectrum was used in calculating the earthquake induced loads. Alternately, the Page 12
t i SEISMIC EVALUATION REPORT i FOR PEACH BOTTOM ATOMIC POWER STATION frequency of the equipment was determined and corresponding input i acceleration was obtained from the appropriate floor response spectra. The criteria, method of analysis and summary of critical stresses for various equipment are given in Table C.5.8 of Appendix C of the PBAPS UFSAR. 3.6.2 Design Baseline Evolution l The evolution of the Dynamic Qualification Program since issuance of the
- operating license has resulted in several changes being implemented.
l These are: L The discovery of additional hydrodynamic loads that were not originally considered in the design of Mark l Containments resulted
- in the initiation of the Mark l Program. This industry wide program
- applied to all General Electric Mark l Containment BWRs. The
! evaluation of the effect of hydrodynamic loads associated with SRV l discharges and LOCAs is an evolution that has been incorporated into the design baseline of the Dynamic Qualification Program. PBAPS voluntarily implemented the dynamic qualification of equipment in accordance with IEEE 344 (1975) (ref. 5.1.5). The
- dynamic qualification of equipment in accordance with IEEE 344 (1975) was incorporated into the design baseline in 1982 (ref. 5.2.9).
3.6.3 Cable and Conduit Raceway i l Electrical raceway system supports, that is, cable trays, conduit, and
- wireway gutter system supports, were seismically qualified by either the capacity evaluation method or the static analysis method. The capacity evaluation methodology considers a comparison of seismic loading based upon the raceway frequency, support frequency, and design spectra, to the allowable capacity. Maximum raceway loadings calculated by the equivalent static load method were evaluated against maximum raceway capacity determined by testing or analysis. Design adequacy was verified l by dynamic analysis (ref. 5.3.3).
3.6.4 Seismic Spatial Systems Interaction
} The original plant design did not include procedures for addressing seismic II/l considerations. However, as stated in the PBAPS UFSAR, Appendix C, j
- O Page 13
F; i ! SElSMIC EVALUATION REPORT
- O i
i FOR PEACH BOTTOM ATOMIC POWER STATION a structure designated seismic Class ll shall not degrade the integrity of a structure designated seismic Class I. 2 l Seismic Class 11 structures are structurally separated from seismic Class I ! structures by means of expansion joints to provide for unequal deflections j associated with independent movements of the structures. The !- arrangement was such that in the unlikely event that a Class 11 structure
- should collapse, it would not impair the safety function of the Class l l structure. The turbine building is a seismic Class ll structure. The main
! control room, the cable spreading room, computer room and emergency ! switchgear rooms, are located in the center portion of the turbine building } which was designated as a seismic Class I structure and was separated from the rest of the turbine building structurally by means of expansion
- joints, and was connected to the radwaste building west of the control room.
The criteria for the relative movements under maximum earthquake
- loadings required that the clearance provided exceeds the combined 4
movements. The relative movements under these loadings were accommodated by expansion joints at adjoining structures and by flexibility for piping systems. A dynamic analysis showed _that the cumulative
- maximum relative displacements of adjoining concrete structures will be
- about one-half of the clearance provided.
i i in the case of structures defined as partially Class I and partially Class ll j- and rigidly interconnected (i.e., Circulating Water Pump Structure), the { Class I structure was checked to assure it can carry any loads that may be . transmitted from the connected Class ll structure.
- 3.7 A-46 Seismic Input 3.7.1 Ground Response Spectra For all Class I structures except the Radwaste and Seismic Class I portion of the turbine buildings, the original design basis ground response spectra as described in Section 3.5.3 were used.
For the Radwaste and Seismic Class I portion of the Turbine buildings, a > 5% damped median (50 percentile) response spectrum was generated using a suite of time histories and compared with the A-46 GIP recommended ground response spectrum shape and the NUREG/CR-0098 Page 14
SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION (ref. 5.2.6) 84 percentile response spectrum shape with a PGA of 0.12g as a target input. The result of the analysis is documented in reference 5.1.8. 3.7.2 In-Structure Response Spectra The seismic input used in the A-46 effort is the same input used in the seismic analysis and design for PBAPS as described in Appendix C of the UFSAR. However, new in structure spectra were developed for the Radwaste / Turbine Building as described in Section 3.7.1. Design-basis in structure response spectra (IRS) for PBAPS are provided for OBE only and are contained in PBAPS Specification 11187-G-14 (ref. 5.2.9). To obtain floor response spectra for the SSE, ths values obtained from the 2% damped OBE were multiplied by 2.4 (0.12g/0.05g). Since the higher damping for the SSE was not considered, the values employed are very conservative. A PECO Energy letter (ref. 5.1.6) informed the USNRC that the _lRS as O. described above would be used for the USI A-46 program. This letter includes a description and plots of the IRS. The NRC response to PECO Energy Company (ref. 5.1.7) defined the PBAPS IRS as ." Conservative, Design" per GIP Section l1.4.2 (Ref. 5.2.2). Median centered in structure response spectra were generated for the l Radwaste / Turbine Building. The resuhs are documented in the PECO Energy Company Letter (ref. 5.1.8) to the USNRC. A Safety Evaluation ; Report (SER) was issued by the USNRC staff documenting the review of ; the procedure used for generating the " realistic, median centered" in-structure response spectra and concluded that it was acceptable for use in A-46 (ref. 5.1.9). Effective Grade for the PBAPS Class I structures is given in Table 3.7-1.
" Effective Grade" is defined as the average elevation of the ground surrounding the building along its perimeter. For PBAPS, which is founded on rock (except for a portion of the Diesel Generator building), the " effective grade" is the elevation wbare the Class I structure receives significant lateral support from the surrounding soil or rock, typically the elevation at the top of the base mat.
O Page 15
i p SEISMIC EVALUATION REPORT l V FOR PEACH BOTTOM ATOMIC POWER STATION (ref. 5.2.6) 84 percentile response spectrum shape with a PGA of 0.12g as a target input. The result of the analysis is documented in reference 5.1.8. 3.7.2 In-Structure Response Spectra The seismic input used in the A-46 effort is the same input used in the seismic analysis and design for PBAPS as described in Appendix C of the UFSAR. However, new in-structure spectra were developed for the Radwaste / Turbine Building as described in Section 3.7.1. Design-basis in structure response spectra (IRS) br PBAPS are provided for OBE only and are contained in PBAPS Specification 11187-G-14 (ref. 5.2.9). To obtain floor response spectra for the SSE, the values obtained from the 2% damped OBE were multiplied by 2.4 (0.12g/0.05g). Since the l higher damping for the SSE was not considered, the values employed are very conservative. A PECO Energy letter (ref. 5.1.6) informed the USNRC that the IRS as described above would be used for the USl A-46 program. This letter includes a description and plots of the IRS. The NRC response to PECO Energy Company (ref. 5.1.7) defined the PBAPS IRS as " Conservative, Design" per GIP Section 11.4.2 (Ref. 5.2.2). Median centered in structure response spectra were generated for the l Radwaste / Turbine Building. The results are documented in the PECO Energy Company Letter (ref. 5.1.8) to the USNRC. A Safety Evaluation l Report (SER) was issued by the USNRC staff documenting the review of the procedure used for generating the " realistic, median centered" in-structure response spectra and concluded that it was acceptable for use in A-46 (ref. 5.1.9). l 1 Effective Grade for the PBAPS Class I structures is given in Table 3.7-1.
" Effective Grade" is defined as the average elevation of the ground surrounding the building along its perimeter. For PBAPS, which is founded on rock (except for a portion of the Diesel Generator building), the " effective grade" is the elevation where the Class I structure receives significant lateral support from the surrounding soil or rock, typically the elevation at the top of the base mat.
O Page 15 4
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 3.7-1 EFFECTIVE GRADE FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND UNIT 3 [STROCTOR50f IEFFECTIVs[GRXD6
- , 7(El_EVdFT.))
4 Reactor Building Unit 2 and Unit 3 91 '-6" Radwaste/ Turbine Building 116'-0" Emergency Cooling Towers 120'-6" Circulating Water Pump Structure
- 80'/86' Pt i
Diesel Generator Building 127'-0"
- The central portion of the Circulating Water Pump Structure which
, houses the Emergency Service Water pumps and High Pressure Service Water pumps has an effective grade of 86'-0". The north and south bays which house the Circulating Water pumps have an effective grade of 80'. O Page 16
I SEISMIC EVALUATION REPORT !O FOR PEACH BOTTOM ATOMIC POWER STATION l i 4.0 SEISMIC EVALUATION OF EQUIPMENT i The reviews of the seismic adequacy of mechanical and electrical equipment on the PBAPS Safe Shutdown Equipment List (SSEL) were performed in accordance with Section l1.4 of the GIP. The Seismic Review Teams that performed the reviews consisted of at least
- two and in some cases three Seismic Capability Engineers, and always l
- included at least one licensed professional engineer. The teams were j composed of PECO Energy Company and VECTRA personnel. Plant support services for the walkdowns included craft to open equipment for internal inspections and to perform expansion anchor bolt tightness checks.
The walkdowns were performed beginning in July 1993. In general, the plant equipment was found to be well anchored and seismically rugged. Housekeeping issues were identified and some equipment items did not meet the GIP screening criteria and were identified , for further evaluations. i
' Tne seismic screening of components was documented ort Screening Evaluation Work Sheets (SEWS) in accordance with the requirements of the GIP. The results of the SEWS are condensed and summarized on Screening Verification Data Sheets (SVDS), also sorted by class and walkdown teams, and presented as Attachment C. The plant Cable Tray and Conduit Raceway reviews were conducted on an area basis and samples were selected for limited analytical reviews. The results are presented in Section 4.4. There are no large flat bottom storage tanks on the PBAPS SSEL. Other tanks and heat exchangers were evaluated using GlP-2 methods.
Outliers were identified as a result of the equipment screening and raceway review efforts. All outliers are documented on Outlier Seismic Verification i Sheets (OSVS) and have been included as Attachment D. All outliers were , reviewed to determine compliance with design documentation, none were found to present a significant risk to public health and safety and all were
- found to be in compliance with the original plant design basis.
4.1 Seismic Capacity vs. Demand i The enveloping of the ground response spectrum and the in-structure 4 Page 17 T
I 1 n SEISMIC EVALUATION REPORT U FOR PEACH BOTTOM ATOMIC POWER STATION response spectra (IRS) by the SQUG Bounding Spectrum and 1.5 times l the Bounding Spectrum, respectively, as required by the GlP Section 11.4.2 was performed. The results are documented in references 5.3.4 and 5.3.6. Table 4.1-1 lists the structure (s) and elevations containing SSEL equipment that have IRS exceedances over specific frequency ranges. Most equipment located at these elevations were classified as outliers since seismic demand exceeded capacity based on a comparison of 1.5 times bounding Spectrum versus Conservative Design In-Structure Response Spectrum at the appropriate equipment elevation. An exception to this rule is when the floor is located within 40' of effective grade. Resolution of these outliers is described in Section 4.6 of this report. Generic Equipment Ruggedness Spectra (GERS) were used to represent the seismic capacity of Motor Controlled Centers (MCCs), Class 1, and Low Voltage Switchgear, Class 2, as defined in the GIP Section 11.4.2.2 and Appendix B. J l 4 4 4 lO Page 18
I SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.1-1 RESPONSE SPECTRUM EXCEEDANCES FOR BUILDING ELEVATIONS CONTAINING SSEL EQUIPMENT
~
~
fFREQUENCY4 55TNOCT0hst~ ~
!!s[5VATi6Wl '
- " RANGES 7 ! h hWHERE-l m a '
ElRST5XC5EDS"AB5 165'-0" 5 - 8 Hz Reactor Building 195'-0" 5 - 12 Hz ! 234'-0" 5 - 30 Hz i 153'-0" 9 - 16 Hz ; Emergency Cooling Towers 168'-0" 7.5 - 16 Hz l 192'-0" 4 - 33 Hz 127'-0" 6.5 - 7.5 Hz Diesel Generator Building 151'-0" 5 - 14 Hz 161'-0" 4 - 16 Hz , i Radwaste / Turbine Building N/A N/A Circulating Water Pump Structure 112'-0" 11 - 20 Hz 130'-6" 12 - 20 Hz O Page 19
E SEISMIC EVALUATION REPORT . A FOR PEACH BOTTOM ATOMIC POWER STATION i 4.2 EaulDment Screenina and Walkdowns f Based on the results of the walkdowns and reviews performed by the SRTs, ^ the plant equipment was found to have good original seismic design; electrical cabinets were generally welded to embedded steel members,
- mechanical equipment were typically anchored with cast in place bolts.
j Equipment data such as vendor drawings was generally available and
- retrieved using plant databases. In one area, overhead components associated with the HVAC systems could impact safety related items. Most Identified interactions were related to proximity or housekeeping concerns.
, All SSEL equipment with the exception of those listed in section 4.2.1 were walked down by at least two seismic capability engineers. Included in the
- SEWS are seismic capacity versus demand comparison, Bounding Spectrum, GERS, anchorage and interaction caveats. In addition, 3 anchorage evaluations, where applicable, and field notes were included as
- part of the SEWS.
The evaluation for seismic adequacy of equipment was performed in O V accordance with the GIP, Section 11.4.4. Field inspections and analyses were performed. Tightness checks for concrete expansion anchors were i t performed. Cast-in-place or J-bolt evaluations used drawing embedment ! values. For expansion anchor bolts, minimum embedment values from the l GIP were used if the tightness check was acceptable. Reduction factors for I
- " reduced inspections" were utilized in cases where the tightness checks could not be performed. The majority of the required anchorage
, calculations were performed using the ANCHOR program (ref. 5.2.8) and j were included as attachments to the SEWS. i As stated earlier, the SVDS are included in Attachment C and provide an overall summary of the screening results. 4 4.2.1 Inaccessible items j Table 4.2-1 provides a listing of all individual components which were
- inaccessible during the walkdowns because they are located in contaminated areas, moderate to high radiation areas, or areas which are difficult to gain physical access to for inspection purposes.
- O Page 20
SEISMIC EVALUATION REPORT , FOR PEACH BOTTOM ATOMIC POWER STATION f k TABLE 4.2-1 1 INACCESSIBLE COMPONENTS l Q,. ASS 5 N ENT$M
^
- DESCRIPTION . MM.
M ,
- 4 !EVM?loi 0 VRV2-2 80960 VACUUM REUEF VALVE FOR MS REUEF General area walkdown.
VALVE C Similar to Unit 3 component. O VRV2 2-80960 VACUUM REUEF VALVE FOR MS REUEF General area walkdown. VALVE D Similar to Unit 3 component. 7 RV2 02-71C SRV Drawing review and similar to other SRVs on the SSEL 7 RV2-02 71D SRV Drawing review and similar to other SRVs on the SSEL 8A MO212-015 RWCU INLET INBOARD ISOLATION VLV SRT looked at robot video camera. 8A MO212 018 RWCU INLET OUTBOARD ISOLATION VLV General area walkdown and drawing review. 88 SV-81308 BACKUP NITROGEN TO ADS B SUPPLY Drawing review. 9 OAV091 Et D/G BUILDING VENT SUPPLEMENT SUPPLY General area walkdown and j FAN drawing review. 9 OBV091 E2 D/G BUILDING VENT SUPPLEMENT SUPPLY General area walkdown and FAN drawing review. 9 OCV091 E3 D/G BUILDING VENT SUPPLEMENT SUPPLY General area walkdown and FAN drawing review. 9 ODV091 E4 D/G BUILDING VENT SUPPLEMENT SUPPLY General area walkdown and FAN drawing review. 10 P0202231 HPSW PUMP ROOM 'B' LOOP SUPPLY DAMPER Simdar to P030223-4 and general area walkdown 10 P020223 2 HPSW PUMP ROOM 'B' LOOP EXHAUST Similar to P030223-4 and DAMPER general area walkdown 10 P020223 3 HPSW PUMP ROOM 'A' LOOP SUPPLY DAMPER Similar to P030223-4 and general area walkdown 10 P020223 4 HPSW PUMP ROOM 'A' LOOP EXHAUST Similar to P030223-4 and DAMPER general area walkdown 10 P0302231 HPSW PUMP ROOM 'B' LOOP SUPPLY DAMPER Similar to P030223-4 and general area walkdown 10 P030223-3 HPSW PUMP ROOM 'A' LOOP SUPPLY DAMPER Similar to P030223-4 and general area walkdown 21 OAT 38 DIESEL FUEL OIL STORAGE TANK General area walkdown and drawing review. 21 OBT38 DIESEL FUEL OIL STORAGE TANK General area walkdown and drawing review. Page 21
)
i SEISMIC EVALUATION REPORT 1 FOR PEACH BOTTOM ATOMIC POWER STATION O TABLE 4.2-1 (cont'd) 4 INACCESSIBLE COMPONENTS
. CLASS COtiPONENTj DESCRIPTION) . RAETHOD OFlii 1 i EVALUATION
~
- I i
21 OCT38 DIESEL FUEL OIL STORAGE TANK General area walkdown and j drawing review.
, 21 ODT38 DIESEL FUEL OIL STORAGE TANK General area walkdown and drawing rowew.
j
- r 4
! l
- O ;
i i i I, i
~
O Page 22 l
L SEISMIC EVALUATION REPORT ! FOR PEACH BOTTOM ATOMIC POWER STATION 4.2.2 Cases where the Intent of the Caveats are Met l i Table 4.2-2 provides a summary of those instances where the intent of the j caveat of the GIP is met but not the exact wording. l 4.2.3 Seismic interaction i~ ! The SRT seismic walkdowns included evaluation for potential seismic j interaction concerns, per GIP Section 11.4.5 and Appendix D. Seismic ! interaction concerns were documented on the equipment SEWS. i
- Given that the original plant design critena did not specifically address
!- compliance with Regulatory Guide 1.29, the SRT placed additional ! emphasis during the walkdowns on reviewing spatialinteractions to assure that no potentialinteractions were caused by permanent plant commodities
- or structures.
[ 4.2.4 Equipment Class Evaluations i ! The equipment on the SSEL was evaluated on an equipment class basis. l The classes of safe shutdown equipment are based on the equipment class ; j- terminology contained in the GIP and are shown on Table 4.2-3 of this i j report. A summary of each equipment class evaluation is presented in
- j. Table 4.2-4. This provides a concise synopsis on major equipment classes, j any unique features, and a summary of the screening and walkdown
- results. It also highlights issues that the SRT focused on during their reviews.
l i The table lists the total number of components requiring walkdown identified l for each GIP Class, the number of components screened-out and the specific components within each Class that were not screened-out and ! therefore identified as outliers. , 5 i 1 i i l i h-i ) Page 23 4
, - - , , . ~ _ - . . - . .
..v ,, , , . ,
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-2 EQUIPMENT MEETING INTENT BUT NOT LETTER OF CAVEAT
SUMMARY
. . . . . . . . . . , . . . . , . . , . . _ . ,_, .f , , . . _ , , . , . . . . . , . . . . . . . . , . . . . . . . .
? EQUIPMENT CLASS! ' iLETTERLOFJCAVEATd ,
., REASON INTENT?OFs a ifNOTiMETs LCAVEAT; MET) 2 (LV SWGR) Capacity vs. Demand Demand exceeds capacity in the range 6.5 to 7.5 Hz by 1.3%; existing FRS very conservative.
4 (Transformers) Type of anchorage not covered by Through bolt to concrete block wall. GIP For this case, anchors provide adequate tension and shear capacity. 5 (Pump) Drive motor and pump mounted on Separate skids for pump and turbine. common skid However, no differential displacement since pedestals have common slab and skids are very stiff. 3 7 (Fluid-Operated Valves) Actuator and yoke not braced Externally braced valve to floor; piping independently from pipe and valve actuators are supported in the same direction. 8 (MOVs) Actuator and yoke not braced Externally braced valve to floor; piping independently from pipe and valve actuators are supported in the same direction. 9 (Fans) Drive motor and fan mounted on Mounted directly to concrete slab at common base different point. However, no differential dieplacement. 2 (LV SWGR) Type of anchorage not covered by Anchor evaluations were performed 4 (Transformers) the GIP; Cast-in-place J-bolts for the using the guidelines of EPRI NP-20 (l&C Panels & Cabinets) embedded channel or angle do not 5228-SL, Rev.1, Vol.1 document. have the required GIP embedmont The results are documented on and 90 deg. hook length VECTRA Calculation No. 0067-00084-C-017 and various evaluations attached to the SEWS. O m Page 24
i SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION j TABLE 4.2-3 LIST OF SAFE SHUTDOWN EQUIPMENT CLASSES ~ Class 4 3* Description!; < Numtse@j - , ,
- 0 Others (i.e., Testable Check Valves, Strainers, etc.)
- 1 Motor Control Centers 2 Low Voltage Switchgear i 3 Medium Voltage Switchgear
) 4 Transformers
- '5 Horizontal Pumps 6 Vertical Pumps 7 Fluid Operated Valves 8A Motor Operated Valves 8B Solenoid Operated Valves 9 Fans 10 Air Handlers i 11 Chillers
- 12 Air Compressors I 13 Motor-Generators
- 14 Distribution Panels i
15 Batteries and Racks 16 Battery Chargers and Inverters ! 17 Engine-Generators 18 Instrument on Racks 19 Temperature Sensors 20 Control and Instrumentation Panels and Cabinets 21 Tanks and Heat Exchangers 22 Cable and Conduit Raceways
- N/A Hydraulic Control Units O
1 Page 25 i
O r SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION
^
megenery of Egetsuteett Uses.Wemfogun " " ., - ^ . y"_m.r. ^ Class Neuse ;
. -^. A of .-
f 1 _. '. _ , _ _ IUj:- i' _ ^leeuem
^ @!
^
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, '- ' , x.
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< s Casuponentejuj- : 4 ge s- - e s
< ClaseIt ~q:a c:- v ::.P:< ^
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U*"* a 2.,5. 0..:1g.5.0g . No amm imne.c:: mg m 4y .
~
% components are screened estJJ i valveelvecuum fellet valves, " " '
m ; - sNi ~ 'i > Sc: , [ ,_:ss.e ^
~
< s s, Motor Control Centere 3N11; Evaluanon of e-Jo.g. is Most MCOs are top t,i.ud to EJpcer,t walls. Each MCC j 16 / 25 00053,54,55,58 required. seceon is a standard 20% x 20M x 90 H. with typicalline-480V AC Power MCCs and 250V DC MCCs are Cuter ups consis6ng of 2 sec6ons or more. The base channels Hammer / Unitrol Units with are welded to embeds on reinforced concrete pads.
dmensions of 20*W x 20"D x 90-H per section. coo #7/We19; MCCs have interac6on Breaker compartments have removable buckets which had concems positve restraints, aqacent sec6ons were bolted together and al devices were found secured with vendor provided hardware. The load path given the top bracing was very 20s3s; Seistnic demand exceeds rugged, there were no large cut-outs or other items of . capacity. Evalua6cn of concem found in the design and support configuration of anchorage is required. MCCs. The majority of the MCCs had adequate eJu ge. Page 26
+ ~ SElSMIC EVALUATION REPORT .! FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUlPMENT CLASS EVALUATION t
*2n < La* Van *as suenameer (tysp "go' 'A11 ; "
-nam = . m wearmee commisw - tys === tipend ens mapeemd m em en vmuy - 4 ^
*- : Law Voltage Switchgoer are ITEt, .eseemseet.w s un- Twee asinsereemenleeums, consisteneyelettiesigndeemessen,9 hep J ~ ,
Aould Load Centers wWR * '
;$081erHrtarmjg - pu]gN, . , , , , , , , , Si@ included verWestlen feet 95 bufrideal inneheni heti %@
' tsmensione M98W x $8 0 N%
^
N [ Sons:LYSlh sesj mamp* teletel austraines Thansioneer and tensman 1 190H. po..r sooden. " g6. ..
.. -., s a ., ,
E(3:. S nassing Museds..iei ouhicle bolled to LV5. The veelous sections were'veemed ; M Sp s l e ?- ." " >
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n$jmp , < it,VS ime estendiend ' " _ s t 3 "*'"u"**"*n*'- - 0/8 "'" *'""'""i s*"'9'*' nas aoor ivuxeum voringe swacngear were openea ano especiso o Medium Voltage Swachgear are sea 15/ter17tte; latching mechar6sms which detal to verify consestency with design documents. The GE Units with dimensions of are not engaged. mspecean also included verifica6on that a4acent cubecles ; 26W x 73 D x 90H per sec6on. were bolted together, and that elecincal devices (such as , Top and bottom comer of relays, swnches, terminal blocks, etc.) were in place and i' doors are provided with property secured Breakers have lateral restraint on lower bolts which are not one-third. Flexitety of base members and the adequacy of ' engaged. the load path were reviewed There were no excessrve cut- ; outs; some cubicles had extemasy attached switches whidi ; 20A16,17,18 have spare are light weight and posi6vely secured. In addtion, the l breakers that are not anchorage (plug welds) of MVS to embednent plates was adequately secured which venhed. are an interacean concem
- MVA ^.
- - e0%c , y The 32VA ere W ey $$o Drapet mounh6_ -
efq, .g^$ ;;f 0 EUM*u" ==t -.a Z ::' .g ...,....,.....;.,, v Q= </d'$ ~~ -f k < ;seassmen: ransformere very horri # MYA3 ^
' . ~ anctioreci wWi 2 bon) 9:M 3The larger eensentmors as oli med shd enenchored. .. ..
- ; to 1000 MVA unite and eso eyi < g ,
Instead of 4 bebed " Modecaden documenteden le in piece.te;eopleon wth A88 0 s :er of WieddTrenetumors arei !&s. *
~
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,1000kVA VPE ventiated dritype senstormers in tw Unitel nM brechst mounted te walls;Georlit '
' ' ' ,- l2 & 3 Reacter Bldgel.Wellelseme inducted IrW=e =s of fiel enounted and,in 9m eensM f e@
~
M;b
^
s y!;f
~,
' ~
deanance between Sus} bus tere and See manei.eledisng .eruf
= ;-
felt gned units.tmenshorest - 9.u ;the hold down bones '
* ^
Page 27
O SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION M E
~..msnn Seiratigt;j, ~'
.: os see - - . are weewee noesamespesssenecemsomense 3
~
3 . . , weenc4tosed h8mahamansg giewendment ; i'"T
.; .y -
, doommeren sue ti pleos en x * ' '
.sopines aldt AO 1000 ;'
^
s
~
s
'" s 1~
' h! . w: '
v
- m
^ "
1 ' c<- SEI
- iKVAsensimmer
[$pe VPEvenetstee Q*%0 ' ' *
, UN W:.. ,.
T' :::s s f:g
~g Ep , (Cepesty vs demand does 7 j , ms ym -
~
g 1 '
- pm 3 , Review etveneur dragengt ^~ - ' '
~m m s
pp. -
. . . . . . m < 4
~ >
M, . y*. y surnet ' . (la eugstedis werer peeper :u:3
' s .r.J 55 ^
- .N d ~
I \ 1. s x s^ 19:. . m0% 4M Whc L ,
- M& ng.-;
~
s = gg , , . - - . . .
-L; _ _ r and demand '
s m v , s y , 5 Hothonal Punes 30/ 30 '* ou*ers None The RCIC, HPCI and RHR pumps and associated turtMnes are located in the Reactor BIdg at Els. 88 ft and 9f ft for both Units. The PCIC pump and turbine are mounted on separate skids /mncrete pedestals Each has a very rigid base and pedestals are supported off same concrete mat foundation. Anchorage was judged acceptable by SRT based on the wakdowns, review of existing documentason and A-46 anchorage evaluation. Attached piping was wel supported The ESW booster pumps, Diesel GeneratortD/G) Air Coolant Auxilig Purnps, D/G Jachet Coolant Auxiliary Pumps, D/C i.ube OR Auxiliary Pumps and D/G Fuel Oil Transfer Pumps are located in the D/G Bldg at B.127 ft As pumps were judged by the SRT to be wsR supported. Attached piping was also wen supported. Anchorage was judged acceptable by SRT based on the wakdowns review , of existing documentation and A46 anchorage evaluations. No seismic spatial interaction concerns were identified. Page 28
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION .I TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION i6: Wed Pum s
.....m.~ gQ/jQp w -- w ; M y ce mig med h p e r em L.. Nipe ed - Pany me kahd h tre.<
- we
%w HP9W & ESW Pumpa me Wr54 "@-
N ;shalt greater tem 40 9.10 '[Ptenp HouseetBJ11f Ri N y g gg g : ~7 empentsp0F.' g' ' } 4 i s { ~ ' ' .g <
&W
' ~
fueApft s' W' " ' ' , ~j"b MR '
., s < 3
~ " -
capeern Witt $ 2"
' W. yy t ;g W
non$ed O M h l : ~ ,
>~
kp47
~
x , [eransleind$,44em peaupy ' - s s ;s
. - . JV :hoseek W s
; ,' g:g
, , , .w -
m -
~
u a:g - ' ; s , , gg x , , 7 Fluid Opermed v 8= 24 / 72 ^ " "'d " M' " ; D"ac* ham centerrme io The sRT _ _2 secused on venricamon of the vahre AOtwd4eeA/9/C/D; top is outside of exponence operator weight and height rosaiction (based on pipe size). AOt43-33/A0343-33; database seesmec spetialinteractions, tie Sexibility of attached tubing AOS4 mea /9/C/D; / elecMeal conduit and tio potential for any cifferential AO" dsplacement between the piping and any actuator , supports AOR-eS-35A/5 Seismic demand exceeds There were no seismic spatial interaction concems A0343-32A9; capacity identified. In al cases attached lines had adequate AOS43-35A/9; Sexibety. For valves which require back-up air supply, m-82471A/9/C/DMMM attached tubing was hacked to im accumulator tanks to RV3.et471A/9/C/0/ES/G44/J/K/t.; W sWal % and m for any smic Aet.es.32Als
. teraction concoms in i
I e8A2 . =* c=="a= =a= - t4 / 834 2;0 E=--=a - < 8** a'=a8 *=== ~ 1* = ***"= *aad m e.ve%
+ sis? .,. Re y
^
+ capacQ N eperater spelght and height testieden W en l%e sles) 1
*Wp
> < < 4% u , y= .. .x 9vano not amassen ., solantespemalinseraesionslihs toeERpof ansehed ' JiS i w^" Mr @: -w yt 343 #' '
nig > x x- easteemaf W@M elaatical e0% and tus' potenuet for antallerental.. l l [ t l l i l Page 29
l l l SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION i TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION
-_ - m Sveemepamer weisms , r_ esamen m ppme == eny"asemer
's s .
' ZM -, jogdWenthshte h @ gg :.g. 7 " ,' 7'
^
amananen - ma - c.--~ q 3,, ,,,gg, g g,3; , s
@:- +
M~ cy= ;IIDIksestemme'st espeitence Mk hkuun menMh M eenessalehndled' g - s
, , j ,gg,,, g ,, g,,
, #pi[
*N s ..
W rs . gg IQ ' ' < Q!?g?g gg' ,[tIO484000, peauneel bewaneen uth esppost for E
. eds .g + -
~g.~g~ . ^ "
"7 estet sedaden eteenet. Seveselinetusoee W nisso 3 . __
; m
- mg
. s s 5 pestdy essene usese neesd;in e essen se af47 isis ath 3 g,
> - - +
- s. s e. Le jedge sm anesseln dessenese'es enhor adhemit or dnet. N
'W, s 4 s
e % <
< ~- '
m (any veswee anpest_imeds te mergmanent end el em( . W
. ,p$g +
' ~ ~ '
s - M1t tw. 2
, .s ,
'" fE' eenesqeense en the eposetEly of tie velveg 1s $%
,' ' , ' W9 - ', s A%# , , , . . . _ . . . , _ _ z.y L.,. s#D , . . ,
- = .
4 -
- s. ,
, e,,'e,shesses de am _uien em isiduo spenew $ mid [
' ag * tAetense tintegens cagesse and tieutue tutter ovelegden t , , i x'^ 7" '
~
~ ,
~, %eser desumentesen is 'seepdroel to deustomesse diet fesO
%_. , %c ;g y
~
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Avesese.eesepentie
~
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s
' ^
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> . .. . . .. .,,3 s
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-7 . ..q :.g..., s .). .y < x.::.
m y .
,, c.:.:., y..<.7,7c...- ......,.j,...s. . . . . .
.; a ' ap'"1 i <
scesieen yees.3 iim mener eposesse seamende er em anales ' eems s ne cast A
! m ex , ' esMy asses >aneses 4z.3 m R ~ 1 V~ m iten. Asse enne r sa Fureer enesysselevesseine eequimd
*' ~ > -
0M M .
. , , "" M i g.;p . ; i;teLdensmestale naampadah ti el apenmaar, 8B seconoes opereies ves= 11 / 12 M G mP e tcwidnoum Deahd .. ^ m perfonmid by em m for em SOVs are smes rugged located, therefore the SOVs. The SOVs are of compact design and were components.. caveats and interachon screened out based on he adequate flexibility of attached effects could not be Enes. No seestmc interaction concoms were identmed venfied. dsring the walkdowns. One SOV could not be located.
This SOV is either in the dywel or south isolaton valve room However, the tubing that was accesseble was walked l down and was found to be acceptabie i l Page 30 1
.I P
l I SEISMIC EVALUATION REPORT ' FOR PEACH BOTTOM ATOMIC POWER STATION ! e TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION i s ;. g 3. .. .~. .. _.
- s16 / 23- si --
+ **8"'8 " a**8 * '" : i*=***"******""8'***'*- i
~ ' Nm -ew teneben IAPT-808.jj i:. " = ^ '-- 88V8MGet ' - . , , _ . #igi;ij sedespeels part al Weel ' M N epielerage ~'
' ' spedi [
- a,tdame,=en se
,;;tsetAF unitsj re.c -
' s
c-
^
^*
rewaewash e "adeepseer(Cambit
~
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""7 9 M^
._ <w '
l .., , s suppefeud tese..thseleestl , s s ^ W > 4 , w'
@k
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*^
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4!:: ; . < ederdadDieteenelampyl ig " $*E $ [ l > s
- + " s '- >
, . w!:ii 1
- W '
- s. s e c:
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, rg:1 - *
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? ~ , !
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* $;5, , j *] .
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;,,g g,,,,,,,; g,,, 4 7 g , QW, . .j s
x . j;g , - alM ;! jib ~ ~.
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^^
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,g, -. .7, 8 .
JO gy .'- BIW og o g
%gg:: s (!%ifj espesig,. -
. etagesel inesi at G?151 R.81he ihmi ee. neb esppen' ed ' f
. m 4 30 we ' ,- - s tash wounm holmens and odemnsfasessmanet ; l
- x
- ' % - Ms SE+y ,
4 \ - M:S ancitesugel9,es.)4eeeSy inspessed and igend.te'attedt) l
, f{$[ ' m3 e Y!LY
^
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" iM efteHH.an.deelpt W[An 4%@ ._ ,, [
" ' ~~
g +
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~~ ' ~
^
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, 3;g. v:w.3 m.[mEil .
3 _ . . ~. .
< - - - , - x s
.a ,
gg y. ;
- s. .n , ,
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, . . , . . ,.s.,.,,.,.,_.., . . ~n ,
N
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g' y v < -
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=7.s , , 3,,,orw er sie m avat uniis are m j
- s ~, itsy temeth minute barrise.'. Access to the hna le not ? -
^-
< wm p . 4 . ,
? >
i s ~
~
, s 3 g g gg -
.c .,' ,
desessiemeden wres podenied tlyLWm SRT4 A general eres i ; x s .s' ggx >- s - -
{ _ f jewise gudeksign was perlenited b wer$y.9ed Siege le yt6 j , i
* ' M ' '
~
m->y 3.g, - '$d", s 4, e -- poteri8el fet interacean diet souhl siege 0Wely eSect We ten / ~ 3, An,, ... - -
.,, w me Ohe em assiseves sim sie weseesvis i x 4 , . Mis ^ 1 ; qs %y > . . . pestatened to date sshew a sempi cerNessen listseen and u] $!k g":7eq !!!$9 x , ~>
~
* ?p;s~I . " , " ] '
x i buit'end es deelgn ter PBAPS Unas 2.4 3dA'conservedve
. ; ,. @s s !!M . * ~ -
enecier bedt analyste men pertenned imins a knlwelpht of[ gg ' i% ,~ ' gg 4 - ?
,g33 x 1 x x J000 k: this $ epislyele shows a large W teater W tieje '
s d!s Ao < 40sg _, 2 " gei.)rg --~ s iW <Bernster
~ ^ - -
> - - ' - Red Head anchors s -= x h3A}<T' " ' ~
e4p;: rg ..e:. 3 Page 31 l
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION
< v s
?$$4-{ , ., , . .
^
MM. _ Ewww {E*Lir) M N M N y
^ ^
N, , ' ;m; tes maism.meer mer ten me mantes esedy to & s" ' _W comuele etelesentpeinen4huseveritieve should be nofL ~ MR ,
^
i e r w"m-aggmenced espinoamentj7he lane med meest.enchemen is:!) r,
- s 1
? .eesepeede , a :mn '
- ..e g -
rM,s. - , xcm
- A .N:
. .. y ;c ..x s w . s.....3,..x.. .
v .s n 3,;3 ;; s k [h? ~M' N .. e, pp .eenehet inne am seemese in me h ade a mass st;
' ' +' ,. ";-: :cN *k ^ >
j' ~
~, J
~
< , m ,
' ;the taas mejseg emppened wisi venudon iementme end t;
, ~
^~
" salemio seetminessTIm endtetege le asseputte pet AJE @
M
%n '
m -
% e m +3 . enesuneen '
Air Hondus 7j/7$ mm3; Inemceon w~ ns wth Tlw W lh focusal on e 7~- of he 10 overfioad HVAC systems. equipment cavoets, anderage inspecnons/ evaluations and Aar Harusers are HK Porter. Mamarlo Coas AXIT-31.0 and spatialinteraceans AX1P-12.9 units. The RCIC, HPCI, Core Spray and RHR room cooling coas 5 are locaisd in the Reactor Bldg at Roor El. 91 ft 6 in. andor 116 ft. The coolers are typicany mounted on frames. External piping is wet supported and no seismic interaction concoms were identiRed. The unit brackets are welded to he supporeng frame at four comers and at the fan ! loca6ons. OA . Att-J,m; heatmg piping at in y- 4, the 4 st,v,a L-n% are connected to upper nozzles poorfy embedded plates and/or base plates and in some instances supported may cause are supported by rod hangers or post members to the floor. excessive nozzle load. The SRT observed some oversized holes in baseplates and some poor qualty welds (porosity). In at cases, the SRT was able to judge that there was sufficsont redundanoes in l the support configuranon; in addison. VECTRA Calculation ! No. 0067-00084-C-022, Rev. O documents adequacy of the l cooler anchorage based on the conservative redsced inspecean option of the GlP. Therefore, the field condrtions i were evaluated and the boundng analysis demonstrated the adequacy of the support frame. , 1 Page 32
O O O SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION t TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION Interacton concems wHh No sestruc interaceon concems were identified for me room overhead HVAC systems. coohng units. The Emergency SWGR vont supply roe feiers and vent supply tan were inspected Overhead &ct is an interacten mncom. Dampers were idonelled as part of the Air Handing dass. TypiceRy, he dampers are an in-line component m the ventRaton duct. Fluid operated valves are attached to te ventiation duct sides andfor damper, and are Rule-of-the-Box with dampers and were found acceptabio For those dampers located in the Redweste Bldg EL 165 ft, the dampers were identined as acceptable. However, the overhead HVAC duct system for the entire area is tracked as an oudier he to concoms wie its support structure PD 20223-1 Tutung from Delta P PO 20223-3 swithes may be impacted by conduit. conduit is supported by beam clamps. E11 m. sem -
- m. ,zx, ca10n /;07. . o mb,-
~^ c s . g._ Ps 'n a a _,.
" 4a 3 ,,, a,
_c Air C - - - - - - - 0/0 N/A N/A N/A 12 g13s
^- ^
o~m ,LO LDi. i " %we. - m, ;*% m - ' w m J+. a = m.nw wi -
+
ns - 14 Diottbveon Pando 31 / 37 -W Dept d put is less man The SRT " L focused a wheatm d me Dismbuton panels are ITE and secea/2924; hat which is included in equipment caveats, anchorage inspectons/evaluatons and West WEB units. - M i exponence spatialinteraccons Misc. waN mounted dstibuton databeso in additon, panels. penols have anchorage This equipment class includes DC Roor mounted dishbuton concoms Anchor boks panels, wat mounted distribution panels. In addison, this have 2%* eccentncity and dass includes 120V AC weg mouned distribution panels. in addeon, comer plates are too flexible and do not The waB mounted units are weM represented in the provide an adequate load exponence database Most panels were tug tested by the pet. Also 20D21 has SRT and were found acceptable Panels are either bolted messmg bolt on bed of to be well or to two Urustrut members Pan *L No seismic interacton concems were idendfied by the SRT. Page 33
w SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION For the 125V DC dissibunon panels which are Noor mounted, depth of panelis less man earthquake exponence database. r15: semen = o nais= ;
-<0"/ 8 "' - ~- -- e 88" *** " * **a*. <* o*""" ane r so meone m me Tweem inen m n
- semenme sesde Catalum < isanneesswecoewseong ~.
- f4so.""edemuel s weis e 7003
- a tas nTthe eseam wen et may ser esemeng naosf Flat Plum CC rnodel 2GN-23 E k lhoj afdeh la eunide" E ~~ Lhsmensk compleedy enomeed each vow of hemoryeensi unhal ~' '
sg ..eupedance damh===. ... (fl.o; had side 'reeniend and ces was sepermed by a l. i
;Mand folk are notenug -
_l . . , , [ .8$) x - apacer< $ threes WsBS_elfWged esbanl0 design.\fbdtof v jppx *
. m We , ;wlsibenedes3hi.! 1. .. : wem based.h toen heeres eoogone, provkeng ent ::;gg
~
. 1:pi '
< eserhees Guarescent $ght) . anampman jeed pe$t and fighBly to seelet lateral lesAng and n
+
[are sempemled athIdesine1 :: to minimise movements she sedei woes bened to me ?
, y< -'>. '
m w;
'~7
,s (heutng epen Shoche. ~ ~ " 'conerses.GoodA consenese A 46 J _ ; eveksedan . ,
' " ~7eTJ~
- ty;
.~
**P . s
> 4 R; ~
.._.. ::ams pedanned whlen demonswesed that me enderage;weny seseptable. t " N T@ . , . "_ " m,
's -
AJ% y:4y , x 4 <
, s gg
.s W, , 9x ?A. ji",N, x4 cj se 9e -
%sm; m '
; o ..
aja
~
x^ - >~ m WW
!weas'wmo Idonened en enemy. refused and.evolumend to IE c g
^
, .~ ,
< ' BuSean 40 i n h M tied ween were Whd as:?
;g n@ -
~
- x yB -
, sport of De IPEEE psegran Desotare, to presence af j " '
@i
^
- +
blocksets near the besory rests were screenodeut < x 16 sener charn"* "'d 9/10 m 37 inumenon concoms h battery chargers and inverters are located in the Invertere These are housekeeping Turbine Bldg at El.135 ft. The battery chargers and Battery chargers are Cyberex issues;large number of inveners were inspected by the SRT. The units were Dual 200A 130/200 R3-S and drums, eye wash on opened to verify mounting of infomal devices and swerters. HDR Power. wooden table, Equid transfor ners AR of the small electrical devices were processing equipment and mounted witi a fut comphment of hardware. Transformers roof pipe with victaunc were mounted at base. Clearances between busses ad joints in the viciruty Also, skin are al greater than %*. The walkdown verified that the invenor 20D37 does not units were acceptable An A4 anchorage evaluation was have drip shield insteRed performed An&orage was acceptable There were no seismic interacoon concems identfied with the battery chargers. The SRT noted a potensat seismic interac6on concems with inverter 20037. Page 34
i l SElSMIC EVALUATION REPORT ! FOR PEACH BOTTOM ATOMIC POWER STATION . t TABLE 4.2-4 ;
SUMMARY
EQUIPMENT CLASS EVALUATION ;
-- '~
q pt ; gg r0 / 4r.
+ c - -- - --- - .- m - - 88***ha **ao*'a wah a (m om == om insummim unn.am samen vunna g g g g ,
Irukseneones; ," . ? toast panel on vammon . .., adN shid end hem adsgem mummi eneantly tr T . ' j
^
behesm mo wkhout lesendj sambang hemi bedad Na coneems som idensned otht l 2
^ ' >
~
- - aspedy, s sempestt'potenselseisovemodenof _ N ,, bat.1 i gg s x ~
' e M :3ube ei, and weser;cochng Onesi -(_ # wen 1.
^
in
, , s M , .vemed am be anoched eth se suppereng nummters.?Thol ~
I tisimi
~ - ~ :: tenhajase sun seppersed on 18 sedan tenissors, ,
e{c~::i? '!!!pjj . '^ % gsg. e
)
p . s. xy ^ , 4
^
S
~
' ^
- .!{t . @N,M hlpe =Ghf]hebMIf _.
s a .. . . emppeed end b here admones ensamy at _ _ _ _% ~ v::W.. W'suten es qdping and condult, to accommednes ' w; f - Wi..W .. &
^
~ !
s wi:~~
.,s. mp ~
g
. m- -s ., s a gq_, qg; gg g " - ' ~
g l;
^ Wi:i gjg; s }:g;
~
< x ; y : ;.g .; e r c. r: . e.; .:: ...,.,.s
=- 3. -: . . . . . < m. q . s :- .- e . t
^' ' y x ij$$ " ' hb v we$ M . mMI NFund D li
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[dieess shown on ensign damnge and eensidendjnf r
^* ^
M * ^
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+ m- . , gg ~
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eelsengg9=haand=t theumenesson.i,No concrees ooruss ; 4,gg 4 , ,,,,,,,,,,,,,,,,
^ ~
i s s x e 4 s wg . .. . ygr [15e3 per0 Breed whlCh demOnskened tiet WWD enteierege1.etl:
. A g:3.+.s 2
m~ . s =P x accepneen-s x e ,,m. r s. i x e..!$cs o
^
' " -pj ; ?d 2'-
*y
.:x p v
7, N~ s .;. .q.;,. , , . . . , , , . , . . . . , . . , . . . , , . . (
+
, , 4 niese gangs penes in mouneed asvesadan insteams wsM m -
+
1 x ~ < * (no inestel especay1 W to pensi becomma W die $ ; x w . s 3 ~
< > s irer prosess te.amdery of to support system (tdie ot) may bos .
=-
n < s - - -_ jw g g ; ,, ; f- .e,
,m dbEpedenetalers.iy 8
=w ..;.%.a ~ -
)
. ts - .
- Eff WE ~x F
. , '. .....g.....,., :.) . . . 7; .,. ,7 . . . :..y. j 4g. w
' _ ~, .Typkesy, annhead mano coneener k not med Mand i i s-N -
^
- ~
- tiese le potonestJnemencion whh sie engine ciental pensiJ i g.
% ti.ere is a. seismic Interacdon concom ' ~M !.
l I i t l i t i Page 35
f} SElSMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION Inowument on Rocke OPS 20224-1 Interacton with tubing to AR instrument racks on the SSEL are located in the Reactor 18 46/34 DPS 20224-3 sensor in duct. Oldg at various elevations. They are of simiar design. AI TIC 30223 Cover is loose. instruments on racks were walked down by Wie SRT to assess their seismic capabihty with an emphasis on wnyv. a attachment to the rack and rack anchorage The racks are primarily buit up of structural angles welded together with adequate bracmg Tghtness check on anchor bolts was not performed. The SRT felt that a proper tightness check could not be obtained due to grout thickness under the anchors and te itse of epoxy paint. In add 6on, some nuts are welded An A-46 anchorage evaluation was performed viiich demonstrated that the anchorage was acceptable. The evalua6on was based on as found information ottained by the SRT during the walkdown. Analysis assumed shell expansion anchor bolts and cxmservative approach to account for grout and the fact that a tightness check was not performed. PT-25005/PT-35085; Seismic demand exceeds Components were identitled where demand exceeded capacity. capacity and therefore the cv.w.ts were identified as outliers. Reanstic medan-centered, in-structure SSE spectra was generated by scahng IPEEE RRS and the outiers were resolved. 2AC65/29C65; Seismic capaczty exceeds 3AC65; demand. Anchorage does in addtion, the A-46 anchorage evaluation for not screen out. 2AC65/2BC65/3AC65 utilized the realistic in-snucture SSE spectra and demonstrated that the anchorage was acceptable. Page 36
t t i i i SEISMIC EVALUATION REPORT l FOR PEACH BOTTOM ATOMIC POWER STATION ; i I i TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION "19 ; s T L 'maa o 64. .1.,.J64.
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oAc"c'e7/otCoe7/oCCoe"7/o'0Coe7; sS*'c-"- ' " ^-""'***'*'**"*'"**"'**"P*"**"' Peness and Cetninets capacity interacean cabinets on tie SSEL was conducted to asses seismic concems exist regarding adequacy The primary purpose of the walkdown was to overhead crane controner. verify that intomal devices were property mounted and secured, were not excessively flexible, are seismically rugged and have an adequate load path to the cabinet i structural frame and andiorage. In addition, the cabinet anchorage was inspected / evaluated. Page 37
. . . _ . . . . . -- ~ _ . . . - . . - _ . - - . - . . ._ . .. _ -, _. - O O O SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION vm.aA.SCO; interacion concems with The SRT Team venhed that cabinets were not excessively 20C124/30C124; hotni;#,9 ssues i in the flexible, had no large cutouts in lower half, were of similar Control Room. These configuration to NEMA stan&rds, drawers and equipment cabinets are tracked as on slides were restrained from fating out, and doors were outliers. secured by latches or fasteners The cabinets found in the PBAPS Units 2 and 3 can be grouped into three categones, Hoffman type panels located throughout the plant, ver6 cal boards and console panels located in the control room, SWGR and Cable Spreading room, and similar type control board panels, located primanly in f.e Diesel Generator areas. 20C32/33; CatHnets are not bolted to 30C32/33 Wie a4acent catHnet, N 93 Interaction concems exist N' with a4acent non-safety cabinets and cable tray. 20C139 interacaon concem with A. Hoffman Type Panels attached procedure booit i The Hoffman Type control and instrumentation panels are Rush mounted or attached to unistrut channels which in tum are mounted to concrete or block wars. In some instances they are mounted to structural support steel. The panel sizes vary in dimension with the maximum size being in the 36"W x 42H x 22"D range. These panels are used as junctior> termination boxes and enclosures for devices such as relays, fuses, switches, indcator lights or instruments and cable connectors AI Hoffman Bcxes were tug tested by the SRT and judged acceptable. Page 38
.- _ _ . . . _. . .~. . . ...m . . _ . . . . _ _ - SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4
SUMMARY
EQUIPMENT CLASS EVALUATION B. Verticai Board and Console Panels The majority of the vertical board panels and consolo panels are located in the control room, SWGR room, Cable Spreedng room and D/G areas. The width of the panels varies from 30' to 36*, the height is typicafy 90* and the length varies imm 24' to 96*. Typica8y, several panels are located next to each other to form a large panel secean The SRT inspected each panel to determine if the indhmfuel panels were bolted to each other. The vertical board and console pane 8s contain control and instrumentation devices such as switches, pushbuttons, panel lights, recorders, relays, controllers, solid state circuit boards, power supplies, wiring and terminal blods and are manufactured with heavy gauge sheet metal and structural framing members which provide a good load path to the foundation. Panels were opened and inspected in detail to verify wh,cy with design documents. The inspection also induded verification that aqacent panels were bolted together, and that electncal devices were in place and property secured on front plates which have intermedate stiffeners. Flexibility of base members and the adequacy of the load path were reviewed and judged to be acceptable. There were no excessive cutouts. It was noted that some aqacent cabinets were not bolted to each other, therefore, impact of cabinets is not prevented during a seismic event. Page 39
I t SEISMIC EVALUATION REPORT ' FOR PEACH BOTTOM ATOMIC POWER STATION TABLE 4.2-4 ,
SUMMARY
EQUIPMENT CLASS EVALUATION l, Seip chart iwb were insW for mown 9 E=hpacy e and IM concoms by the SRT. A detailed reisw and evaluation of the anchorage was i performed by the SRT. l Several hoci;#4 concems were identified in the Control Room and therefore, some panels are being t tracked as outliers until hoci:34 ssues i are resolved "f 21 *<
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Page 40
i t Y SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION ! t [ ( [ TABLE 4.2-4 -
SUMMARY
EQUIPMENT CLASS EVALUATION a" ~ . 1 ' a ns au seem me is sewage Imme am aurios iermen
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- 22 Bac'rie.i Ceine Tr.v. & Pipe etenchion supports. Lateralload aitena of GIP See Secton 4.4 Conduit Rx Bldg. Its', RW Bldg.165* not met by pipe stanchen Mismuaneous cable trays and supports mnduit Conduls room T2171 Conduit supported by beam lamps which rely on friction to transfer verticalload.
w m 3* e - m w m m s p w n sme3*" Condun in RW % B.165' In e co m s M x x < < Fan Room overhead HVAC systems. Some conduits supported as;- by beam clamps which rely [ on friction to transfer verscalload. i.5Ef4g' : MUUs7 . . . 2/4 HCUs for Unit 3 Top honzontal frame for See Section 4.5
=
ydraulio Connel Unlie, d HCU piping does not have adequate interai bradng. Page 41
1 SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION O 4.3 Tanks and Heat Exchanaars Evaluations There were no flat bottom tanks identified on the SSEL. All other tanks were
- evaluated using the screening criteria defined in Section 7 of the GIP.
3 The RHR heat exchangers which are vertically mounted are not specifically l covered by Section 7 of the GlP. These Heat Exchangers were evaluated by the SRT using the general methodology and acceptance criteria described in Section 7.2 of the GIP. Additionally, anchorage capacities for all RHR heat exchangers were reviewed for SSE and hydrodynamic loads as part of the PBAPS Mark l Containment Program. The SRT has reviewed these analyses and the resulting modifications and concluded tnat they adequately address GIP criteria. As shown in Table 4.2-4, Summary Equipment Class Evaluation, fifty three (53) tanks and/or ! heat exchangers were included as part of the SSEL. All 53 tanks and heat { exchangers were screened out by the SRT. !
- 4.4 Raceways Evaluations The raceway reviews were performed independent of the equipment effort in accordance with the criteria given in the GIP, Section 8. The cable and conduit i raceway review consisted of:
1 i ' (1) plant walkdowns that focused on the inspection of all accessible portions of the installed raceways. The walkdowns were performed on an area basis and documented on area summary sheets. This enabled the SRT to confirm that the as-built details were consistent with the intent of the original 4 design and installation specification (ref 5.2.10) and also to the extent possible, the SRT looked for any seismic performance concerns in accordance with the GlP guidance. The PBAPS design met the inclusion rules set forth in the GlP. (2) an analytical check of selected worst-case supports using a set of Limited Analytical Review (LAR) Guidelines. i The SRT noted that trapeze-type and cantilevered supports were abundantly used as cable tray supports. The trapeze supports were typically 5/8" diameter threaded rods hung from an embedded unistrut or attached to floor beam members. The
~ inspections addressed such items as cable fill, cable ties, tray hold down, support anchorage and raceway spans.
The cable spreading room, which is common for both units and is located in the Turbine Bldg El.150', has an overhead raceway system that is very congested. The cable tray and conduit supports are not accessible and therefore were p) t inspected from the floor only. The SRT spent a significant amount of effort i reviewing existing plant documents before performing the final raceway walkdowns Page 42
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION O to become very familiar with the original design basis. The cable tray supports in this area are of a trapeze-type design with %"- 5/8" diameter rods attached to horizontal unistrut members (in most cases on a swivel). The unistrut members are supported by the bottom flanges of floor beams. Two SRT teams spent a total of 3 days walking down this area. The emphasis of the walkdowns was on GIP guidelines and ensuring the as-found canfiguration matched the design documents. The SRT did not identify any significant deviations from the design documentation and therefore concluded that the raceways in this area met the GlP requirements and thus are screened out. Conduit supports at PBAPS are typically constructed of unistrut members. The SRT during the walkdowns reviewed conduit span lengths and support anchorages. The SRT noted that conduit was well supported. Supports were typically compact and did not support an overabundance of conduits. Supports with long members were typically braced. At several locations, it was noted that some conduits were supported from the HVAC duct support angle with a friction clamp which were incorrectly oriented. Some conduits located in the Radwaste Building elevation 165' were identified as having interaction concerns with the overhead HVAC systems. The SRT identified this area to be an outlier. The area summary sheets which document the Raceway seismic review O ixeo e erthe sat rei#civo oi# att c8 ote. sixtee"('e>cemt'a < tio"- were selected for Limited Analytical Review (LAR). The results of the raceway LAR evaluations have been documented in reference 5.3.5. Fifteen (15) of the LARs met the criteria established in the GIP and are therefore acceptable. One (1) LAR does not meet the GIP acceptance criteria. There is one type of support, a pipe stanchion, that does not meet the lateral load criteria established in the GlP. This type of support for conduit and cable raceways is only used in the Reactor Building, elevation 195 ft. and Radwaste Building, elevation 165 ft. for both Unit 2 and Unit 3. The cable tray and/or conduit is typically supported at the top of the pipe stanchion. The pipe stanchion is typically 7 feet high or higher and is attached to a base plate which utilizes 4 anchor bolts. This type of support is used to carry cable and conduit across a room or corridor and is therefore free standing. There are usually two to four of these supports in series. Based on the plant wide walkdowns and area-by-area review, all locations where these type of supports have been utilized were identified by the SRT. The SRT has judged this type of support to be an outlier and OSVS were generated and are included in Attachment D. Based on the results of the walkdowns and LARs, the SRT has judged that the cable and conduit raceway system at PBAPS Unit 2 and Unit 3 meet the criteria set forth in the GIP with the resolution of outliers for the specific supports identified g above. Page 43
SEISMIC EVALUATION REPORT l FOR PEACH BOTTOM ATOMIC POWER STATION i O 4.5 Hydraulic Control Units i The Hydraulic Control Units were also reviewed by the SRT. The assemblies j include a rack design which supports two small size accumulator tanks, diaphragm j operated and solenoid operated valves, and a pressure switch. The racks are secured to an embedded unistrut with %" bolts. These are typical of the GE BWR { HCUs and are common at most GE plants. Some of the installations vary for l different plants. An evaluation (ref. 5.3.7) was performed which demonstrated that
- the anchorage for the above described design is acceptable. The SRT identified l a concern with the supporting scheme of the overhead attached piping. A large j suspended frame with minimal lateral bracing or moment capacity along the axis i of the adjacent units is used. The SRT could not screen this out. Therefore, the j HCUs for Unit 3 have been identified as an outlier.
4 4.6 Description of Outliers i
- The method contained in the GlP, Section 11.5 was used for the identification, documentation, resolution (or proposed resolution) of outliers.
l ! An outlier is an item of equipment which does not comply with all of the screening i guidelines provided in the GlP. The GIP screening guidelines were used as a LO aeaer'c b i 'cr ev '" tima the ' mic o a" cv c' eaviame"t. A detailed description of each equipment outlier is provided in the attached OSVS j and summarized in Table 4.2-4. Table 4.2-4 contains a Summary of the GIP
- j. equipment class evaluation and summarizes the outliers identified. Attachment D
- contains the list of outliers (OSVS), resolution and/or proposed method of
- - resolution. Generally the same level and requirements for qualification of
- personnel were used for the proposed outlier resolution as were utilized for the USl l A-46 review. Implementation of the resolutions will be per normal plant design
! practices. { ! As stated in Section 4.1, Table 4.1-1 lists the structure (s) and elevations containing
- SSEL equipment that have IRS exceedances over specific frequency ranges. The i equipment located at these elevations generally were classified as outliers since j seismic demand exceeds capacity.
l i The SSEL equipment outliers identified as not meeting the seismic capacity versus i demand caveat were further evaluated in accordance with the special exception j to enveloping of seismic demand spectra per Section 4.2 of the GIP as described i below. The OSVS for these components have been filled out and the outlier j resolution section have been completed stating the outlier has been resolved using i the special exception contained in Section 4.2 of the GlP. i j In-structure response spectra have been developed based on NUREG/CR-0098 i Page 44 i
~
SEISMIC EVALUATION REPORT , FOR PEACH BOTTOM ATOMIC POWER STATION l l O (ref. 5.2.6) for the median rock spectrum anchored at the IPEEE assigned review level earthquake (0.3g pga). For PBAPS, these in-structure response spectra were used to generate realistic, median - centered, in-structure response spectra for use in the USl A-46 program by scaling down the NUREG/CR 0098 based spectra an appropriate amount in accordance with the method described in the GlP, Section
- 11. 4 . 2 . 4 . The results of this evaluation are documented in reference 5.3.4 and resolve these outliers.
The MCCs which were identified as outliers due to anchorage concerns have been ! resolved. Additional walkdowns were performed by members of the SRT to I document in greater detail the actual configuration of base welds and anchors which were previously inaccessible. Evaluations were performed which documented that the components are seismically adequate. l The High Pressure Service Water pumps and Emergency Service Water pumps were identified as having casing and impeller shafts cantilevered greater than 20 feet. An evaluation was performed and documented that these pumps are ; seismically adequate. l Many valves were identified as being outliers due to valve operator eccentricities ; and/or weights which are outside the GIP experience' database. Since the' ! walkdowns, existing documentation was found or new calculations were performed j which document that the valves are seismically adequate. Section 4 of the OSVS i forms (found in Attachment D) indicates the documentation that was used to make this determination for each valve. I Four sluice gate motor operators were indicated to be outliers because the floorstand (yoke) is cast iron. These outliers have been resolved by reviewing the ! seismic analysis for these components which documents that the cast iron components are seismically adequate. Eight battery racks were identified as having batteries which are outside the experience database due to their weight. However, the batteries are seismically adequate since they were qualified to meet the testing requirements of IEEE-344 (1975). The eight RHR heat exchangers were listed as outliers because the anchorage evaluation was not performed. These outliers have been resolved by reviewing design calculations which were performed to account for seismic and hydrodynamic loads. Based on a review of these calculations, the SRT has determined that the heat exchangers are seismically adequate. in addition all outliers were reviewed and were determined to have no significant O impact on the health and safety of the public. There are no outliers that will not be resolved either by analysis or proposed work. Page 45 l 1
i 1 SEISMIC EVALUATION REPORT l FOR PEACH BOTTOM ATOMIC POWER STATION O 4.6.1 Schedule of Resolution of Outilers l Outlier resolutions will be performed in accordance with the schedule provided in the cover letter to this report, i ) i Ninety-two (92) outliers have completed resolutions as documented on the OSVS.
- One hundred and eight (108) outliers are planned to be resolved either by further analysis or plant work. If the analysis does not provide resolution other options will i
. be evaluated. 1 4 4 i 1 , l O Page 46
SEISMIC EVALUATloN REPORT O eon eEaca sorTou Arouic powEn station
5.0 REFERENCES
- 5.1 Codes, Standards and Regulatory Documents
{ 5.1.1 USNRC Generic letter 87-02, Supplement 1, issued May 22,1992. i 5.1.2 Supplemental Safety Evaluation Report No. 2 (SSER No.2) on Rev 2 of the Generic Implementation Procedure (GIP-2), May 22,1992. ' 5.1.3 NUREG-1030, " Seismic Qualification of Equipment in Operating Nuclear Power Plants, Unresolved Safety issue A-46," USNRC, Washington, D.C., ! February,1987. l l 5.1.4 NUREG-1211, " Regulatory Analysis for Resolution of Unresolved Safety Issue A-46, Seismic Qualification of Equipment in Operating Plants," i USNRC, Washington, D.C., February 1987. 4 l 5.1.5 IEEE 344-1975,"lEEE Recommended Practice for Seismic Qualification of l Class 1E Equipment for Nuclear Power Generating Stations," institute of Electrical and Electronics Engineers.1975. l 5.1.6 G.J. Beck, PECO Energy Company Letter to NRC dated September 18, j 1992. "PBAPS Units 2 & 3 Response to GL 87-02, Supplement 1, j Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, USl A-46". t 5.1.7 J.W. Shea (NRC) Letter to PECO Energy Company, dated November 17, 1992. " Evaluation of the PBAPS Units 2 & 3120 Day Response to Supplement 1 to GL 87-02". 5.1.8 G.A. Hunger, Jr., PECO Energy Company Letter to NRC, dated January 24, 1994. 5.1.9 J.W. Shea (NRC) Letter to PECO Energy Company, dated December 1, 1994. "Use of Realistic Median Centered in-Structure Response Spectra for PBAPS Units 2 & 3, Radwaste Building". l U Page 47
, i i SEISMIC EVALUATION REPORT lO FOR PEACH BOTTOM ATOMIC POWER STATION ! 5.2 Technical Criteria and Design Basis Documents } 5.2.1 EPRI NP-6041-SL R1,"A Methodology for Assessment of Nuclear Power j Plant Seismic Margin", August 1991. $ 5.2.2 " Generic implementation Procedure (GIP) for Seismic Verification of Nuclear
- Plant Equipment," Revision 2, as corrected on February 14,1992.
l 5.2.3 PECO Energy, PBAPS Station UFSAR. l 5.2.4 Not used. i l 5.2.5 Not used.
- j 5.2.6 Development of Criteria for Seismic Review of Selected Nuclear Power l Plants, NUREG/CR-0098, U.S. Nuclear Regulatory Commission, i Washington, D.C., May 1978.
5.2.7 " General Project Class l Seismic Requirements . for Equipment, {- Instrumentation, Systems and Components For Peach Bottom Atomic j Power Station Unit 2 and Unit 3," Specification 6280-G-14, Rev.1, Bechtel j Power Corporation, September 1973. 1 i 5.2.8 S & A Report, " ANCHOR User's Guide, 3.0, Rev. 0," Stevenson & ! Associates, Boston, Massachusetts, August 16,1990. 5.2.9 " General Project Requirements for Seismic Design and Analysis of l
- Equipment and Equipment Supports for The Peach Bottom Atomic Power j Station Units 2 and 3", Specification 11187-G-14, Rev. O, Bechtel Power Corporation, July 26,1982.
- j. 5.2.10 Drawing E-1315, " Conduit and Cable Trays, Symbols, Notes and Details".
[ Bechtel Power Corp. 5.3 Evaluation Reports and Calculations i j 5.3.1 VECTRA Report 0067-00084-D003, " Seismic Safe Shutdown Success ] Paths for Peach Bottom Atomic Power Station Units 2 and 3", Revision 0, dated October 26,1995. 4 Page 48 i, a
SElSMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION 5.3.2 VECTRA Report 0067-00084-R002,"USl A-46 Relay Evaluation report for Peach Bottom Atomic Power Station Units 2 and 3", Revision 0, dated October 26,1995. 5.3.3 "Bechtel Cable Tray and Conduit Raceway Seismic Test Program," Volumes I and 11, September,1978. 5.3.4 VECTRA Calculation 0067-00084-C-014, " Capacity versus Demand", PBAPS, Rev. 2, August 25,1995. ' 5.3.5 VECTRA Calculation 0067-00084-C-11, "Umited Analytical Review of Raceways", PBAPS, Rev.1, August 25,1995. 5.3.6 VECTRA Calculation 0067-00084-C-013, " Comparison of Design Basis Spectra to 1.5 Time Bounding Spectra", Rev. O., July 1994. 5.3.7 VECTRA Calculation 0067-00084-C-026, " Hydraulic Control Unit Anchorage Evaluation", Rev. O., October 5,1995. O O Page 49 1
l i SEISMIC EVALUATION REPORT ' pd. FOR PEACH BOTTOM ATOMIC POWER STATION l i ' i l 4 i i i ATTACHMENT A i i RESUMES AND TRAINING RECORDS OF { KEY PROJECT PERSONNEL lO l Richard E. Daniels
- Daniel J. Fiorello James Flaherty il Charbel Abou-Jaoude l Dimitrios Antonopoulos 4
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- RICHARD E. DANIELS l PROFFRSIONAL EXPERIENCE Mr. Daniels is a structural engineer in the Nuclear Engineering Division of PECO Energy Company. He has over twenty-five years of civil and structural engineering experience, of which twenty-one years are in nuclear and fossil power plant structural design and modification. He has also performed engineering for industrial, commercial and
, residential buildings and parking garages. Mr. Daniels is the PECO Energy Lead Responsible Engineer (LRE) for civil / structural aspects of the Peach Bottom Atomic Power Station USl A-46 Program, as well as for the Peach Bottom and Limerick Generating Station Individual Plant Examinations for Extemal Events (IPEEE). He has been trained by EPRl/SQUG and is certified as a Seismic 5 Capability Engineer. In his capacity as LRE for civil / structural aspects of the USI A-46 i and IPEEE Programs, Mr. Daniels nas served as a member of the Seismic Review Team O <ssT).n<evidee eeco emeravtecheic iienettethe ceet< cter eeieei" tec"#ic i review of the various work products. l Mr. Daniels is also the Program Manager for the PECO Energy Dynamic Qualification of ! Equipment Program and the PECO Energy SOUG Representative. As Program Manager for Dynamic Qualification (DO) of Equipment, Mr. Daniels coordinates the activities of engineers and consultants performing various DQ services and is guiding the technological growth of the program. , l Prior duties at PECO Energy have included various civil and structural engineering tasks. l
. Mr. Daniels has designed structural steel and reinforced concrete and investigated issues i associated with their long term performance. He has prepared specifications for 1 anchorage to concrete, construction of scaffolding, grouting of equipment foundations, ;
repair of concrete, grouting of cracks in concrete, and use of temporary lead shielding. l Mr. Daniels developed and presented the concrete technology portion of a technical staff j training program. He reviewed drawings and calculations for commercial-type structures acquired by design / build contracts and observed construction of these facilities to monitor ) conformance to design documents. He has also performed structural analysis using both 1- classical methods and PC-based finite element analysis using Algor /Supersap. Page 1
!n SEISMIC EVALUATION REPORT iU FOR PEACH BOTTOM ATOMIC POWER STATION i l ATTACHMENT A i RICHARD E. DANIELS l j PROFFARIONAl NYDERIFNCE Mr. Daniels has in-depth knowledge of various industry codes and standards, such as ! IEEE 344, the AISC Code, ACI 318, ACI 349, ACI 301, various USNRC Regulatory Guides and the USNRC Standard Review Plan. i From 1986 until joining PECO Energy as an employee in 1990, Mr. Daniels was associated with ASTA Engineering, Inc., who loaned him to PECO Energy. His work l l activities were the same as described above. j
'From 1984 to 1986, Mr. Daniels was employed by A&R Engineering Co., Inc. He was i responsible for design, inspection, and vendor review for various structures utilizing i reinforced concrete, prestressed concrete, reinforced masonry and structural steel. Types
! of buildings included industrial, commercial, and residential facilities and parking garages. He performed condition surveys of precast and cast-in-place parking garages, as well as
- \ other concrete, steel, and wood structures. He also performed third-party design and construction reviews for owners and financial institutions. Clients included a school !
district and a mortgage company. From 1972 to 1984, Mr. Daniels was employed by United Engineers and Constructors, ! !- Inc. J 1 a ; i While assigned to the Structural Group for the Seabrook Station Project, he performed the following functions: I j - Lead engineer and developer for a structural steel design verification program utilizing !
- the STRUDL analysis code and a computerized database for applied loading and
! associated reference data. j j - Responsible engineer for design implementation during construction of sub-sea, j' reinforced concrete circulating water tunnels and pumphouse. He performed design i revisions and interfaced with field engineers and contractors. i - Responsible engineer for ongoing development of concrete and other civil / structural l specifications. He researched requested revisions and interfaced with field engineers ' j to implement changes. He also initiated use of superplasticizers and the maturity 2 method to improve quality of construction and reduce costs. j 2 Page 2 1 i
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- V SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A i
RICHARD E. DANIELS l PROFFARIONAl EYpKRIFNap t i Responsible engineer for. development of structural and civil engineering sections of ! FSAR.
- Prior to the Seabrook assignment,. Mr. Daniels worked on several projects in the 1 l Structural Analysis Group and Mechanical Analysis Group. He performed the following functions
l Lead engineer for development of contractual seismic design criteria for a nuclear ! power plant for a west coast utility. The task included generating representative amplified response spectra for several NSSS vendors who planned to bid on the project. Performed and directed seismic analyses to develop instructure response spectra and design forces. Performed and directed finite element analyses of 3D and axisymmetric structures. Performed non-linear stress analyses and heat transfer analyses. Performed and directed general dynamic analyses using impulsive and other loads. ! Performed and directed dynamic analyses to determine natural frequencies and mode shapes of light and heavy turbine generator pedestals to aid in start-up procedures. Developed structural analysis sections of several PSARs. Developed procedures for design and analysis of nuclear plant structures. Develop user manuals for several in-house computer programs. Used the following computer codes extensively: STARDYNE WILSON 1* STRUDL WILSON 2* O u^so i ) Page 3 i
n SEISMIC EVALUATION REPORT
- U FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A RICHARD E. DANIELS PROFFRRIONAL EYPERIENCE
! *In-house axisymmetric analysis programs initially developed by ! E. L. Wilson of the University of California, Berkley. Developed subroutines for MARC and pre- and post-processors for other programs, using the FORTRAN programming language. j - Structures analyzed include reinforced concrete shear wall buildings, steel frames, concrete containments, reinforced concrete tunnels, gas ducts, buried pipes, turbine generator pedestals, other machine foundations, and pipe rupture restraints. Analyses included complete structures and isolated components. ) From 1970 to 1972, Mr. Daniels was employed by Gannett Fleming Corddry & Carpenter, Inc. He worked as a highway engineer and was involved in development of right-of-way l plans and design of drainage systems for a major urban interstate highway. 4 l' From 1969 to 1970, to pursue his masters degree at Drexel University, Mr. Daniels was , awarded a teaching assistantship and taught soil mechanics laboratory, statics, and ) j dynamics. l j EDUCATION i M.S., Civil Engineering Drexel University, Philadelphia, PA f B.S., Civil Engineering i Drexel University, Philadelphia, PA i REGISTRATION l Professional Engineer in the State of Pennsylvania i i l Page 4 : 1 l 4
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l SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A RICHARD E. DANIELS PROFESSIONAL AFFILIATIONS American Society of Civil Engineers, Fellow American Concrete Institute, Member American Institute of Steel Construction, Member ; Tau Beta Pi Honorary Engineering Fraternity, Member i Chi Epsilon Honorary Civil Engineering Fraternity, Member l i O O Page 5
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SEISMIC EVALUATION REPORT ( FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A DANIEL J. FIORELLO EROFFRRIONAL EXPERIENCE _ Mr. Fiorello is a Senior Structural Engineer for PECO Energy Company's Nuclear Engineering Division. He has over 18 years of nuclear power plant design experience. As a member of the Technical Support Section, he is responsible for various structural and l seismic design / analysis activities which are performed by the Nuclear Engineering Division. He has particular expertise in the analysis and design of plant concrete and steel structures, the analysis of structures for seismic loads, and the generation of design response spectra. Mr. Fiorello is assigned as a member of the Seismic Review Team on the USl A-46 SQUG/IPEEE project for Peach Bottom Atomic Power Station and the IPEEE project for i Limerick Generating Station. Mr Fiorello was the PECO Energy Company's SQUG P representative from 1992 to 1994. He has been trained by EPRl/SQUG/IPEEE and is certified as a Seismic Capability Engineer. Mr. Fiorello also provides technical support for the design of various modifications at i Peach Bottom and Limerick Stations. This support includes the specification of dynamic ! qualification requirements for new equipment, and the review of dynamic qualification reports. This support also incidas the structural aspects of the modification including the l design of supports for new equipment, the analysis of existing structural components for i revised loadings, and the evaluation of concrete components for core bores. Mr. Fiorello was the Responsible Structural Engineer for the Limerick Fuel Pool Rerack Modification. This task included the writing of the design specification and the coordination of the activities of engineers and consultants in the structural reanalysis of the Spent Fuel Pool. Mr. Fiorello is the PECO Energy Company's Subject Matter Expert for the Control of Heavy Loads (NUREG-0612), and Masonry Wall Design (IE Bulletin No. 80-11). Mr. ' Fiorello developed and presented the Heavy Load portion of a technical staff training program. i k Page 8 l
1 SEISMIC EVALUATION REPORT ! O FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A DANIEL J. FIORELLO PROFFREIONAL EXPERIENCE (Cont'd) Mr. Fiorello was the PECO Energy Company's representative on the BWROG Drywell ! (Containment) Inspection Committee. ! Mr. Fiorello was the Lead Responsible Engineer for the preparation of several structural related Design Baseline Documents. Prior to joining PECO Energy Company in 1989, Mr Fiorello was employed by United Engineers and Contractors where he was a staff engineer in the Structural Division. In this espacity he performed seismic and structural analyses for various structures and compents for the DOE Savannah River Project. Mr. Fiorello also prepared the i prelinhary design for a blast resistant reinforced concrete building for a chemical plant. ! Before joining United Engineers and Contractors, Mr. Fiorello was employed by Stone and , Webster Engineering Corporation from 1977 to 1988, where he held several positions from Engineer to Senior Structural Engineer. He was assigned to various nuclear projects including Nine Mile Point Unit 2, River Bend, and Comanche Peak. At Stone and Webster, Mr Fiorello's tasks included the analysis of the reactor building containment structures and various internal structures for the effects of accident loads. The analyses included the use of various finite element computer programs including
'STRUDL' , 'ANSYS' and various Stone and Webster in-house programs.
He also performed seismic analyses for various structures using the response spectrum and time history methods. Tasks included the preparation and use of mathematical models ranging from simple fixed base stick models, to those which included nonlinear soil structure interaction. Design responsibilities included the design of various reinforced concrete structures including the design of the reactor pedestal and fuel pool girders for a Mark ll containment and the drywell and reactor building mat for a Mark lli containment. O Page 9
SEISMIC EVALUATION REPORT p> s FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A DANIEL J. FIORELLO l PROFFARIONAl FYDERIENCE (Cont'd) From 1981 to 1985, Mr. Fiorello was a group leader on the River Bend Project. In this capacity, he was responsible for the supervision of support engineers in the verification of the design of all the concrete structures associated with the Reactor Building. From 1986 to 1988, Mr. Fiorello was assigned to the Comanche Peak Project. In this capacity he was involved in the verification of the seismic response spectra which was used for the project. This effort included the remodeling of the structures and generation l of new amplified response spectra. Mr. Fiorello was then assigned to the position of j responsible engineer. In this capacity, he was responsible for the supervision of support l engineers in the verification of the Reactor Building Containment. This task involved the j development and use of finite element models of the containment shell, foundation mat, ; and areas around penetrations in order to verify that the existing structure could safely ! withstand all design conditions. C_ Fr1UCATION M.S., Civil Engineering, December 1976 University of Pennsylvania, Philadelphia, PA B.E., Civil Engineering (Magna Cum Laude), May 1975 Villanova University, Villanova, PA REnlRTRATION Professional Engineer I in the State of Pennsylvania PROFFRRIONAl AFFILIATION Member - American Society of Civil Engineers l l 1 1 O Page 10 l
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SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A l JAMES A. FLAHERTY l PROFFRRIONAl EYPERIENCE-Mr. Flaherty is a Technical Services Manager of VECTRA's Eastem Region Engineering Mechanics and Systems Division. He has over 25 years of nuclear and fossil power plant i design experience. He is responsible for Project Management and Administrative Control I for structural and mechanical design consulting services. He has particular expertise in i the analysis and design of plant structures and mechanical components including containment vessels, tanks, piping systems and their supports to ASME BPVC Section Ill, Section Vill and Section XI requirements. Mr. Flaherty is the Project Manager for VECTRA work in support of the Individual Plant Examination for External Events (IPEEE), for PECO Energy Company for Peach Bottom Atomic Power Station (PBAPS) and the Limerick Generating Station (LGS) and for the USl A-46 project for PBAPS. He is also the Project Manager for the Public Service Electric and Gas Company's USl A-46 SOUG Program for Salem Units 1 and 2. He has been trained by EPRl/SQUG and is certified as a Seismic Capability Engineer. Mr. Flaherty is the Project Manager for the Boston Edison Company MOV Modifications Plant Design Change Package project. He is also the Project Manager for the Reactor Pressure Vessel Head Torquing evaluation and procedure evaluation at Pilgrim Nuclear Power Station. Mr. Flaherty was the Lead Structural Engineer for the PECo Structural Topical Design Baseline Document for Peach Bottom and Limerick Generating Stations. Mr. Flaherty was the Project Manager for the Pressurizer PORV/SV thermal hydraulic piping reanalysis project for PSE&G Salem Unit 1 and 2. He was responsible for the analyses of Safety and Relief Valve actuation using RELAP4 and the subsequent pipe stress evaluations using VECTRA's SUPERPIPE Program. The objective of this analysis was to demonstrate Safety and Relief Valve Operability under all postulated loading conditions. He was the overall Project manager for the DCP preparation and modifications for draining the PORV and SV loop seals at Salem Units 1 and 2. O Page 13
4 l SEISMIC EVALUATION REPORT !O FOR PEACH BOTTOM ATOMIC POWER STATION 4 ATTACHMENT A JAMES A. FLAHERTY ! 1 ' PROFERSiONAl. FYPFRIENCE (Cont'd) 1 He recently completed a project for PECo that developed the acceptance criteria and l examination requirements program for a BWR Mark I torus subjected to local and global corrosion. l 1
- Previously, Mr. Flaherty was Vice President of Engineering for Altran Corporation. He was responsible for all engineering and design services for outside clients and had overall management responsibility for all of the parent company's engineering activities.
He was responsible for the permitting and design associated with the construction of four , 50 ton per day Cogeneration Medical Waste incinerator Facilities and the conceptual design and technical support activities for a 240 ton per day municipal solid waste cogeneration facility. His iesponsibilities included technical development, site investigation and environmental permitting. He was responsible for selection of the air l( quality control systems and compliance with state and federal regulations. i His duties incluoed consulting engineering services for various fossil and nuclear power ! plant projects. These included failure analysis and recommended repair options for a 4 l million gallon oil storage tank facility, snubber reduction program at a nuclear utility and l l various operability and functionality evaluations for several nuclear power plant systems. I Before joining Altran, Mr. Flaherty was associated with Teledyne Engineering Services from 1968 to 1987. In 1984 he became Vice President with responsibility for all activities performed by Failure Analysis and Prevention Group, Experimental Mechanics Testing and Instrumentation Group and Brewer Engineering Laboratories. 4 Mr. Flaherty was also a Consulting Engineer in the area of pressure vessels and structural components with particular emphasis on stress analysis and the applicability of the ASME Boiler and Pressure Vessel Codes, AISC and Regulatory Requirements. The analysis included the evaluation of heat exchangers, tube-to-tube sheet joints, steam generators, containment shells, ASME Class 1, MC,2 and 3 component evaluation and high pressure closure joints. Various finite element Codes such as ANSYS, STARDYNE, STRUDL, and SAAS have been utilized for heat flow, structural analysis and structural dynamics. O Page 14
SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A JAMES A. FLAHERTY PROFFRRIONAL FYPERIFNCE (cont'd) From 1980 to 1984 he was Manager, Engineering Design and Testing. He had direct ; responsibility for repairs and replacements of nuclear power plant systems and their j components including design, analysis, fabrication and examination requirements. As a i Project Manager, Mr. Flaherty had the overall responsibility for the modifications, design, fabrication and installation of various components under the Mark i Torus Program for Boiling Water Reactors at five nuclear power plants. Mr. Flaherty was the Project Manager for Independent Design Verification Programs at , three nuclear power plants and a member of the review group for Diablo Canyon Program to determine the Adequacy of Construction. Mr. Flaherty has been responsible as the Project Manager and Lecturer of more than twenty seminars for the electric power generating industry in the area of plant modifications and the applications and use of various codes and standards. Seminars l were held in the United States, Germany and Sweden. Subjects presented included: ; vessel design and analysis, component supports design and evaluation, methods of I analysis, Design Specification development and Repair / Replacement / Modifications of components to the rules of ASME Section XI. Mr. Flaherty was also a member of the Welding Research Council, Pressure Vessel Research Committee (PVRC) from 1971 to 1987. As a member of PVRC, he served on the Subcommittee on Elevated Temperature Design and was a member of the Subcommittee of Shells and Ligaments. Mr. Flaherty was also the Project Manager for various analytical and experimental projects. He was responsible for the development of a data acquisition and control system for the investigation of ship stamming in high seas. He was the Program Coordinator for a Fifteen Utility Owners Group for the generic response to the USNRC for IE Bulletin 79-02. The program included the development of a finite element computer code for determining the flexibility of base plates and experimental testing of concrete ' expansion anchor bolt. Page 15
l 1 l O SEISMIC EVALUATION REPORT U FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A JAMES A. FLAHERTY PROFFREIONAL EYPERIENCE (Cont'd) i Mr. Flaherty served as a member of the NRC Review Team for determining the adequacy l of the Comanche Peak Review Team Program Plan for Design. i Earlier in his career, Mr. Flaherty worked for both Avco Corporation of Wilmington, Massachusetts and Unethal-Becker-Eisenberg, Inc. of Boston, Massachusetts. While at Avco Corporation he was an Associate Engineer, Structures, Analytical Mechanics Section, Missile Systems Division. He formulated the necessary computer input for structural re-entry vehicle problems involving thermal, static and dynamic loadings; checking output for critical conditions. He also assisted in preparation of stress reports. At Linethal-Becker-Eisenberg, Inc., Mr. Flaherty's position was that of Structural Engineer. He participated in the design of two shopping centers and an elementary school where he was responsible for overseeing the work of draftsmen, checking and approving shop I drawings. He was also involved in design of structural steel and foundation members. Mr. Flaherty was commissioned a 1 st Lieutenant, United States Army Corps of Engineers. He served as a Project Officer in the Directorate for Data Systems, Lexington - Blue , Grass Army Depot, Lexington, Kentucky. EDUCATION M.S., Civil Engineering Tufts University, Boston, MA B.S., Civil Engineering Northeastern University, Boston, MA Technology Managers Program Babson College, Boston, MA O Page 16
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i-l SEISMIC EVALUATION REPORT !- FOR PEACH BOTTOM ATOMIC POWER STATION ! ) ATTACHMENT A CHARBEL M. ABOU-JAOUDE, P.E. EXPERTISE Mr. Abou-Jaoude is a Project / Service Area Manager in VECTRA's Boston Office, with a broad technical and managerial experience in the power industry. His areas of technical expertise are Structural Mechanics and Seismic Design; he has an in-depth knowledge of various industry codes / standards such as Sections ill & XI of the ASME Code, ANSI B31.1, IEEE-344 and 382, various USNRC Reg. Guides and NUREG Reports, WRC Bulletins, AISC, and ACI-349. He is well versed in the Generic implementation Procedure developed by the Seismic Qualification Utility Group for the resolution of USI-A-46, and the methodologies developed by the industry for the response to Generic Letter 88-20 as < outlined in NUREG-1407; he has completed the SOUG/EPRI sponsored A-46 and Seismic IPEEE training courses and has participated in several A-46/IPEEE walkdowns as an SRT member. Mr. Abou-Jaoude has also participated in Post-Earthquake Investigations at industrial facilities in Califomia. While at VECTRA, he has lead the engineering efforts of various work scopes; his responsibilities have included: Criteria
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development, training and personnel development, project execution, interface with regulators and outside organizations, and overall project management. Currently, Mr. Abou-Jaoude is the Project Manager for the Northeast Utilities A-46 projects (Connecticut Yankee, Millstone Units 1&2). He is also the Project Manager for the IPEEE peer review of the Perry Plant. He is the VECTRA Project Engineer for the ! PECO Energy (Peach Bottom 2&3) IPEEE/A-46 and PSE&G (Salem 1&2) A-46 projects i and an SRT member of the Wolf Creek and Limerick 1&2 IPEEE efforts. At Connecticut i Yankee, Mr. Abou-Jaoude has been instrumental in the successful completion of the project; he has provided cost effective resolutions to a number of outliers, and lead the development of implementation procedures for the procurement of new and replacement i equipment. Mr. Abou-Jaoude is also serving as peer reviewer for A-46/IPEEE efforts at the CP&L plants (4 sites) and the Perry Plant. Mr. Abou-Jaoude was the Assistant Project Manager for the Civil / Structural effort at TU Electric CPSES Unit 2 Project. He had primary management responsibility for the work of 80 engineers in the Electrical Raceways, Seismic Equipment Qualification, and Seismic II/I disciplines. This effort involved the design validation of existing Raceway designs, issuance of new designs, establishing the qualification basis of all BOP Seismic Cat 1 and NSSS C1E equipment, procurement of new and replacement O
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. ~ . . _ _ . __ _ ._ ..__._. _ _ _.._._ - . _ _ -_ _. -. .-_ _ _ . - _ _ _ _ _ _ i SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A CHARBEL M. ABOU-JAOUDE EXPERTISE (Cont'd) equipment, structural evaluation of non seismic commodities using an A-46 walkdown based approach, and field engineering to support the completion and start-up of Unit 2. Prior to his Unit 2 assignment at CPSES Mr. Abou-Jaoude was the Assistant Project Manager for the Secondary Water Chemistry Improvement Project at Consumers Power (Palisades). This project involved modifications to the existing blowdown system, the addition of various equipment items, and the installation of 2000 ft. of piping. The design effort was completed in a period of six months with a peak staff of 40 engineers; the design has been successfully implemented and its operation has provided improvements beyond the plant's initial expectations. in addition to this project he was involved in a number of projects for Consumers Power: He was the Project Engineer for consulting work related to the resolution of 79-14 piping and pipe support issues; he also was the O Project Engineer for a modification to install a reactor head shielding which involved generating the amplified response spectra and performing the seismic analysis and qualification of the lifting ring / shielding structure. Mr. Abou-Jaoude has also worked on a number of piping and equipment qualification l projects for Commonwealth Edison and Northern States Power. He was the Project i Engineer for the development of criteria to evaluate integral welded attachments for Prairie Island; the completion of this effort provided successful closure of an NRC 79-14 issue. Previously Mr. Abou-Jaoude lead a group of 18 engineers, working on the seismic qualification of BOP components, in support of a successful SORT audit for TU Electric's Comanche Peak Station Unit 1. He was responsible for the technical adequacy, budget and schedule of the following scope: Preparation of summary packages and supporting calculations to demonstrate the seismic qualification of storage tanks, heat exchangers, pumps, valves, the diesel generator set, piping, and other electrical components (motors, battery racks, control panels, and instrumentation devices). O Page 21
jO S"'S"'o "v^'u^ " """ "' FOR PEACH BOTTOM ATOMIC POWER STATION . ATTACHMENT A CHARBEL M. ABOU4AOUDE EXPERTISE (Cont'd) l Evaluation of mechanical equipment rerating, under Section XI of the ASME Code, for revised design conditions such as pressures, temperatures, nozzle loads, and or acceleration values (approx. 200 stress reports). Mr. Abou-Jaoude was also involved in the Comanche Peak cable tray hanger design validation effort. He was a group lead responsible for qualifying cable tray systems. This . required detailed dynamic analysis and evaluation of structural members and anchorages.
- He was involved in the development of criteria for modification reduction techniques. He also worked on the dynamic testing of full scale cable tray systems and provided analytical results for correlation with measured test data.
I j Prior to joining ABB Impell, Mr. Abou-Jaoude has worked in the Middle-East on the ! (, construction of several commercial and industrial reinforced concrete buildings. He has also worked as a field engineer responsible for the installation and maintenance of equipment at an automotive refurbishing plant in the United Arab Emirates. EDUCATION l M.S., Civil Engineering, December 1985 University of Michigan, Ann Arbor, Michigan B.E., Mechanical Engineering, July 1984 American University of Beirut. Box 110236, Beirut, Lebanon PROFESSIONAL AFFILIATIONS ] Professional Engineer - State of Connecticut, License No.18527 American Society of Civil Engineers American Society of Mechanical Engineers Tau Beta Pi Honor Society Chi Epsilon Honor Society j 0 Page 22 l i
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l I SEISMIC EVALUATION REPORT gk FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A 1 DIMITRIOS ANTONOPOULOS Technical Lead Engineer Civil / Structural 1 l PROFFRRIONAl EYPERIFNCE Mr. Antonopoulos is a Technical Lead Engineer with VECTRA Technologies and has over , twenty (20) years experience in structural engineering analysis and design of nuclear power, industrial and commercial facilities. He is responsible for supervising a staff of , twelve engineers for stiactural and mechanical consulting services. He has particular expertise in the analysis and design of plant concrete and steel structures, including
- vessels, foundations for various equipment, seismic equipment qualification and support i of piping systems in accordance with applicable industry codes. Mr. Antonopoulos is also 3
assigned as a member of the Seismic Review Team on the USI A-46 SOUG and IPEEE projects for Northeast Utilities and PECO Energy Company. He has been trained by gj EPRl/SQUG/IPEEE and is certified as a Seismic Capability Engineer. Mr. Antonopoulos is currently the Project Engineer for the PORV/SV piping system Design Change Package project for Public Service Electric and Gas Salem Units 1 and
- 2. This project addresses issues associated with PORV and SV actuation in response to NRC concerns identified in NUREG-0737 (ll.D.1). In addition, he is involved as the
; Lead Structural Engineer with the Digital Feedwater and Annunciator projects for Salem Units 1 and 2. He is responsible for the overall structural support, including equipment qualification for the various plant design change packages. On previous assignments he was involved as the Lead Structural Engineer with the Control Room lighting modification projects for Salem Units 1 and 2. The projects included an analysis and design of a temporary work platform for replacing existing light fixtures in accordance with NUREG-0700 requirements, and support of the new light fixtures. The design was performed for deadweight, live and seismic inertia effects, in accordance with PSE&G Seismic 11/l Program. The ANSYS computer code was utilized to develop and analyze static and dynamic finite element models for the platform.
O Page 25 i
1 2
' SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STAT 12M ATTACHMENT A DIMITRIOS ANTONOPOULOS PROFESSIONAL EXPERIENCE (Cont'd)
Mr. Antonopoulos was assigned to Niagara Mohawk Power Corporation Nine Mile Point Unit 1 Design Basis Reconstitution Program project where he prepared the Design Criteria Document (DCD) for plant reinforced concrete structures. Mr. Antonopoulos was assigned to Ohio Edison's Niles Generating Station DOE WSA-SNOX Demo Plant Project as a Lead Senior Structural Engineer. In this capacity, he was responsible for the design of foundations which supported duct towers, high RPM fans, tanks, and various equipment / buildings. The STAAD-Ill structural program was utilized in the analysis and design of spread footings, mats and pile cap foundations. Mr. Antonopoulos was assigned to BECo's Pilgrim Nuclear Power Station Salt Service Water Pump Evaluation Project. The evaluation was performed for deadweight, internal pressure and seismic inertia effects in accordance with the requirements of ASME BPVC Section Ill. The ANSYS computer code was utilized to develop and analyze finite element models for the vertical pump columns and the flanged column section region. Mr. Antonopoulos was assigned to GPUN Three Mile Island Unit 1 skew loaded clam evaluation project as a Lead Support Engineer. Employing the finite element method and utilizing ANSYS the skewed pipe clamps were evaluated for non-standard load application and checked against sliding. Similarly, the stresses in the pipe wall induced by a lug were evaluated. This project successfully demonstrated that 58 skewed pipe clamps l were acceptable and field modifications were avoided. Mr. Antonopoulos was assigned to Niagara Mohawk Power Corporation Nine Mile Point Unit 1 Project where he was involved in numerous pipe support evaluations to support plant restart. Prior to joining VECTRA, Mr. Antonopoulos was employed by Cygna Energy Services where his experience included an assignment as Group Leader for the pipe support and baseplate analysis and design effort for the Vermont Yankee Nuclear Power Plant. In this capacity he was responsible for the supervision of a staff of 20 Page 26
f O SElSMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION I j ATTACHMENT A ! l l DIMITRIOS ANTONOPOULOS j 1 PROFESSIONAL FYDERIENf5 (f' ant'd) l engineers involved in the analysis and design effort. He was also responsible for the development of work instructions and design criteria, and for setting specifications for the L design of special purpose software for pipe support analysis. Mr. Antonopoulos was assigned to Boston Edison Civil / Structural Group for over a year as a resident engineer providing engineering support on various PDC packages. In . addition, he was responsible for writing and/or revising engineering specifications dealing with painting, grouting and miscellaneous fasteners, l i Mr. Antonopoulos was responsible for performing analysis and design of upper internals storage cask for Northern States Power Prairie Island Units 1 & 2. The cask was designed to meet radiation shielding and NUREG-0612 requirements. The cask was of l O cylindrical shape and was used for transporting the upper internals of the reactor vessel from the reactor building to its permanent location at the plant site for long term storage. { l l Mr. Antonopoulos was also responsible for performing analysis and design of IDNS RAGEMS facilities for CECO's Dresden, Quad Cities and Zion Plants. The steel facilities were designed for wind and/or seismic loads in accordance with the requirements of the UBC code and were supported by the roofs of existing structures or the ground which involved design of footings and slabs on ground. Mr. Antonopoulos was responsible for interfacing with the architect to produce all necessary specifications and architectural details as well as interfacing with HVAC and electrical groups to bring the project to its successful completion. Mr. Antonopoulos was also responsible for performing analysis of postulated reactor vessel and upper intemals load drops for NUREG-0612. This work was performed for l RG&E's Ginna Plant and it involved finite element models using ANSYS, and both elastic l- and plastic analyses. This project successfully demonstrated that these drops were acceptable and expensive crane modifications were avoided. l O Page 27 l l
l SEISMIC EVALUATION REPORT O FOR PEACH BOTTOM ATOMIC POWER STATION l ATTACHMENT A DIMITRIOS ANTONOPOULOS l PROFFRRIONAL EYPERIFNCE (Cont'd) in an earlier assignment, Mr. Antonopoulos served as Assistant Project Engineer for the ; reanalysis of masonry walls for 1.E. Bulletins No. 80-11 for Millstone Unit 1. On this ! project he was responsible for various phases of the analysis and modification design effort. In addition, Mr. Antonopoulos supervised the field effort for installing the blockwall l modifications. Mr. Antonopoulos on three occasions was loaned to area engineering firms were he performed structural engineering analysis and design of industrial facilities (General ' Motors, Paint Shop in Framingham, MA) and various high rise commercial buildings. Mr. Antonopoulos has been involved in structural analysis and design at Stone and Webster Engineering Corporation. Responsibilities on various projects included analysis and design of reinforced concrete structures, pipe rupture restraints, equipment supports, embedded plates for pipe rupture restraints, pipe supports, cable tray and conduit supports. His project assignments included Beaver Valley Unit 2, North Anna Unit 1, Shoreham, Montague, and Nine Mile Point Unit 2. As a Senior Engineer in the Structural Division, Mr. Antonopoulos was relied upon to prepare structural designs for some of the more complex plant buildings. In particular, he was responsible for the analysis and design of the fuel handling structure which contained the spent fuel pool for the Beaver Valley Unit 2 Nuclear Station. This project involved 3-D finite element modeling for dead, live, wind, tornado, seismic and thermal loadings. He was responsible for all phases of the production effort including analysis, design and drafting. EDUCATION M.S., Structural Engineering Northeastern University, Boston, MA B.S., Civil Engineering University of Massachusetts Dartmouth, North Dartmouth, MA O Page 28
5 4 i l I n SEISMIC EVALUATION REPORT i lV
- FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A DIMITRIOS ANTONOPOULOS 1
I REnlRTRATION i l
- Professional Engineer in the States of Massachusetts and Rhode Island PROFFARIONAL AFFILIATION !
I ' l Member - American Institute of Steel Construction j ! Member- American Concrete Institute l l I l l 4 4 i
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SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION O ATTACHMENT A PETER GUGLIELMINO PROFFARIONai NYDERINNNF Mr. Guglielmino has over 23 years experience in the nuclear industry with expertise in:
. Project Management . . Business Development . Seismic Design . Structural Mechanics . Mechanical Engineering . Technical Training Presently he is the Business Area Manager for VECTRA Atlanta Engineering Mechanics Service Area, responsible for developing, selling and providing " VECTRA Smart" solutions to our client's current and future problems and issues. Most recently he served as the Project Manager for the Resolution of Unresolved Safety issue (USI) A-46, Project for Connecticut Yankee Millstone 1 and 2 and for VECTRA work in support of the Individual Plant Examination for External Events (IPEEE) program for PECO Energy Company's O- Limerick Units 1 and 2. He has completed the SOUG/EPRI sponsored training for USl A-46 and IPEEE programs, and the EPRI sponsored Seismic Fragility Training Course.
He has participated in A-46/IPEEE walkdowns as an SRT member. Mr. Guglielmino was also Client Manager responsible for all aspects of client relations including business development. Prior to joining VECTRA, Mr. Guglielmino worked for Cygna Energy Systems as a Client Manager where he was responsible for all aspects of client relationships, including technical management, project management, business development and contracts. The following projects were secured and managed by Mr. Guglielmino:
. Implementation of Regulatory Guide 1.97 Modifications at J.A. FitzPatrick Nuclear Power Plant . Engineering and Design of Containment isolation Provision Upgrada, J.A. FitzPatrick Nuclear Power Plant . Seismic Qualification of the Reg. Guide 1.97 Instruments and Control Room Panels at TMI-1, utilizing In-Situ Testing and Dynamic Analysis ,
Page 32
SEISMIC EVALUATION REPORT j FOR PEACH BOTTOM ATOMIC POWER STATION O ATT4csusNT4 i PETER GUGLIELMINO
- PROFESSIONAL EXPERIENCE (Cont'd) l
- Appendix R Upgrade Associated Armor Cable Support,J.A. FitzPatrick Nuclear Power l Plant Valve Limitorque Motor Operator Sizing and Setpoint Calculations, J.A. FitzPatrick Nuclear Power Plant Failure Analysis of the Control Rod Drive Mechanism (CRDM) Cooling Fans, Indian 4
Point Unit 2
. Feasibility Study of the CRDM Cooling System, Indian Point Unit 2
- Piping Database Phase 2 and 3, Indian Point Unit 2 Seismic Evaluation of the Service Water Pumps at Indian Point Unit 2 O(/ As Manager in the Structural Mechanics Department, Mr. Guglielmino had administrative
, and technical responsibility for the department including staffing, planning budgeting, salary, administrative and marketing. As Section Manager he provided full support to the Engineering Mechanics Department . in the areas noted above. Some examples of direct involvement included:
. Equipment structural evaluation and failure analysis of the Traveling Water Screens for Salem Nuclear Generating Station
! - Evaluation of hot shutdown piping systems using PVRC damping criteria (Code Case l N-411) and peak shifting criteria (Code Case N-397), Yankee Rowe l
. Development of analytical techniques, test methods and acceptance criteria for the
- seismic evaluation and qualification of safety-related cable tray support systems i
! . Development of Cygna's generic approach to snubber reduction
. Development of Cygna's generic approach to nuclear plant life extension
. Pipe support upgrade analysis to meet the requirements of NRC IE Bulletin 79-02, (7
U Three Mile Island, Unit 1 4 Page 33
SElSMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A PETER GUGLIELMINO PROFESSIONAL EXPERIENCE (Cont'd) Seismic qualification of safety-related small bore piping using combined in-situ testing and analysis methods, Yankee Rowe i Application of Code Case N-411 on selected piping systems to determine benefits and i effectiveness in reducing snubbers at Three Mile Island Nuclear Station, Unit 1 ! l ASME Code Section lil, Class I analysis of in-line components, Limerick Generating Station, Units I and ll Prior to that, Mr. Guglielmino was an Engineering Supervisor who functioned as project engineer for the Analysis and Qualification of the Instrument Racks at Commonwealth Edison's Dresden Units 2 and 3, and Quad Cities Units 1 and 2; as project engineer for ! the Equipment Seismic and Hydrodynamic Requalification Project for WNP-2; and as project enginaer for a series of equipment qualification tasks for Copes-Vulcan and the I Zion Nuclear Power Station. Mr. Guglielmino provided key leadership in the development of Cygna's generic Equipment Qualification Program as well as contributed to the development and implementation of a piping system analysis and design training program for VEPCo. ! He was also responsible for developing the design criteria and analytical methodology for the re-evaluation of safety-related masonry walls at Unit 1 of the Millstone Nuclear Power Station and providing technical supervision to a staff of 25 engineers assigned to the project. Mr. Guglielmino also participated in a cable tray scoping study for the Surry Nuclear Power Station, Units 1 & 2, which determined the potential applicability of NRC Information Notice 80-21 and response strategy. I Prior to joining Cygna, he worked for Stone & Webster where he supported the Engineering Mechanics Division working on a full range of engineering and field problems for nuclear power plants, including the seismic qualification of cable tray and cable tray support, ar:alysis and design of supports for safety-related equipment, and stress ' evaluation of piping nozzles for category i vessels. Other duties included the review and approval of vendor seismic qualification reports, preparation of technical input for purchase specifications and SAR submittals and the resolution of various problems O associated with installation and constructability of equipment supports. Page 34
i SEISMIC EVALUATION REPORT { FOR PEACH BOTTOM ATOMIC POWER STATION
- O ATTACHMENT A
- PETER GUGLIELMINO FnUCATION
. M.S., Civil Engineering ] Northeastern University, Boston, Massachusetts B.S., Civil Engineering Northeastem University, Boston, Massachusetts l l i
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i l j SEISMIC EVALUATION REPORT i FOR PEACH BOTTOM ATOMIC POWER STATION O ATTACHMENT A
- MIGUEL A. MANRIQUE l PROFFRRIONAl FYpERIFMcF-
- Mr. Manrique is a Technical Manager and has over fifteen years of experience in civil l structural and earthquake engineering. He has acted as project manager, project i engineer or technical consultant on numerous projects dealing with structural analysis and design of power plant structures, DOE and industrial facilities. He has performed
- standard and specialized dynamic linear and non-linear analyses using state-of-the-art
! methods. He has performod and been responsible for structural evaluations and design ! qualification of reinforced concrete and steel structures, and has developed seismic 1
- design criteria for new and existing power generating facilities. Mr. Manrique has '
i performed or directed seismic analyses for over 20 nuclear facilities in the US and ! l abroad. He has performed post-earthquake investigations of power generating facilities, l and was the principal investigator on an industry-sponsored study to correlate actual ! j versus predicted earthquake responses of power plant structures. He is fully familiar with i DOE orders and standards, particularly those dealing with natural phenomena analysis . ! (DOE Order 5480.28 and related Standards; Doe-STD-1020, DOE-STD-1021, DOE-STD- l I 1022), DOE Order 6430.1 A, and those dealing with Safety Analysis (DOE Order 540.1 B, j j' DOE Order 5480.23, DOE Order 5481.1B). ! l Mr. Manrique is currently supporting the development of the Final Safety Analysis Report (FSAR) for the Hazardous Waste Management (HWM) facilities at the Lawrence
- Livermore National Laboratory (LLNL).
1 Mr. Manrique is Project Engineer on the implementation of Unresolved Safety Issue A-46 l: and the Individual Plant Examination for Extemal Events (IPEEE) programs for PECO l Energy Company's Peach Bottom Units 2,3 and Limerick Units 1,2. He has completed i the SOUG-sponsored training for A-46 and IPEEE programs and is a member of the
- Seismic Review Team (SRT) for the IPEEE seismic capability walkdowns for Limerick 1, j 2 and Wolf Creek nuclear plants. He has developed HCLPF capacities for components j and structures as part of these efforts.
Mr. Manrique was an independent third party reviewer for the structural design and
- analysis of the large reinforced concrete underground waste storage facilities constructed l by the Department of Energy at the Richland, Washington site. The review encompasses j design criteria development, criteria implementation and design adequacy verification.
l Project Engineer responsible for the containment overpressure evaluations for Salem Units 1 and 2 (PWR), and Hope Creek (BWR) nuclear plants required as part of the US y NRC's IPE internal events program. He also reviewed the seismic fragilities and high confidence low probability of failure (HCLPF) calculations in support of the ! Page 37
i SEISMIC EVALUATION REPORT i FOR PEACH BOTTOM ATOMIC POWER STATION ' i
- O ATTACHMENT A l MIGUEL A. MANRIQUE
! PROFESSIONAL EXPERIENCE (Cont'd) ! Probabilistic Risk Assessment (PRA) performed as part of the Diablo Canyon's Long l Term Seismic Program.
- Project Engineer responsible for all civil / structural project activities required for completion j of Comanche Peak Steam Electric Station, Unit 2. Mr. Manrique's responsibilities j included production activities, providing technical direction, client interface, cost and
!' schedule control and interface coordination with field engineering and construction support j groups. Technical responsibilities _ included development of design packages, design l verification and qualification of all Unit 2 reinforced concrete structures, embedded plates, structural steel structures, containment liner, containment penetrations, tanks, etc. Project Manager for the seismic analysis of Combustion Engineering's Advance Light Water Reactor System 80+ design. The work involves performing soil-structural interaction analyses using various generic site profiles and seismic criteria. This work was performed in support of DOE's program to obtain NRC's design certification of the O next generation of nuclear reactors. Mr. Manrique performed engineering evaluation of unanchored liquid storage tanks for a large chemical production facility in California. The objective of these evaluations was to determine potential failure mechanisms that could induce a catastrophic failure, i.e.,: instantaneous release of tank contents. The work involved review of the tanks' original design (the tanks were built in the 1950's and 1960's), review of their operating history, review of materials properties and welding procedures and assessed the potential failure modes associated with a major seismic event. Assistant Project Manager for the cable tray and conduit raceway supports evaluation and qualification scopes at the Comanche Peak Steam Electric Station. Project Engineer for the in-structure response spectra development for the Comanche Peak Steam Electric Station. Mr. Manrique was responsible for development of criteria and implementation through detailed project guidance. Mr. Manrique was also responsible for interfacing with external third-party review organizations, preparing technical position papers for submittals and presentation to the NRC. Project Manager for the Lotung Large Scale Seismic Experiment, sponsored by the Electric Power Research Institute. The project's objective was to assess the methods O used by the industry for seismic analysis. The results of this project have been used to make recommendations to the technical community, licensing and regulatory agencies as to the adequacy and improvement of methods for seismic analysis. Page 38
~_. . _ _ _ _ -
SElSMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION iO ATTACHMENT A MIGUEL A. MANRIQUE i PROFESSIONAL EXPERIENCE (Cont'd) l Mr. Manrique has performed independent reviews of the seismic analysis and i development of floor response spectra for the Department of Energy N-Reactor facility. This included review and assessment of the analysis assumptions and procedures to ensure that they were adequately implemented and in accordance with accepted industry practice. Project Engineer for the Long Term Service Seismic Evaluation Program for the San Onofre Nuclear Generating Station. Mr. Manrique implemented the overall analysis approach and made presentations to the NRC and its consultants for its approval and licensing. Project Engineer for the structural evaluations of the Department of Energy N-Reactor , (Richland, Washington) facility. Mr. Manrique directed efforts associated with the l generation of artificial time histories, model development for various N-Reactor structures ! and the generation of the input for the reactor core nonlinear evaluations. Seismic analysis of the Reactor Building in Millstone, Unit 1 for Northeast Utilities. ; Project Engineer for the seismic response analyses of Category I and major non-Category I I buildings for the Hope Creek Generating Station. The analyses results were used for the design of the plant structures, systems and components. Project Engineer for the soil-structure interaction analysis of a BWR Reactor Building for Toshiba Corporation (Japan). Project Engineer for the confirmatory soil-structure interaction analysis for the GESSAR ll BWR standard plant for General Electric Company. Project Engineer for the generic evaluation of the damage potential of small, high-frequency earthquakes on the passive systems, equipment and components in a nuclear power plant for the V.C. Summer Station. Performed linear and nonlinear dynamic anclyses to evaluate the adequacy of operating PWR plants for postulated loss-of-coolant accident (LOCA) loads. Mr. Manrique developed and analyzed models for highly loaded reactor containment shear walls. The nonlinear evaluations considered the nonlinear behavior of reinforced concrete structures. O Development and review of design margins for piping systems at Comanche Peak Steam Electric Station for Texas Utilities Electric Company. Page 39
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION t i ATTACHMENT A ! i ! MIGUEL A. MANRIQUE i ! PROFESSIONAL EXPERIENCE (Cont'd) , I Review of seismic design criteria for non-nuclear facilities for Pacific Gas & Electric ] Company. l Performed analysis and redesign of steel structures for hydrodynamic loads associated i with loss-of-coolant accident (LOCA) loads.
- FnUCATION-l B. S. - Civil Engineering, University of Rhode Island,1976 M. E. - Structural Engineering and Structural Mechanics, University of California,
{ Berkeley,1979 ) i PROFESSIONAL CEf!TIFicATIONR/RFalRTRATIONR/cl FARANOFA-j - Registered Professional Engineer, State of California, C038457 Member, American Society of Civil Engineers i Member, ASCE Dynamic Analysis Committee
- Structural Engineers Association of Northern California j Earthquake Engineering Research Institute Tau Beta Pi Engineering Honor Society !
RPFol Al 17Fn TR AINING- )
" Seismic Qualification Utility Group Training Course for Implementation of the Generic !
Implementation Procedures in the Resolution of US NRC USl A-46", sponsored by the i Seismic Qualification Utility Group, September 1992. I
" Add-on Seismic IPE Training Course", sponsored by the Seismic Qualification Utility Group, October 1992.
" Fragility Evaluation for Probabilistic Risk Assessments for Nuclear Power Plants",
sponsored by North Carolina State University, December 1992.
" Seismic Design of Highway Bridges Training Course", University of California, Berkeley, March 1992.
Page 40
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION O ATTACHMENT A t-SING CHU PROFESSIONAL EXPERIENCE Mr. Chu is a Senior Engineer in the Engineering Mechanics Services Area of VECTRA's Boston Office. He has nine years of experience in areas of seismic engineering, systems engineering, design baseline documentation, cost and scheduling, computers, and emergency preparedness. Systems Engineering NUSCO - Presently Mr. Chu is involved in the NRC's Unresolved Safety issue (USI) A-46
" Seismic Qualification of Equipment in Operating Plants" for Millstone Units 1 & 2.- His responsibilities include equipment and relay screening verification and walkdown, and outlier identification and resolution. Mr. Chu is also responsible for all GlP databases' control and maintenance. All tasks are performed in accordance with the SQUG,~
" Generic Implementation Procedure for Seismic Verification of Nuclear Plant Equipment" with Stevenson & Associates GIPPER software v2.03.
Mr. Chu is also assigned as a member of the Seismic Review Team on the USI A-46 SOUG and IPEEE projects for NUSCO and PECO Energy Company. He has completed training by EPRl/SQUG/IPEEE and is certified as a Seismic Capability Engineer. PECO Energy / PSE&G - Mr. Chu is also involved in USI A-46 and IPEEE projects at Peach Bottom Atomic Power Stations and Salem Stations. NUSCO - Staff augmentation for Seismic Equipment Qualification at Connecticut Yankee and Millstone Unit 1. Responsible for seismic qualification activities associated with new replacement equipment such as electrical instrument and cabinets, mechanical components, and valves, etc.. Staff augmentation for High Energy Line Break HELB at Millstone Unit 2. Responsibilities included identifying all high energy lines within the plant, documentation and drawing search, plant wide walkdown, developed / maintain HELB databases, and generated final calculations. Project team member for Connecticut Yankee A-46 project, final NRC report submitted 12/93. Responsibilities included equipment / relays walkdown, evaluations, and final report generation. i. Page 41
SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A SING CHU PROFESSIONAL EXPERIENCE (Cont'd) FPL - Mr. Chu functioned as an engineer in support of the As-Built In-Service inspection Project. In this capacity, Mr. Chu performed field walkdowns and generated engineering calculations to qualify noncompliance to the existing field conditions. Structural and stress analyses were performed by using STAAD 111 and MATHCAD. Design Baseline Documentation PECO Energy - Mr. Chu developed the 480 Volt Load center and the 480 Volt Motor Control Center Design Baseline Documents (DBDs) for both PBAPS and LGS. His duties included researching the system design, modifications, plant specifications, and licensing documents. Mr. Chu was also responsible for writing draft and final sections of the DBDs ensuring technical accuracy and completeness in accordance with PECO Energy requirements. Cost and Scheduling NMPC - Mr. Chu served as the Financial Administrator to the Nine Mile Point Units 1 & 2 engineering mechanics project. Mr. Chu's other responsibilities were as follows: Assisting in setting up Structural Evaluation System (SES) database for the Seismic Upgrade Program, Translate NUPIPE-SW piping models to SUPERPIPE using the same geometry, material properties, support configuration, and boundary conditions. Established and maintained databases for the NMPC Maintenance Walkdown/ISI and 50.59 program. I Emergency Preparedness NMPC/LILCO - Mr. Chu was involved in the development of the NRC exercise and emergency preparedness drill scenarios for NMPC's Nine Mile Point Unit 2. He also l reviewed and developed LILCO Shoreham Station's 1988 FEMA /NRC graded exercise. In both capacities, Mr. Chu's main task was to generate drillinformation based upon raw data input. NHY - Mr. Chu was assigned to New Hampshire Yankee's _Seabrook Station as a document / production controller. Helping establish and track the completion of several ' hundred open items to revise the New Hampshire Radiological Emergency Response . Plan. He has also provided input to assist in completing Seabrook's Offsite Emergency I Plan. 1 Page 42
SEISMIC EVALUATIOl4 REPORT FOR PEACH BOTTOM ATOMIC POWER STATION
- >O ATTACHMENT A i SING CHU PROFFRRIONAl EYPERIFNCF (Cont'd)
J Subsequent to this assignment, Mr. Chu was assigned to ABB Impell's Plant Engineering Division to assist in completing Niagara Mohawk's Nine Mile Point Unit 1 pipe hangers j and supports analysis using CAD and CAEMIS (Computer Aided Engineering Management Information System). Duties included generating support and hanger drawings using CAD, creating mathematical model, and running analysis per set requirements. Prior to joining ABB impell Corporation, Mr. Chu worked as an electrician aide for a large electrical contractor.
- EDUCATION
! B. S. Aerospace Engineering Polytechnic University, Farmingdale/ Brooklyn, New York l TRAINING COURAFR ! - SOUG USl A-46 Walkdown Screening and Seismic Evaluation Training Course, ; Nov.1992
- EPRI IPE Individual Plant Examination of External Events Seismic Margin l t
Assessment Training Course, Dec.1992 i
- Stevension & Associates SOUG Generic Implementation Procedure GIPPER ;
4 computer program training course, Nov.1992
- EPRI STERI Training Seminar - Seismic Technical Evaluation of Replacement
- Items in Nuclear Power Plants NP-7484, Jan.1995 HONORS AND AFFILIATIONS m
Who's Who Among Students in America Universities and Colleges REnlRTRATION Engineer in Training, New York Page 43 i
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} SEISMIC EVALUATION REPORT j FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT A i STEPHEN P. RflCHLE PROFFARIONAl FYpKRIFNOP i i Mr. Reichie has over 20 years of power plant engineering, design, maintenance, and
- operations experience. As Technical Services Consultant for Mechanical Systems in l VECTRA's Boston office he is currently assigned as the Project Manager for the Fire Hazards Analysis (FHA) project for the New York Power Authority. This project consists of updating the FHAs for both the James A. FitzPatrick and Indian Point 3 nuclear plants.
The project also includes the preparation of an analysis that assesses the effects of pipe rupture, inadvertent actuation and manual use of fire protection systems on safety-related j equipment at JAF and IP3. l Mr. Reichie is also currently serving as the Systems Project Engineer on the NRC's
- Unresolved Safety Issue (USI) A-46 projects for: Northeast Utilities (Millstone 1,2 and i Connecticut Yankee), PECO Energy Company (Peach Bottom) and Public Service j Electric & Gas (Salem). In this role, he is responsible for the identification of safe
- shutdown paths and the development of a Success Path Component List for each unit.
These NRC programs deal with the seismic adequacy, or margin of equipment in operating plants. Previously, Mr. Reichle served as the Project Manager for the Appendix R Compliance
- Program and Fire Barrier Upgrade Projects at the Pilgrim Station. Mr. Reichle managed these programs for over two years, with tasks including the development of Appendix R shutdown analyses, the development of associated operating procedures, the review and
, upgrade of all Appendix R fire barriers, and the design of various electrical and
- mechanical system modifications. This project was staffed with approximately 25 engineers and technicians.
Mr. Reichle served as the Project Engineer, and managed the engineering resources, . during the update of the J. A. FitzPatrick Fire Protection Reference Manual, and i supported the update of the Fire Protection Program Manual for Indian Point Unit 3. Both of these projects involved the update of fire protection and Appendix R programs to . Include the changes made by modifications, and the preparation of a new manual that included both programs. !o Page 46 ]
i 2 ~! . SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION ] ! ATTACHMENT A STEPHEN P. RElCHLE FYpERIENCE (cont'd) 3 Mr. Reichie also served as the Project Engineer for an Appendix R project for Northeast
- Utilities Millstone 3 Nuclear Power Plant. This project consisted of four major tasks
- 1) review the plant's safe shutdown methodology and equipment list to ensure completeness
- 2) identify which components might be affected for each fire area,3) identify the worst case fire scenario (in terms of equipment loss) for each fire area, and 4) identify and prioritize the operator actions that need to be taken in each fire area. !
Prior to this assignment, Mr. Reichle performed a design baseline verification cf the Emergency Operating Procedures (EOP) for Nine Mile Point 1, and determined the impact of operating safety related systems with normally open manual valves at the system's O interface with non-safety related portions of the system. His responsibilities on these projects included the preparation of verification packages to document design basis of input parameters to EOP flowcharts, preparation of various design calculations, and preparation of a report on the boundary valves. Also included within this project was a review of the plant's Service Water System and the effect of increased lake water temperature. Mr. Reichle has also served as a technical specialist in support of triennial fire protection audits at the H.B. Robinson, Brunswick and Sheeron Harris nuclear power plants. During these audits, he served as the Systems Engineer reviewing station operating practices, programs and procedures used to ensure safe shutdown of the plants in the event of a fire. Mr. Reichie has prepared Design Baseline Documents (DBDs) for the feedwater and fire protection systems at the PECO Energy Peach Bottom and Limerick nuclear plants. This project consisted of conducting the necessary research to identify the boundaries, interfaces and requirements of the individual systems. The documents also describe how each of the systems satisfies their design input and output requirements, and what modifications have impacted the system's original design basis. Mr. Reichie also participated in the Appendix R update project for the Limerick
..O Page 47
i !O SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION 1 ATTACHMENT A ' l i . STEPHEN P. REtCHLE ElfpERIFNCE It' ant'd) i { Nuclear Station by reviewing the new and updated shutdown methods identified for each ! fire area, and assisting in the resolution of shutdown concerns identified during the review process. Mr. Reichle has also served as the Project Manager for the single failure analysis of the ECCS sub-systems, and their support systems, for the Connecticut Yankee plant. This project included the identification and review of potential equipment failures for each of the systems, including mechanical, electrical and instrumentation, during injection and l recirculation modes in response to a LOCA. l O im co#iemctio# ith the bev ieai-<i'er iv . < vi o'the cv procedures was performed. This review was conducted to ensure that all ECCS
#< iii "c-redundant or required components were included in the appropriate procedure, and that ;
proper surveillances were being performed to asrJre operability of the systems. ' Prior to joining VECTRA, Mr. Reichle was a Senior Engineer at Cygna Energy Services and assisted in the preparation of the Appendix "R" review for NUSCo's Millstone 1,2 and Connecticut Yankee generating stations. As a member of this project, he was assigned tasks such as developing safe shutdown scenarios and identifying equipment which needed to be protected, establishing safe shutdowr; fire areas, performing walkdowns of fire areas to verify the adequacy of existing barriers (including doors, dampers, and penetration seals), identifying barrier deficiendes, preparing justifications for exemption requests, and making recommendations for upgrading fire barriers or their penetrations to the required fire resistance rating. Mr. Reichle also participated in preparing a conceptual design of a seismic hot shutdown , system for the Yankee Rows Nuclear Plant. This project reviewed the feasibility of providing a standby, portable pumping system made up of standard commercial grade i components, that would deliver water to the steam generators and/or main coolant system in the event no other method was available. Included in this project was the identification system demands, sizing of components, identification of water sources, and providing an estimated cost to install the system. Page 48
l r l L SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION i i ATTACHMENT A l STEPHEN P. RElCHLE j FYDERIFNcp mant'd) { . In a previous assignment, Mr. Reichle served as Lead Engineer for the development of i- surveillance and maintenance procedures for the Shoreham Power Station. His responsibilities included the identification of maintenance and inspection requirements for , all mechanical balance of plant equipment. He established the parts requirements, i special tools, rigging and handling instructions for those procedures. Mr. Reichie also i supervised additional tasks for the Shoreham Station including:
- Development of Fire Protection Program Description and Associated Procedures ,
- Development of Maintenance Program Description i
- NUREG-0612 Heavy Loads Analysis, and Procedure Preparation 4
p-
- Preparation of Refueling Procedures
- Design, Analysis, and Fabrication of Fuel Handling and Reactor Head Strongback j Before joining Cygna, Mr. Reichie held the position of Lead Applications Engineer for the Jamesbury Corp., a manufacturer of fluid control equipment. His responsibilities included l supervising technical analysis, sizing equipment, selecting material and accessories, and
! resolving field installation and operational problems of motor-operated valves. Mr. Reichie was responsible for sizing valve actuators (both pneumatic and electric) given the system operating conditions. For motor operated valves this task included : j determining the necessary torque output, then selecting the appropriate gear train ! ! configuration and motor size. For nuclear projects, motor sizing included considerations of both normal and degraded voltage conditions. Earlier in his career, Mr. Reichle worked with Stone & Webster Engineering Corporation where he was the responsible engineer for liquid and solid radioactive waste systems. Responsibilities associated with this position included: development of system design and flow diagrams, engineering, selection of equipment and layout, preparation of equipment :' specifications and purchase requisitions. Other duties included review of system piping diagrams, and resolution of field installation problems. Mr. Reichle also assisted in the development of a spare parts program and database for Millstone Unit 3. ] O 1 Page 49
l O saisMiC syr.suAriOu nePOnT FOR PEACH BOTTOM ATOMIC POWER STATION , ATTACHMENT A STEPHEN P. REICHLE FYpERIFNOF (Nant'd) In his initial assignment at Stone and Webster, Mr. Reichle assisted in the preparation of a system operations manual for Connecticut Yankee. This work included the writing of system descriptions and operating procedures for the waste evaporator degasifier, aerated drains, and steam generator blowoff. Before Mr. Reichle's employment with Stone & Webster, he spent six years in the U. S. Navy Nuclear Submarine Program where he qualified as an Engineering Watch l Supervisor. I FnUNATION O B.S., Mechanical Engineering, Central New England College A.S., Mechanical Engineering, Worcester Junior College U.S. Navy Nuclear Power School and Prototype Training Graduate Work, Fire Protection Engineering, Worcester Polytechnic Institute PROFFRRIONAl ACTIVITIER Member, American Society of Mechanical Engineers Member, Society of Fire Protection Engineers O Page 50
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O SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION i !O 1 ATTACHMENT B l THIRD PARTY AUDIT REPORT AND RESUME l l 4 O 4 i s
i Programmatic Solutions 040-96-002-L 1 24 Woodbine Annue, Suite 12 l - Nordport. New Yorki1768 j April 15,1996 ! Mr. Richard E. Daniels l PECO Energy Company
%5 Chesterbrook Blvd.
l Wayne, PA. 19087-5691 I Dear Mr. Daniels This letter report summarizes the activities performed and the conclusions drawn from the Third Party Audit of the USI A-46 Implementation program for Peach Bottom
- Umu 2 & 3.
l 1.0 Scone of Third Party Audit The scope of the third party audit covers all US A-46 topics that relate to the' j capacity of the equipment reviewed and the seismic demand that applies to these items. Specifically, the following activities were reviewed as a part of this third party audit. j 1.1 The Peach Bottom Seismic Design Bases l a j e Site seismicity
- 1.
- Seismic input to stmetures and equipment i e Seismic design of mechanical and electrical equipment l e Seismic design of tanks
! e Seismic spatialinteraction issues [ e Damping l 4 1.2 The USI A-46 Evaluation e Development of the SSEL's e Relay screening
- The overall approach used
- The screening criteria used
- The qualifications of the Seismic Review Team e Screening walkdown implementation e Results of the screening walkdown I e Outlier resolution
- Design enhancements j
~
1.3 Control of Work l
- Procedures
- Documentation ofwork hv-- ' Solutions e
$14 2615536 fax: 516 2615732
! Mr. Richard E. Daniels April 15,1996
- Page 2
- O
- Interface of the seismic activities with the systems activities 1.4 Conclusions and Results e Reasonableness ofresults e Appropriateness of recommended resolutions j 1.5 Structures, Systems, and Components Included in the Third Party Audit
! . Electrical and mechanical equipment included on the SSEL i e Tanks and heat exchangers included on the SSEL e Electrical raceways l
- Items which may have potential spatial interaction with SSEL items 2.0 Summary of Third Party Audit Activities The following summarizes the activities performed for the third party audit ofUSI A-46 activities for Peach Bottom Units 2 & 3.
2.1 Review Project Instructions The Project Instructions (References 5,6,7, and 12) provide the methods to be used for (1) developing the SSEL, (2) performing the relay review, and (3) performing the seismic screening. A third party audit of these instructions was performed and comments were forwarded to PECO (References 4,9,10, and 13). Responses to the comments made by Programmatic Solutions were provided by VECTRA by letter (References 8 and
- 18) and by inclusion of comments, as appropriate, in the reports.
2.2 Third Party Audit Walkdown of Peach Bottom Units 2 & 3 On July 15,1993 a third party audit preliminary walkthrough of the plant was performed by Harry Johnson (Reference 11). The final third party audit walkthrough was performed by Harry Johnson on November 11,1994 (Reference 14). The objectives of the walkthrough were the following:
- Gain familiarity with the typical design and installation of equipment used at Peach Bottom.
- Review the seismic interaction potential at Peach Bottom, Units 2 & 3 (particularly focusing on housekeeping issues).
. Observe the SRT walkdown activities. -
- Review at least one of each equipment classes on the SSEL O
Mr. Richard E. Daniels April 15,1996 Page 3 The conclusion from the third party walkthrough at Peach Bottom Units 2 & 3 is that, in general, Peach Bottom Units 2 & 3 are well designed for seismic loads and equipment installation appears to be quite rugged. 2.3 Third Party Audit ofMethods Used The third party audit of the methods was based on review of project instructions, on insights obtained during the third pany audit walkdown of Peach Bottom Units 2 & 3, and on review of cor pmal and draft final reports (References 1,2, and 3). Observations regarding the methods used were provided in References 15,16, and 17. 2.4 Third Party Audit of Sample Documentation During the site visit and a visit to VECTRA's Boston office on March 29 and 30, 1993 by Harry Johnson, a sample of the SEWS forms being filled out by the SRT were reviewed to determine if the documentation being developed was appropriate. During a visit to VECTRA's Boston office on June 7-8,1995 by Greg Rahner, a O review ofthe Peach Bottom Atomic Power Station Safe Shutdown Equipment List (SSEL)/ Success Path Component List (SPCL) was reviewed to determine if the SSEL was being developed in accordance with GIP and PECO requirements. The documentation of walkdown and results provided in the project report (References 1,2, and 3) was reviewed. This documentation includes the following items:
- Summary of Peach Bottom Units 2 & 3 seismic design basis e Example SEWS forms e
Seismic Verification Data Sheets (SVDS) e Peach Bottom Units 2 & 3 Safe Shutdown Equipment List e Relay Evaluation e Walkdown Resumes
- Walkdown Comments by SRT e Summary ofOutlier Recommendations e Photographs taken during the walkdown 2.5 Third Party Audit ofResults The results of the Peach Bottom Unit 2 & 3 USI A-46 implementation are provided in the project reports. A third party review of the seismic evaluation report was O performed on the conceptual and draft reports (References 1,2, and 3).
I Mr. Richard E. Daniels j . April 15,1996 i Page 4
- O 3.0 Ra=nhe of' third Party Audit j
i ) 3.1 Methods Used 4 i The method used for Peach Bottom Unit 2 & 3 conforms with the SQUG GIP l method. This method has been accepted by the NRC as described in SSER Revision 2. 3.2, Implementation of Program { j The Peach Bottom Unit 2 & 3 USI A-46 implementation has been correctly l implemented and documented. } j 3.3 Reasonableness of Results W i Based on the third party audit walkdown and review of the methods used for the ! Peach Bottom Unit 2 & 3 USI A-46 implementation, the results appear to be reasonable l and consistent with those anticipated.
- 3.4 Recommended Actions The recommended actions resulting from USI A-46 are documented in the project
! reports in Section 4.6 of the Seismic Evaluation Report (Reference 1) and in Section 5.0 of the Relay Enluation Report (Reference 3). 'Ihese recommended actions appear to be j reasonable and consistent with those anticipated. ( 4.0 C-h s o-. The methods used for the Peach Bottom Unit 2 & 3 implementation are i syymyriate, the methods have been w,irstly implemented, and the results and the j recommended actions appear to be reasonable and consistent with those anticipated , ) 5.0 Refem ! 1. " Peach Bottom Atomic Power Station Units 2 & 3 Seismic Evaluation Report",
- (1) Caa=*=1 Report, July 20,1995 and (2) Draft Report, December 1995, t
- 2. " Peach Bottom Atomic Power Station Units 2 & 3 Safe Shutdown Equipment List",
i Draft, December 1995. j 3. " Peach Bottom Atomic Power Station dnits 2 & 3, Relay Evaluation Report", (1) Con =*=1 Report, July 10,1995 and (2) Draft Report. December 1995. l-1 4
l Mr. Richani E. Daniels i April 15,1996 Page 5 1
- 4. Programmatic Solutions letter 040-92-004-L, " Peach Bottom Atomic Power Station Units 2 & 3 IPEEE/USI A-46 Independent Peer Review / Third Party Audit", October 28,1992 (comments on 0067-084/85-PI-001, Rev 1).
- 5. " Identification of Safe Shutdown Paths, Equipment and Preparation of Success Path Component List (SPCL) for Peach Bottom Atomic Power Station", Project Instruction 0067-084/85-PI01, Rev 0 & Rev 1
- 6. " Development of Median Centered In-Structure Response Spectra for Peach Bottom Atomic Power Station, Units 2 & 3", 0067-084-PI-002, Rev 0.
- 7. "USI A-46 and IPEEE Relay Evaluation for Peach Bottom Atomic Power Station Units 2 & 3",0067-084-P008, Rev 1.
- 8. ABB Impe11 letter 067-00085-084, "ABB Impell Project Instruction No. 0067 084/085-PI-001, Rev 1, Identification of Safe Shutdown Paths, Equipment and Piwsion of Safe Shutdown Equipment List (SSEL)", May 21,1993 (responses ,
to Programmatic Solutions letter 040-92-004-L). l
- 9. Programmatic Solutions letter 040-93-010-L, " Peach Bottom Atomic Power Station Units 2 & 3 IPEEE/USI A-46 Independent Peer Review / Third Party Audit", June 30,1993, (comments on: ABB Impell PI 0067-084-P008).
- 10. Programmatic Solutions letter 040-93-012-L, " Peach Bottom Atomic Power Station Units 2 & 3 IPEEE/USI A-461%t Peer Review / Third Party Audit", July 7,1993 (comments on 0067-084-PI-002).
- 11. Programmatic Solutions letter 040-93-016-L, Preliminary Peer Review Walkdown l at Peach Bottom, August 16, 1993.
- 12. "USI A-46/IPEEE SMA Seismic Capability Walkdowns for PBAPS 2&3", Project ,
Instruction 0067-084-P003, Rev 0,10/1/93 l
- 13. Programmatic Solutions letter 040-93-018-L, " Peach Bottom Atomic Power Station Units 2 & 3 IPEEE/USI A-46 Independent Peer Review / Third Party Audit",
October 28,1993 (comments on PI 0067-84-PI-P003, Rev 0) I
- 14. Programmatic Solutions Meeting Minutes, " Peach Bottom Units 2 & 3 Walkdown (focus on Unit 2), November 11,1994.
O 15. er 8r - tic s i tie i et r o4o 9$-oo8-t. e ch nette- ^te ic eewer Station, Units 2 &3", August 10,1995 (comments on Conceptual Seismic Evaluation Report)
... . __ - _.-. - - . - _ ~ - ..--
Mr. Richard E. Daniels April 15,1996 Page 6
- 16. Pregiswetic Solutions letter 040-95-009-L, " Peach Bottom Atomic Power Station, Units 2 &3", August 11,1995 (additional comments on Conceptual l Seismic Evaluation Report).
- 17. Pregis.. etic Solutions letter 040-95-013-L, " Peach Bottom Atomic Power l Station, Units 2 &3", August 22,1995 (comments on Conceptual Relay Evaluation Report).
- 18. Vectra letter 0067-00084-234, " Response to Programmatic Solutions Letter 040-95-009L Third Party Audit, Observations", February 24,1996. '
i Sincerely,
=
l ohnson 4 Senior Consultant O se 4
- .-.. ~_...- - - ._ . - _-_. - ---. - ._- - _ - __ ---__. ,
SEISMIC EVALUATION REPORT i FOR PEACH BOTTOM ATOMIC POWER STATION ! ATTACHMENT B l j Harry W. Johnson j l Education I Columbia University - Mechanics Engineer,1968 l University of Miami- Master of Science in Civil Engineering,1967 ( University of Miami- Bachelor of Science in Civil Engineering,1965 l Bettis Atomic Power Laboratory - Reactor Engineering School,1972 j SOUG Walkdown Screening and Seismic Evaluation Training Course,1992 i i Licenses and Registrations ! . California: Civil Engineer Professional History Programmatic Solutions, Inc.1992 Robert L. Cloud & Associates, Inc., Senior Associate, 1990-1992 EOE Engineering, Senior Associate, 1986-1990 Impell Corporation, Section Manager, 1974-1986 Westinghouse Bettis Atomic Power Laboratory, Senior Engineer,1969-1974 Cornell Aeronautical Laboratory, Project Engineer,1968-1969 Experience Mr. Johnson has over 20 years experience in engineering consulting in the power industry. In particular, Mr. Johnson has extensive experience in project management and design engineering. Mr. Johnson is currently performing Peer Reviews for USI A-46 and/or IPEEE for Peach Bottom 2 & 3 and Limerick 1 & 2, Salem Units 1 & 2, Arkansas Nuclear One Units 1 & 2, Grand Gulf, Waterford, Nine Mile Point 2, Byron, Braidwood, LaSalle, and Dresden.
. Mr. Johnson is also performing Peer Review of experience based piping re-evaluation for the Brookhaven National Laboratory HFTR, performing a OA Audit of Seismic Programs for Indian Point Unit 2, performing USI A-46 walkdown for Indian Point Unit 3, helping to develop a plant specific seismic program and performing O Page 1
4 i i i lO l SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION I i ATTACHMENT B l' Harry W. Johnson walkdowns to address USI A-46 for Crystal River, participating in the implementation of the Seismic IPEEE for Perry, and providing EPRl/PSE sponsored training for Seismic Technical Evaluation of Replacement items and for Use of SOUG Methods for New and Replacement Equipment. Programmatic Solutions Mr. Johnson has performed SQUG type seismic verifications for Peach Bottom, Vermont Yankee, Pilgrim, Three Mile Island, Oyster Creek, Maine Yankee, Princeton Tokamak (TFTR), Savannah River Project, Craus (France), Sequoyah, and Indian Point Unit 2. For TVA Bellefonte, Mr. Johnson developed and implementation strategy for the overall IPEEE program (all external events). O Mr. Johnson has performed independent Peer Reviews of comprehensive seismic interaction programs at Watts Bar and Comanche Peak and of the equipment seismic qualification program at Watts Bar. Mr. Johnson has participated in the development of SQUG training programs, and developed the original draft of training for the SOUG seismic interaction module. Mr. Johnson (along with Paul Smith of TRO) developed a 2 day training course in SQUG walkdown methods which has been presented to GPU Nuclear, PSE & G of New Jersey, Rochester gas & Electric, New York Power Authority, Carolina Power & Light, Marin Marietta, Stone & Webster, and Gilbert / Commonwealth. Mr. Johnson is heavily involved in applying SQUG methods to nuclear procurement programs, and is active in industry initiatives in this area. To date Mr. Johnson has managed the development of these methods for seven plants. Mr. Johnson is a contractor for EPRl/PSE in the development of Seismic Technical Evaluation of Replacement items (STERI) and Generic STERI (GSTERI). At EQE Mr. Johnson started up and managed the Eastern Regional Office. Project work included development of new methods for seismic evaluations of mechanical and electrical equipment using SQUG methods. For GPU Nuclear, Mr. Johnson developed Harry W. Johnson O Page 2 l
l O' SEISMIC EVALUATION REPORT i l FOR PEACH BOTTOM ATOMIC POWER STATION ATTACHMENT B and managed all work associate with the seismic verification of TMI and OCNGS control room cabinets, including verification of many modifications. At Impell Mr. Johnson was Manager of Engineering Mechanics. This included design, project management and engineering evaluations. I At Bettis Mr. Johnson headed a reactor engineering stress / test group for an advanced submarine project. At Cornell Aeronautical Laboratory Mr. Johnson performed projects related to automobile crash injury research. l O l Page 3
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1 + O SEISMIC EVALUATION REPORT FOR PEACH BOTTOM ATOMIC POWER STATION 1 i l 1 i i l i I l, !O 4 ATTACHMENT C SVDS i 1 l 1 i i l 1
!O l
i l ! l l I i
w. PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) , [d Eq. Eq.ID Equipment Description Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Cavests Anchor Interact Equip Cl % Spec Demd7 OK7 OK7 OK7 OK7 PIMS ID g 20sw 450 V REACTOR AREA EL.165" MCC 20836 Reodor bug -U2 165 R2-41 165 N/A GERS CRS N N U Y N (E124-R-C) E12<tt4 tacess) 4 2ax135 PANEL 20Y35 TRANSFORMER Russ Beg -U2 135 R2-29 135 N/A ABS CRS Y Y Y Y Y 2aX13S 5 2AP35 RHR PUMP A Reedor 8Mg .U2 091 R2-5 91 N/A BS GRS Y Y Y Y Y 2Apo35 5 2eP35 RHR PUMP B Reedor eMe -U2 091 R24 91 N/A BS GRS Y Y Y Y Y 29Po3S 2CP35 RHR PUMP C Reedor 8Mg.U2 091 R2-7 91 N/A BS GRS Y Y Y Y Y 5 2CPo35 5 20P35 RHR PUMP D R*' der BMs U2 091 R24 91 N/A BS GRS Y Y Y Y Y 20Po35 e 2AP42 HIGH PRESSURE SERVICEWATER PUMP A Pmp Hou" 111 PM4 til Y BS GRS Y N U N N 2 Apoe 2 e 29P42 HIGH PRESSURE SERVICE WATER PUMP B Pwp Hou" 111 PM4 111 Y BS GRS Y N U N N 2ePod2 , 8 2CP42 HIGH PRESSURE SERVICE WATER PUMP C Pwy Hou" 111 P/H4 111 Y BS GRS Y N U N N 2CPo42 0 20P42 HIGH PRESSURE SERVtCE WATER PUMP O Pmy Hou" 111 P/H4 111 Y BS GRS Y N .U N N 2DPo82 Cert!flestfort AB the InfbrmeWen contained on this Screening VertRcedon Data Sheet (SVDS)le, to me best of our The inRirmoson provided io me Selspree CapetiHRy Engineers regente systems and operocone of me knowledge and besef, aned and accurate *AR Intirmegorf Includes eedi entry and conclusion (whether equipment contained in the SVDS te, to me best of our knowledge end besef, corred and scxwnee. vertfled ta be sehenicesy adequate or no0 Approved (one signature of Systems or operseene Engineerle reqded If the Seierrde CapabERy Engineers deem R necessary.) Approvee (Signatures of se Seismic CapabHRy Enginee's on the Sohmic Revhnv Team (SRT) are required; there ohnued be at leest two on me SRT. As signatories should agree with as the entries and
;)
conclusions. One signetory should be alicensed r n ; engineer.) Charbei Abou-Jaoude c; /77 Ah /1./g. Y Print or Type Name Signatur4 Date Print orType Name Signature Date Dimitrios Antonopoulos ,[ fh/g Print of Type Name Signature ' Date ' Print or Type Name Signature Date
\-
-- - - ew- .- rwa Print nr Tyne Name Sbneture Date
p f% O s V.. PEACH BOTTOM ATOMIC POWER STATION Eq. Eq. ID Equipment Description SCREENING VERIFICATION DATA SHEET (SVDS) h Bldg. Fl. EL Room Base Et <407 Cap Demd. Cap > Caveats Anchor Interact Equip Cl PIMS ID Spec Spec. Demd? OK7 OK? OK7 OK7 7 Pcv2-23s-so HPCI COOL'NG WATER TO LO. COOLER AND C a BHg U2 088 R2-13 GLAND SEAL CDSR 88 Y BS GRS Y Y WA Y Y PCV-2-23450 7 Rv2 23434 HPCI PUMP SUCTION HEADER RELIEF VALVE E = = BMg-U2 088 R2-13 88 Y BS GRS Y Y N/A Y Y RV-2-238434 8A M02toMSA RHR LOOP AINBOARD DISCHARGE VALVE - Bug - U2 135 R2-25 135 N/A ABS CRS Y N N/A Y N MO-2-ioMSA SA M02-tom 58 RHR LOOP B INBOARD DISCHARM VALVE needs see- U2 135 R2-27 135 N/A ABS CRS Y N WA Y N MO-21oM58 8A MO2-2H14 HPCITURBlNE STEAM SUPPLY VALVE Reeds ese-U2 088 R2-13 88 Y BS GRS Y Y N/A Y Y MO-2-23414 8A MO2-23417 HPCI CONDENSATE STORAGE TANK SUCTION RaedwBHg U2 088 R2-13 88 Y BS GRS Y Y N/A Y Y Mo-2-23417 8A M02 23425 HPCI MtNIMUM FLOWVALVE Reedw BWg -U2 088 R2-13 88 Y BS GRS Y N N/A Y N MO-243425 8A MO2-23457 HPCI TORUS SUCTION OUTBOARD ISOLATION ReedorBMg U2 088 R2-13 88 Y BS GRS Y Y N/A Y Y VALVE u n 23457 BA Mo2 2345e HPCI TORUS SUCTION INBOARD ISOLATION Reeder Bug -U2 098 R2-13 VALVE 88 Y BS GRS Y Y N/A Y Y Mo.243458 BA M0242233A UNIT 2 A SLUTCE GATE S m H ase 118 S/H-4 116 Y BS GRS Y N N/A Y N MO-2M2233A 8A . Mo2422335 UNIT 2 B SLUICE GATE s- H=se 118 S/H-4 116 Y BS GRS Y N N/A Y N MO-2522338 14 20021 125V DC STATION DISTRIBUTION PANEL Twt *w Bus -U2 150 T2-81 150 N/A ABS RRS Y N N Y N 200021 Cert!fication. Ceritnesson. AR the informsbon contained on this Screening VerfficsBon Data S.ieet (SVDS) Is. to the best of our The informogon provided to the Seismic Capetmy Engineers regensng systems and operseons of the knowledge and belief, conect and securate "As Information includes each entry and condusion (whether equipment contained in the SVDS is, to the best of our knowledge and Delief, coned and accurate vertMed to be seismicopy adequate or not). Approved: (One signature of Systems or Operseons Engineer is required if the Seismic Capetmy App oved: (Signatures of as Seismic Capabmty Engineers on the Seismic Rev!ew Team (SRT) are Engineers deem it necessary.) required, there should be at test two on the SRT. At signatories should agree wMh m8 the entries and j conduskms. One signatory shed be a licensed professional engineer.) Charbel Abou-JaouGe C /}?.&ga_ ~ n./p.1f' Print or Type Name Signature Date Print or Type Name Signature Date Dimitrios Antonopoulos d /gh(( Print or Type Name Signature ' Date ' Print or Type Name Signature Date t Print or Type Name Signature Da% Print or Type Name Signature Date
p /% A U PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq Eq. ID Equipment DesCnpbon Bldg. FI Et Room Base Et <40"? Cap Demd- Cap > Caveats Anchor Intered Equip Cl PIMS ID Spec. Spec Demd7 OK? OK7 OK7 OK7 14 2eD22 125V DC STATION DISTRIBUTION PANEL Turt*w side U2 150 T241 150 N/A ABS RRS Y N N Y N 20D022 14 20023 125VDC STAT 10N DISTRIBUTION PANEL Twt *= side - U2 150 T2-81 150 N/A ABS RRS Y N N Y N 200023 14 20S3t5 BYPASSASOLATION SWITCH Twtow sedo-U2 150 T241 150 N/A ABS RRS Y Y Y Y Y 20$315 14 2cV35 120VAC OtSTRIBUTICN PANEL R u m side-U2 135 R2-29 135 N/A ABS CRS Y Y Y Y Y 20Vo35 18 LTeo27A TORUS WATER LEVEL TRANSMITTER FOR Rum Bldg -U2 091 R2-10 110 N/A ABS CRS Y Y Y Y Y LR-8027 LT4027A 18 LT4027e TORUS WATER LEVEL TRANSMITTER FOR U4027 R**de'IM g U2 o31 R2-10 110 N/A ABS CRS Y Y Y Y Y LT40278 13 LT4123e TORUS WATER LEVEL TRANSMtTTER FOR Reedor Bids -U2 091 R24 95 N/A ABS CRS Y Y Y Y Y LR-81238 LT41238 18 PT-25o88 CONTAINMENT ATMOS DRYWELL PRESS pesew side -U2 195 R2-53 195 N/A ABS CRS N Y Y Y N TRANSMITTER FOR PR-2508 PT-2Soe8 20 20041 HPCI GLAND SEAL CONDENSER VACUUM PUMP Reactor gode-U2 088 R2-13 88 WA ABS CRS Y Y Y Y Y STARTER 20Do41 20 20S37#ANEL "U2" HPCI TURBfNE Raw side-U2 ON R2-13 88 N/A ABS CRS Y Y Y Y Y 20$o37fAMEL 20 2CC133 FAN ROOM HSV RELAY PANEL Red e m Side 165 R/W-32 165 N/A ABS RRS Y Y Y Y Y 2CC133 21 2eE33 HPCI C:.AND SEAL CONDENSER (23-2) Reemor side -U2 088 R2-13 88 N/A N/A N/A N/A Y Y Y Y 2eEo33 Ce,1lncanon Ceviincetion. As the information contained on this Screening Venncagon Data Sheet (SVDS)Is, to the best of our The h*wmeson provided to the Seismic Capetmy Engineers regarding systems and operssons of sw knowiedge and benet. conect and accurate "As informoeon" includes each entry and condusion (whether equipment contained in the SvDS is, to the best or our knowledge and bem er conect and accurese verined to be seismicany adequate or not).
- Approved: (One signature of Systems or Operamons Engineer is required W the Seismic Capabmy Approved. (Signatures of aR Seismic CapabMy Engineers on the Seismic Review Team (SRT) are Engineers deem R necessary.)
required, there should be at leest two on the SRT. AR signatories should agree w!!h a8 the entries and ) conclusions. One signatory should be a licensed professional engineer.) Charbel Abou-Jaoude dl /)7, & M ., fy,g.?f Print or Type Name Signature Date Print or Type Name Signature Date Dimitrios AntonOpoUlOs Print or Type Name [Signature
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Date Print or Type Name Signature Date
's Print or Type Name Signature Date Print of Type Name Signature Date
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PEACH BOTTOM ATOMIC POVWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) -[d Eq. Eq.10 Equipment Descnotion Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Cavests Anchor Interact Equip Cl Pm4S K) Spec. Spec Demd? OK7 OK7 OK7 OK7 i i 2 sosio 480 V BUS E134 mesenssue-US 185 R3-116 165 WA GERS CRS Y* N N_ N N ; E 3t201o i 2 30e11 480 V BUS E234 R*" 8MB - US 105 R3-41 165 WA GERS CRS Y* N N N N l , 30e011 l 2 3ce12 480 V BUS E334 mus=ei8h-U3 165 R3-115 165 WA GERS CRS Y* N N N N Sono 12 2 sosis 4eo V BUS E434 n -seeine-us 165 R341 165 WA GERS CRS Y* N N N N 3 coo 13 4 sono E134 LOAD CENTER XFMR(30X30) #88 BMW - U3 105 R3-11e 165 MA DOC CRS Y .Y Y Y Y somno 4 3001 E234 LOAD CENTER XFMR (30X31) R"88 8888 - U3 165 R341 165 MA ABS CRS N N N Y N 30221 4 30u2 E334 LOAD CENTER XFMR (30X32) name esse-US 165 R3-115 165 WA DOC CRS Y Y Y Y Y sono 32 4 3003 E434 LOAD CENTER XFMR (30X33) m usweens-U3 165 R3-41 165 NA ABS CRS N N N Y N somos 5 3AP35 RHR PUMP A R"888M8-U3 001 R3-5 91 NA BS GRS Y Y Y Y Y 3mPass 5 seP3s RHR PUMP B m usssus-U3 091 R34 91 MA BS GRS Y Y Y Y Y sopo35 5 3CP35 RHR PUMP C nasceueMe U3 091 R3-7 91 MA BS GRS Y Y Y Y Y j 3CPo3s 5 30P3s RHR PUMP D R'*88M8*US 091 R3-8 91 MA BS GRS Y Y Y Y Y soposs CerWRes50rt. N As the Irdormoson conleined on Wile Screening Vertnesson Dale Sheet (SVDS) le. to sie best or our The Informoson provided to the Setemic c p.am Engineers r regoriang erstems and opersenne et sie knamendge and baser, conect and somrsee. An irsonneson indudes endi enty and condusion (whosher equipment contained in the svDs le. to the best or our knousedge and beast, coned and accursee vertned to be setemicasy adequets or not). Approvet tone signature of systems or opersenne Engineeris requhed Nthe Seismic empasmy Approved (signelures at as setemic ar= c Nosy Engineers on the Setemic Review Team (SRT) are Engineers deem R necesesry ) required. Insee shound be et leset two on the sRT. As signseortes should agree wah su the entries and j condusions. One signatory should be a ncenend prosessionsi engineer) Charbel Abou-Jaoude d/?J.jQLM /1./3 7J-Print or Type Name Signature Date Print or Type Name Signature Date
.Y Signature'
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Date' 9W Print or Type Name Signature Date Print or Type Name i Print or Type Name Signature Date Print or Type Name Signature Dele
PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [e'es Eq. Eq.ID Equipment Desenption Bldg. FL EL Room Base EL c40'? Cap Demd. Cap > Cavests Anchor Interact Equip Cl ptMS lo Spec Spec Demd? OK? OK7 OK7 OK7 3AP42 PepHe 111 P/H-9 111 Y BS GRS Y N U N N 0 HIGH PRESSURE SERVICE WATER PUMP A 3APo42 3eP42 PepH= 111 Pne 111 Y BS GRS Y N U N N 0 HfGH PRESSURE SERVtCE WATER PUMP B 3ePo42 8 3CP42 HIGH PRESSURE SERVICE MTER PUMP C % Hm 111 PR9 .11 Y BS GRS Y N U .N N scPo42 6 3oP42 HIGH PRESSURE SERVICE WATER PUMP D PepHm 111 P/H-9 111 Y BS GRS Y N U N N 3oPo42 y Pcv3.238-50 HPCI COOLING WATER TO LO, COOLER AND Reedor 94 - U3 088 R3-13 88 Y BS GRS Y Y WA Y Y GLAND SEAL CDSR Pcv-3-2Soso 7 W123c34 HPCI PUMP SUCTION HEADER RELIEF VALVE R**do' sw . U3 088 ns.13 88 Y BS GRS Y Y WA Y Y Rv4238434 8A Mos-23414 HPCITURBtNE STEAM SUPPLY VALVE Reedor og -Us 088 R3-13 88 Y BS GRS Y Y WA Y Y Mo423414 Mo123417 Reactor 8Mg .U3 088 R3-13 88 Y BS GRS Y Y WA Y Y 8A HPCI CONDENSATE STORAGE TANK SUCTION Mo423417 8A Mo3-21025 HPCI MINIMUM FLOWVALVE R*emar sus -U3 088 R3-13 88 Y BS GRS Y N WA Y N Mo423425 Mo3-23457 HPCI TORUS SUCTION OUTBOARD ISOLATION Reactor seg -U3 088 R3-13 88 Y BS GRS Y Y N/A Y Y 8A VALVE Mo423457 8A Mo3-2345e HPCI TORUS SUCTION INBOARD ISOLAMON Reactor eMO -U3 088 R3-13 88 Y BS GRS Y Y N/A Y Y VALVE Mo42345e 8A Mo*343233A UNIT 3 A SLUICE GATE saeon **au'* 118 SAM 118 Y BS GRS Y N N/A Y N Mo4343233A CertrReabort CerWRcseen. As the Infbrmation contained on this Screening Vertnesson Data Sheet (SVDS) is, to the best of our The intbrmenon provided to the Seismic Capsbay Engineers regereng systems and opers5cns of tw knowiedge and bener, conect and exurste As intbrmattore includes eedi entry and concsusion (whether equipment contained in the SvDS is, to the best or our knowledge and benet, corred and securate veriRed to be seismienny adequate or not). Approved (One signature of Systems or Operseens Engineer is required N the Se%mic Capabmty Approved (Signatures of se Seismic CapabMy Engineers on the Seismic Review Toom (SRT) are Engineers deem R necessary) requent there should be et least two on the SRT. AB signatories should agree with mR the entries and J condussons. One signatory should be a licensed professional engineer.) Charbel Abou-Jaoude C./77.k, b e /1. /8.7f Print or Type Name Signature Date Print or Type Name Signature Date Dimitrios Antonopoulos j /h(( Print or Type Name Signature ' Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
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PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) $$ Eq. Eq.10 Equipment Desenpten Bldg. FL EL Room Base EL <4(T7 Cap Demd. Cap > Coveele Anctior M Eqdp Ci Pa4S 10 Spec. Spec. Deme? oK7 oK7 oK7 on?
- 8A eso u m 33e UNIT 3 8 SLLMCE GATE Screm Houes 116 $84 116 Y BS GRS Y N WA Y N Mo43aw32338 14 3oD22 3 PPB DISTRIBUTION PANEL 125VDC Tusene eine-U3 150 T341 150 MA ABS RRS Y N N Y N 3oDo22 94 3o023 3PPC DISTRIBUTION PANEL 125V DC Tween m e US 150 T341 150 N/A ABS RRS Y N N Y N 3o0023 14 3o024 3 PPD 125V DC DISTRIBUTION PANEL Tween me.U3 150 T341 150 N/A ABS RRS Y N N Y N 300o24 14 30S315 BYPASSASOLATION SWITCH T**** N o*U3 150 T3-et 150 N/A ABS RRS Y Y Y Y Y Sos 315 to LT-so27A TORUS VmTER LEVEL TRANSMITTER FOR ponener seso-US Det C-Core Spray 110 N/A ABS CRS Y Y Y Y Y LR-e027 LT-oo27A te LT-con 8 TORUS WATER LEVEL TRANSMITTER FOR Lt.e027 pensor me.U3 01 C. Core Spray 110 N/A ABS CRS Y Y Y Y Y LT oo27e is LT.e123e TORUS WATER LEVEL TRANSMITTER FOR moscaer esso-U3 01 R24 95 NA ABS- CRS Y Y -Y Y Y LR-e1238 LT.s1238 20 30D41 HPCI GLAND SEAL CONDENSER VACUUM PUMP - Reecser esso-US ggg R313 88 MA ABS CRS Y Y Y Y Y STARTER 300041 20 3oS3WdEL "U3" HPCI TURBINE nossor seso-U3 Cee R3-13 88 N/A ABS CRS Y Y Y Y Y 3aSo37-PADEL 2g SoE33 HPCI GLAND SEAL CONDENSER (23-2) R"88' 8'8e - U3 Oee R3-13 88 N/A N/A N/A N/A Y Y Y Y 3cEo33 coast 480 V PUMP STRUCTURE bCC 00001 (E224-P,A) Peip Huume U-2 N/A GERS CRS 1 111 111 Y Y Y Y Y coast CergReasort. CerWesson:
As the informoeon canismed on shio Screening vertnesIlon Dale Sheet (SVDS) le. to tus best or our The inIbrmoeon provided to the Setserse t'M Engheere =egereng systerns and opereenne or the w .M bemer, conect and ecoween "As in s, mason e incsudes each eney and conesuoion (whether equipment conesined in the SVDS te. to sie best or our smoweedge and beast, conoce and accurses vertnee to be sawmy adequois or nog. Approved- (One signelure of Systerne or Operegone Engineeris required W the Seismic e W Approvect (Signatures of al Seismic Capetfuly Engineers on the Solemic Review Team (SRT) are EngLwere deemit neeeeeery.) required; there should be et leest two on the SRT. AN signatories should agree ulk e8 tie enstes and ) conclusions. One signatory should be a Rcensed profeestonal engineer.) Charbel Abou-Jaoude d /2/.h %g._ a./g .V Print or Type Name Signature Date Print or Type Name Signature Dele h l Date 6 f Print or Type Name Signature Date Print or Type Nome yignature' Print or Type Name Signature Dole Prim or Type Name Signature Date
. _ . . .~__.___.m. _. _.___-_- _, . . _ _ _ _ _ _ _ _ . . . _ - . _ .._ . _ . _ . _ . . _ . _ _ _. ._ _ _ . . _ . _
g a PEACH BOTTORA ATORRIC POWER STATION Eq. Eq. ID Equipment Desenption SCREENING VERIFICATION DATA SHEET (SVDS) Room [d l Bldg. FL EL Base EL <40'? Cap Demd. Cap > Caveste Ancfior Interact Equip CI PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 - OK7 1 Does2 480 V PUMP STRUCTURE MCC 00862 (E124M) % muse 111 U-3 111 N/A GERS CRS Y Y Y Y Y oose2 , 4 contos PANEL OGYO3 TRANSFORMER Redeeme eMe 135 R M 21 135 WA ABS RRS Y U Y Y- U I contos onPs7 Pu"* *use ' e EMERGENCY SERVICE WATER PUMP A 111 PM-8 111 Y BS GRS Y N U N N onrost 8 CeP57 EMERGENCY SERVICEMTER PUMP g Pun, muse 111 PM4 111 Y BS GRS Y N U N N ' oeros7 7 Pcve7aoseA WN2 8tU SUP PRESS CRTL VLV FOR 08VO35 AND RedeemseMe tes RW29 165 N/A ABS RRS Y- Y WA Y Y OA(8)V034 Pcveroosen y Pcy m rocese WN2 8/U SUP PRESS CRTL VLV FOR 08VO35 AND N eMe te5 RM29 165 N/A ABS RRS Y Y N/A Y Y ; OA(8)V034 PCv467aosse 1 y Pcv e rcoest WN2 8/U SUP PRESS CRTL VLV FOR 04V035 AND Redeems eMe 165 R M 32 165 N/A ABS RRS Y Y N/A Y Y OA(8)V036 Pcvo e roceen i y PCv67aosse WN2 8/U SUP PRESS CRTL VLV FOR OAVO35 AND Rosseme else 105 RM/-32 165 N/A ABS RRS Y Y N/A Y Y CA(8)V038 pey m yga,,, , sv-sesano20 WA SOLENOID VALVE FOR PO440W-00020-01 + > eMe ABS RRS se 185 R W 32 165 N/A Y Y N/A Y Y 00020 42,808,803 41.-02.-03 svmanoso es sv-sescooms WA SOLENOfD VALVE FOR PO4-40W-00025-01 + Redeems sus 165 R W 32 165 N/A ABS RRS 00025-02 Y Y N/A Y Y svmanors og sv.3esanone FA SOLENOID VALVE FOR PO440W-0002e41 + Reessess eMe 165 R/W-32 165 N/A ABS RRS Y 0002642,00e1841 + 00816-02 Y N/A Y Y I sv m i gg sv 38840032 WA SOLENOID VALVE FOR PO440W-00032-01 + 00032 42 Redeems eMe 165 R/W-32 165 .N/A ABS RRS Y Y N/A Y Y l svam - I Cerglicatort Cerenceton: As the informaton cxmenined on WWe Screening vertilcanon Does Sewet (SVDS)lo, to the best or our The indbrmoeon provided to the Seismiccap=Nety Engineers resoneng systems and opersonne of the I knowledge and besef, corred and occurate *AR informogon" includes eedt enWy and concluelon (wheguir equgment contained in 9m SVDS is, to Wie best of our knowlsepe and beast, correct and occurate. , i verined to be seismiceer adequate or not). 1 Approved. (One signature of Systems or Operstone Engineer is required N 9ie Selenec rap =Nimy j Approved: (Signatures of as Setemc Capotely Engineers on sie Seismic Review Team (SRT) are Engineere deem it necessary ) t required; there should be et leest two on the SRT. AN signatortes should agree unth oE We enktes and j , concsusions. One e gnatory enould be e scensed profeemones engineer.) ? Charbet Abou-Jaoude c f)7.JQL /2./8- X Print or Type Name Sigdeture Date Print or Type Name Signature Date { MMW h$ignature / ~
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Oste' Print or Type Nome Print or Type Name Signature Date l I 4 Print or Type Name Signature Dole Print or Type Ne :ie Signature Dele _ __ _ _ _ _ . _ _ _ _ _ _ - . _ _ _ __.#- ..- ._. _ _ ~ _ . .
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PEACH BOTTOM ATOMIC POVWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [ Eq. Eq. ID Equipment Description Bldg. FL EL Room Bose EL <40 7 Cap Demd. Cap > C m eets Antfiw Interact Equip CI PIMS ID Spec. Spec. Demd7 cK7 on? on? on? g onvo35 EMERG SWITCHGEAR VENTIt.ATION EXHAUST nessesseende 165 RMf-32 165 N/A ABS RRS Y Y Y FAN A U U onvo35 g onvo3s BATTERY ROOM EXHAUST FAN A R*8"eme ends 165 RMf-32 165 N/A ABS RRS Y Y Y U U 04voss g opvo35 EMERG SWITCHGEAR VENTILATION EXtMUST Roememen eing jeg Rmr.32 165 N/A ABS RRS Y Y Y U U FANB cavess 9 cevo38 BATTERY ROOM EXHAUST FAN B Rosseme ends 165 RMF 32 165 N/A ABS RRS Y Y Y U U oevoss 10 cAvo34 EMERG SWGR AND BTRY ROOM VENTILATION meseems side 165 RMF-32 165 N/A ABS RRS Y N Y* N N SUPPLY FAN A envo34 10 P(NoW40o17e MASTER FOR EMERG SWGR/BTRY RMS VENT massene side 165 ' RMf-32 165 MA ABS RRS Y Y MA Y Y EXH TO CR ROOF DAMPER PO4-doW4ao17m 10 PCNoW4001 set EMERG SWGR + BATTERY ROOMS VENT SUP nessene side 165 RMf-32 165 MA ABS RRS Y Y NIA Y Y FAN OAVD34 INLET DAMPER Po.04Wooo1601 10 PO-doW40019m EMERG SWGR + BATTERY ROOMS VENT SUP messene sid9 165 RMf-32 165 N/A ABS RRS Y Y N/A Y Y FAN OAV034 OUTLET PO44oW40o1942 10 PCMoW4ao2OO1 EMERG SWGR + BATTERY ROOMS VENT SUP messesse else 165 RMF-32 165 N/A ABS RRS Y Y MA Y Y FAN 08V034 INLET DAMPER PO4-doW4co2041 10 "CMcW4ao2SO2 EMERG SWGR + BATTERY ROOMS VENT SUP Rosseme esse 105 RMi-32 165 N/A ABS RRS Y Y MA Y Y FAN 08vo34 OUTLET DAMPER Poo-4oW4ao20a2 P(NoWooo2541 EMERGENCY SWITCHGEAR VENT EXHAUST FAN Rosseele pass N/A ABS RRS 10 165 RMf-32 165 Y Y MA Y Y OAV035 INLET DAMPER PO464co2541 10 PCMoWooo2542 EMERGENCY SWITCHGEAR VENT EXHAUST FAN Rossene esse 165 RMf-32 165 N/A ABS RRS Y Y N/A Y Y OAV035 OUTLET DAMPER Po+40W4ao2s42 Cer$Rcedort Cerfliceben. As the inlbrmenon contained on this Screening Verukation Date Sheet (SVDS) lo, to Wie liest of our The irermogen provkled to Wie Solemic t'apshamy Engineers regeneng eyelomo and operesons or Wie knoededge and betet, conect and accurele *AA infbrmaton" includes each entry and conctuelon (ushether equipment contained in Wie SVDS is.10 Wie best of our kneededge and tieBef, correct and accurele vermed to be estemicesy adequele or not). Approved: (One signskne of Systems or Opersuone Engineeris required 9 the Seleneea ap hmer Approved: (Signatures of en Seismic Capabilley Engineers on Wie seismic Revlear Team (SRT) are Engineers deem it necessary.) requeed; Wiere should be et least two on the SRT. As signatories shoukt spee with eN the enstes and ) cxmesusions. One signatory should be a scensed prossesional engineer.) Charbel Abou-Jooude c, p)f, Agh_ /p, pp.pf Print w Type Name Sigheture Date Print or Type Name Signature Date [ Print or Type Name Print or Type Name Signature Deite Signature Date i Print or Type Name Signature Date Print or Type Name Signature Date
- s s . _
PEACH BOTTORI ATORRIC POYWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [E Eq. Eq.10 Equement Descripten Bldg. Fl. EL Room Base EL <4(r? Cap Demd. Cap > Cavests Ander Interad Equip CI ptMS ID Spec Spec. Demd? OK7 OK7 OK7 OK7 to P(mow 4oo2641 EMERGENCY SWITCHGEAR VENT EXHAUST FAN Rasmemm eMe 165 RM-32 165 WA ABS RRS Y Y WA Y Y 08V035 INLET DAMPER PO44h4ao2641 10 PCMoW4002642 EMERGENCY SWITCHGEAR VENT EXHAUST FAN RoswomoeMe 165 RW32 '165 WA ABS RRS Y Y WA Y Y 08V035 OUTLET DAMPER Pc e m mm 10 PCMoW4co3141 BATTERY ROOM VENT EXHAUST FAN DAV036 Rossene eMe tes RM-32 165 WA ABS RRS Y Y WA Y Y INLET DAMPER PCNMoW4ao3141 to P(McW4oo3142 BATTERY ROOM VENT EXHAUST FAN OAV036 RahomeeMe 165 RM-32 165 MA ABS RRS Y Y WA Y Y-OUTLET DAMPER POe e "3142 10 PCMoW4003241 BATTERY ROOM VENT EXHAUST FAN 08V036 Res.ame eMe 165 R W 32 165 WA ABS RRS Y Y WA Y Y INLET DAMPER PO44W4pos241 10 PCMoW4003242 BATTERY ROOM VENT EXHAUST FAN 08V036 Redsome eMe 165 R w 32 165 WA ABS RRS Y Y WA Y Y pc e m a.was42 14 oDvo3 120VAC DISTRIBUTION PANEL. R*8"emeeMe 135 R M 21 135 WA ABS RRS Y Y Y Y Y covoo3 21 oAS3s4 8ACKUP NITROGEN TO 08V035 AND DA&8V034 RosseneeMe 165 RM-29 165 WA WA WA WA Y Y Y Y FAN DAMPERS cAssee 21 oeS385 BACKUP NITROGEN TO OAV035 AND OA&BV036 RoemmeeMe 165 RM-32 165 WA WA WA NA Y Y Y Y FAN DAMPERS oesses CertWicaton. Com As the trdormenon contained on this Screening verticagon Dale Sheet (SVDS) is, to the best or our The Irdormogon enwided to Wie Solemic Nramy Engineers vegenAng systems and operemone at M [ knowiedse and beast, coneet and occursee An irdarmeson Ir-*=e== ese entry and cor-** twhether equipment eonesined h the SvDS is, to the best or our knoweedse and beast, conect and securses. ; 4 vertned to be solemiceer edequate or not). Appnwed: (One signature at Syelems or Opersuons Engineer is required N the Seismic Copsbety l Approved: (Signatures of as Seismic Capsbuty Engineers on sie Selemic Review Team (SRT) are Engineers deem R necessary) { required; there should be et least two ort me SRT. AR signatories should agree wipi es sie entites and ) l concluetons. One signotory should be e seensed professional engineer.) i Charbel Abou-Jaoude C. /h .A1#. M. v- V Print or Type Nome Sig6sture Date Print or Type Nome Signature Dele l Dintrios Arit d _ .[ _ / [pf Print or Type Nome Signature / Date Print or Type Nome Signatore Data i ! Print or Type Nome Signature Date Print or Type Nome Sgnature Deto ; i
-m m. . _ . _ . _ _ . m _ . _ . . . _ . . . _ . _ _ . _ . _ _ . _ m h
O ' PEACH BOTTOM ATOMIC POYUER STATION SCREENING VERIFICATION DATA SHEET (SVDS) Yh Eq. Eq. ID Equipment Description Bldg. ' FL EL Room Base EL 6 Cop Demd. Cap > Coweste Anchor Interect % Cl PIMS ID Spec. Spec. Demd7 OK7 OK7 OK7 OK7 PCv4917A NtTROGEN PRESS CTRL 4 ALVE FOR SACKUP mesoereMg-U2 135 R2-22 135 N/A NfA WA Y Y NfA Y Y 0 SUPPLY TO ADS PCV.2-16A4917A PCves178 NITROGEN PRESS CTRL VALVE FOR BACKUP nommereMg-U2 135 R2-22 135 MA N/A N/A Y Y WA' Y Y 0 SUPPLY TO ADS PCv416A4017e f 0 PCv4817C NITROGEN PRESS CTRL VALVE FOR BACKUP nosmarsus-U2 135 R2-22 135 WA NrA WA Y Y WA Y Y ! SUPPLY TO ADS PCV-2-tea 4017C
, 2ae37 4eoV REACTOR AREAEL195* MCC20837 nemmerens-U2 135 R2-23 135 N/A GERS CRS Y Y Y Y Y.
(E224-R-8) E224Jte (20e34 1 2ceae 4eoV RADYmSTE AREA EL 135' MCC 2083e nomear BMs-U2 135 R2-2e 135 N/A GERS CRS Y Y Y Y Y (E324-R-8) E324M Qce30) t 2cese de0V RADYmSTE AREAEL.11e* MCC2083e TwemeeMe-U2 tie T2-44 116 N/A GERS CRS Y Y Y Y Y (E424WA) E424 WA(2ce3M i 20o11 (200011) RX BUILDING DC MOTOR CONTROL nessorsuu U2 135 R2-2e 135 MA GERS CRS Y Y Y Y Y CENTER 20 eses acP3s HPCI PUMP nomear sug.U2 One R2-13 88 Y BS GRS Y Y Y Y Y 5 2 cease 5 20 37 VI' HPCI TUR8tNE 8'sesr eus -U2 One R2-13 88 Y BS GRS Y Y Y Y Y 2csos7 7 Ao2m45A SCRAM DISCHARGE VOLUME OUTSOARD nm w ems.U2 135 , R2-26 155 N/A ABS CRS N Y N/A Y N ISOt.ATION VENT W AoomessA 7 Ao24s-3se SCRAM DISCHARGE VOLUME OUTBOARD needer BMs U2 135 R2-24 155 N/A ABS CRS N Y N/A Y N ISOI.ATION VENTW Ao-2messe Mo2-toes 4A RHR LOOP A FULL FLOW TEST VALVE nummersus+U2 125 R2-110 125 Y BS GRS Y Y N/A Y Y eA (SUPPRESSON POOL COOLING) 900-2-to454A Cetinczeert Cermo-a-r As me trearmenon canished on tNo Saeonino Versicsson Does Sheet (SVDS) la, to the best or our lhe infbrmonon provided to the Seismic ?=p.maarEngheers segodng synesmo and operesons or me knowiedge end baser, conoce and escureen As hebemaeore br** each enty and concsusion whether equipment consomed in the SvDS te. to the test or our kn=*a== and esost, conect and scasses. vermied to be seismicear =d=t* or no0-Approvet (One signetwo or Systems or Operemons Engheer le requbed W the Seinwie M Approved (Signesweeof asSeismicr ..p.near EngheersontheSalemicReviewTeam(SRT)are Enghoore doom It necessary.) requket, there should be et least two on the SRT. As signatories shouh! epee wqh at the enties and ) concsuniors. One signatory shoukt be o Ocensed prolbestonal engheer.) Cherbei Abou4aoude d///./94 vD.4A //h7[ff Print or Type Nome Signature Dele Print or Type Name Signature Date DImitrious Antoriopolous d r I- M7/yf Print or Type Nome Signature ' Date Print or Type Nome Signature Date RiChord Daniels [.[, h /s/g:p/9f-Print or Type Nome Signature Date Print or Type Nome Signature Date
. - ~ - . , . - . - - - - - - . . - - - - . . - -- - -. ... -- . . - - . - - - - - . .. . .
F PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) ,% Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <4(r? Cop Demd. Cop > Coweets Anchor Interact Equip C PIMS ID Spec. Spec Demd? oK7 oK7 on7 ox7 8A Mo2-104Me RHR LOOP B FULL FLOWTESTVALVE needw eMg -U2 125 R2105 125 Y BS GRS Y Y WA Y Y I MO-2-io4Me SA M02-10m RHR LOOP A TORUS HEADER n =sesus-U2 125 R2-110 125 Y BS GRS Y Y WA Y Y M42-toonA 8A Mo2-104Me RHR LOOP B TORUS HEADER moedweMe-U2 125 R2-104 125 Y BS GRS Y Y WA Y Y MO-2-104Me es SV4130A BACKUP NITROGEN TO ADS A SUPPLY nusw sus-U2 135 R2-23 135 WA ABS CRS Y Y WA Y Y i SV-2-tea 413oA 10 2AESS RCIC PUMP ROOM COOUNG COIL A n uessus-U2 914 R2-14 100 MA ABS CRS Y Y Y Y Y 2AE055 j to 2AEse HPCI PUMP ROOM COOUNG COIL A namsw sus-U2 914 R2-13 101 MA ABS CRS Y Y Y Y Y l 2AEase 10 2AE57 A CORE SPRAY ROOM COOUNG COIL A noemzeMe-U2 91 4 R2-9 104 N/A ABS CRS Y Y Y Y Y 2AEo67 to 2AE$e A RHR ROOM COOUNG COIL A Reedssu s-U2 116 R2-16 116 N/A ABS CRS Y Y Y Y Y 2AEose } to 2eE55 RCIC PUMP ROOM COOLe#G COIL 8 mandwsus U2 91 4 R2-14 100 WA ABS CRS Y Y Y Y Y i 2eEass to 2eE5e NPCI PUMP ROOM COOUNG COIL e mammeBug-U2 914 R2-13 106 MA ABS CRS Y Y Y Y Y asease to 2eE57 A CORE SPRAY ROOM COOUNG COIL B mesaweMe-U2 91 4 R2-9 104 N/A ABS CRS Y Y Y Y Y 2eEo67 10 2eEse A RHR ROOM COOUNG COIL 8 n uessus-U2 91 4 R2-5 100 MA ABS CRS Y Y Y Y Y 2eEose Cerencesort Cerenesson. As sie bibemason contained on 9de Soesning Wrlaceuon Data Sheet (SVDS)Is, to tie best of our The MIbrmagon provided to sie Seismic Par =hsty Engineers recompng erstems and aparagone of tie ; knomiedge end beast, correct and occureen. "As inIbrmason* Includes eedi eney and conclusion (whether equipment contained in the SVDS is, to the beM of our knommedge and toget, conect and sceurste. vertned to be setemkmer Neo ornatt e Approvect (One signmeure of Systems or Opereuene Engheerle requbed N9te Selande r ar-hany ( Approvee (Signalures at en Seismicref=nemy Engineare on ins Seismic Review Team (SRT) are Engineare deem R m) requiree. there shoued be et inest two on the SRT. As signatortes should agree wist eN the entries and j condusions. One signatory should be o Ikensed J ; engineer.) ; Charbel Abou-JaOude d'-/2/[k /2/27hr Print or Type Nome Signature Date Print or Tye Name Signature Date l M Y Signature ' 2 l Date 7ft.t"
~
Print or Type Name Sigr.sture Date Print or Type Name Richard Darnel 5 .b /2[t.7 I Print or Type Name Signature Date ' Print or Type Nome Signature Date L
O -. O O , PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) d Eq. Eq. ID Equipment Description Bkig. FL EL Room Base EL <407 Cap Demd. Cap > Cavests Anchor Intered Equip Cl PIMS ID Spm Spec Demd7 OK7 OK7 OK7 OK7 10 2CE57 C CORE SPRAY ROOM COOUNG COfL C Reedor EHdg -U2 91 4 R2-11 104 N/A ABS CRS Y Y Y Y Y 2CEM7 2CE58 Refor Ng -U2 914 R2-7 105 N/A ABS CRS Y Y Y Y Y 10 C RHR ROOM COOUNG COIL C 2CEM8 10 2DE57 C CORE SPRAY ROOM COOUNG COIL D Reedor Indo-U2 91 4 R2-11 104 N/A ABS CRS Y Y Y Y Y 2DE057 10 2DESS C RHR ROOM COOUNG COfL D Reedor mg .U2 91 4 R2-7 97 N/A ABS CRS Y Y Y Y Y 2DEo$a 10 2EE57 B CORE SPRAY ROOM COOUNG COtt E Reedor eing .U2 91 4 R2-10 104 N/A ABS CRS Y Y Y Y Y 2EEoS7 to 2EE58 9 RHR ROOM COOUNG COfL E Reedor Side. U2 91 4 R24 107 N/A ABS CRS Y Y Y Y Y 2EEoS8 10 2rE57 B CORE SPRAY ROOM COOUNG COtt F R*'do' mg.U2 91 4 R2-10 104 N/A ABS CRS Y Y Y Y Y 2rEoS7 10 2FE58 B RHR ROOM COOUNG COfL F Reedor No .U2 91 4 R24 100 N/A ABS CRS Y Y Y Y Y 2FEo5e 10 2GE57 D CORE SPRAY ROOM COOUNG COfL G Reedor Bede -U2 91 4 R2-12 105 N/A ABS CRS Y Y Y Y Y 2GEoS7 10 2GE$e D RHR ROOM COOUNG COtL G Rwsar Ng.U2 116 R2-19 119 N/A ABS CRS Y Y Y Y Y 2GEoS8 10 2HE57 0 CORE SPRAY ROOM COOUNG COfL H Reeder Bedg .U2 91 4 R2-12 105 N/A ABS CRS Y Y Y Y Y 2HEoS7 10 2HE58 O RHR ROOM COOUNG COfL H Reedor side. U2 91 4 R24 100 N/A ABS CRS Y Y Y Y Y 2HEoS8 Certificatlert Certificabon. AR the Infbtrnetton contained on this Saeoning Verification Data Sheet (SWS) te, to the best of our The Irdormanon provided to the Seismic Capability Engineers regarding systems and operations of the knowledge and beNef, correct and accurate *AR infbn.iation" kich: des eact aitry and mnclusion (whether equipment mntained in the SVDS is, to the best of our knowledge and beest, correct and somrs's vertRed to be seismicefy adequate or not). Approved. (One signature of Systems or Operations Engineer le requhed N the Setemic CapabNty Approved- (Signatures of at Seismic CapabEty Engineers on the Seismic Review Team (SRT) are Engineers deem it necessary.) required; there should be at least two on the SRT. AR signatories should agree with all the entries and J conclusions. One signatory should be a scensed 4a engineer.) Chafbel Abou-Jaoude e,/77, & v he /2/17/W Print or Type Name Signat'ure Date Print or Type Name Signature Date Dimitrious Antonopolous Print or Type Name ((M Signature
/kr/[pf Date Print or Type Name Signature Date Richard Daniels g,7 /rf7/TT Print or Type Name Signature 'Date Print or Type Name Signature Date
-J ~
PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) 7d Eq. Eq. ID Equipment Description Bldg. FL EL Room Bose EL <4(T7 Cop Demd. Cap > Coweste Anchor Interact Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 16 2o037 STATIC INVERTER Twemmeus-u2 135 T2-73 135 MA ABS CRS Y Y Y N N 2 coast is 2ccer HPCIINSTRUMENT RACK R'*de me - W Oee R2-15 88 WA BS GRS Y Y Y Y Y 20C007 ta 2 ace 5 RCIC INSTRUMENT RACK Reedw a s -U2 one R2-15 88 NA BS GRS Y Y Y Y Y j 2acces 2g 2AE24 RHR HEAT EXCHANGER A R*'desus-U2 116 R2-16 116 WA WA WA WA WA U Y U 2AEo24 21 2As3n BACK-UP N2 SUPPLY TO ADS RVS mesaw me-U2 135 R248 135 WA WA WA WA NA Y Y Y 2Ae3n 21 2eE24 RHR HEAT EXCHANGER 8 nemme eMe-U2 116 R2-te 118 MA WA WA NA NA U Y U 2eEo24 21 2sssn BACK-UP N2 SUPPLY TO ADS RVS Rooms eMg-U2 135 R2-23 135 MA WA WA WA WA Y Y Y 2es3n 21 2CE24 RHR HEAT EXCHANGER C R' eau me-U2 De1 R2-17 91 NA WA WA WA WA U Y U 2CEo24 21 2cs3n BACKUP NtTROGEN SUPPLY FOR ADS mesma me-U2 135 R2-23 135 WA NA NA NA WA Y Y Y 2csan - 21 2DE24 RHR HEAT EXCHANGER D Reeds me-U2 116 R2-19 116 WA WA WA NA NA U Y U 20Eo24 3 aosse 480 V RADWRSTE AREA EL 116' MCC 30836 Twtem aus-U3 116 T3-44 116 WA GERS CRS Y Y Y Y Y (E134-WA) Et34-WA(3o83e) q suga7 480 V REACTOR AREA EL 135' MCC naeawsus-U3 135 R3-23 135 WA GERS CRS Y Y Y Y Y 30837(E234-R-B) E234Jt4(30e37) l Cersaceson. Cerenceman As the trearmogon contained on this Soesning vertncogon Dean Sheet (SVDS) le, to tie boot at our The Inibemauen provided to eie Solenec Par =Nu'r Enginsors regensne oralems and operomans of sie - knowledge and beser, arrecs and occurses. Au informomore includes each eney and condusion puheihor equipment contained in the SvDS is. to the best or our knowledge and beast, correcs and emesse versted to be esiomiceny =*=t* or nog. Approvet (one signeeure at systems or operemons Engheer is requked itthe Solemicr =r=Nay 4 Approvee (Signeeures et en Seismiccar=Nay Engineers on the Seismic Review Team (SRT) are Engineers deemIt necessary) required; there shoued be et least two en sie SRT. AE eignatories should agree w4h og the enetos and j conclusione. One signatory shouts be a licensed prosessicries engineerJ Charbel Abou-Jaoude c /);,jQf__ 1 _f,_ _ f2/jy/yf-Print or Type Name Signature Dele Print or Type Nome Signettne Dele NS / !ff Print or Type Name Signature ' Dele Print or Type Name Signature Date Richard Daries k.f./ Signature d h/phf Date ' Print or Type Name Signature Dole Print or Type Name _ - - . _ _ _ _ - _ . . _ _ _ . - . _ _ _ _ _ _ _ ____ _ _m._ _ _ _ _ _ _ _ _ . . . - -.____i.___.-.m.i__ _ _ _ __-.-_m____ ______._______._____m__u___ _ _ _ _ _ _ _ _ _ _ _ . ._ ____m_ _ A_ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___________.____m___m_. _ .__ _ _ _ _ _
O O PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Equipment Descriphon Bldg. FL EL Rem Base EL <407 Cap Demd. Cap > Caveats Anchor Interact Equip Cl PIMS ID % % Dornd? OK? OK? OK? OK7 9 sosse 480 V REACTOR AREA EL 135' MCC Reader seg .U3 135 Rs-22 135 N/A GERS CRS Y Y 'Y Y Y 30838(E334-R-B) E3344t4(3083e) , Y Y 9 30s3s 480 V REACTOR AREA EL 135' MCC 30839 Reedor BWg -U3 135 R3-23 135 N/A GERS CRS Y Y Y (E434-R-8) E4344t4(30839) g 30011 (300011) RX BUILDING DC MOTOR CONTROL Reedor BMg-U3 135 R3-26 135 N/A GERS CRS Y N N Y N CENTER 30sR4 5 30P3e HPCI PUMP R***BWe-U3 088 R3-13 88 Y BS GRS Y Y Y Y Y SoPo3e 5 30s37 "tTT HPCI TUR8tNE Reedoraug us 088 R3-13 88 Y BS GRS Y Y Y Y Y 309037 , 10 3AE$$ RCIC PUMP ROOM COOUNG COfL A Reedor BMg .U3 91 4 R3-14 100 N/A ABS CRS Y Y Y Y Y 3AEo56 10 3AE5s HPCI PUMP ROOM COOLING COIL A Ramsar sus-U3 91 4 R3-13 102 N/A ABS CRS Y Y Y Y Y 3AEase 10 3AE57 A CORE SPRAY ROOM COOUNG COfL A RumrBMg.U3 91 4 R3-9 109 N/A ABS CRS Y Y Y Y- Y 3AEoS7 10 3AE5e A RHR ROOM COOUNG COtt A Reeder eue -U3 116 R3-18 116 N/A ABS CRS Y Y Y Y Y 3AEo$e to 3eE55 RCIC PUMP ROOM COOUNG COfL B Reedor sus-us 91 4 R3-14 100 N/A ABS CRS Y Y Y Y Y 3eEoss 10 39E5e HPCS PUMP ROOM COOUNG COfL B ReedorSMg U3 91 4 R3-13 104 N/A ABS CRS Y Y Y Y Y 3eEo$s to 3eE57 A CORE SPRAY ROOM COOUNG COilB R**do' sue - us 91 4 R3-9 103 N/A ABS CRS Y Y Y Y Y 3BEoS7 Cerencaton. Cert lRestion AN the Informaton contained on this Screening VerlRestion Data Sheet (SVDS) is, to the best of our The infbrmation provided to tie Seismic CapablNty Engineers regenSng systems and opersenne of the equipment antained in the SVDS is, to the best of our knowledge and besef, correct and accurate _ knowledge and belief, correct and accurate. *AR infbrmatiort" includes each enty and condusion (whether veriRed to be seismicany adequate or noe. Approved: (One signature of Systems or Operssons Engineer is required N the Seemic Capabety Engineers deem it neassary ) Approved: (Signaturer of se seismic Capsbety Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT AI signatories should agree with at the entries and ) condusions. One signatory should be a neensed professional engineer-) Chafbel AbOu-JaOude z". /7).hj_ _ J 71/g7h;- Signdture Date Print of Type Name Signature Date Print or Type Name Dirnitrious AntonopolOus j /Mr7[f( Print or Type Name Signature Date Print or Type Name Signature ' Date Richard Daniels M.[. AeIrbr
/2d'7/fT'
'Datd Print or Type Name Signature Date Print or Type Name Signature
O O . . - O s PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [$ Eq. Eq. ID Equipmeid Description Bldg. FL EL Room Base EL <40'? Cap Demd- Cap > Caveats Anchor Interact Equip Cl Spec- Spec Demd? OK7 OK7 OK7 OK7 PIMS ID to 38E58 A RHR ROOM COOUNG COfL g Rm*r side -U3 91 4 R3-5 100 MA ABS CRS Y Y Y Y Y 38E058 10 3CE57 C CORE SPRAY ROOM COOUNG COIL C R u m elds-U3 gja R311 101 N/A ABS CRS Y Y Y Y Y 3cE057 10 3CE58 C RHR R'JOM COOLING COIL C Rems Ng-U3 91 4 R3-7 104 N/A ABS CRS Y Y Y Y Y 3CEoS8 to 30E57 C CORE SPRAY ROOM COOUNG COtt D Rmer side-U3 914 R3-11 101 N/A ABS CRS Y Y Y Y Y 3DEoS7 to 30E58 C RHR ROOM COOUNG COtL D Rum Budg - U3 91 4 R3-7 97 N/A ABS CRS Y Y Y Y Y 3DEoS8 to 3EE57 B CORE SPRAY ROOM COOUNG COfL E amm side - U3 gi4 R310 105 N/A ABS CRS Y Y Y Y Y i 3EE057 10 3EE58 8 RHR ROOM COOUNG COfL E Rmkr Bido -Q 914 R34 105 N/A ABS CRS Y Y Y Y Y 3EE058 to FE57 B CORE SPRAY ROOM COOUNG COtt F R=
- No-U3 91 4 R3-10 105 N/A ABS CRS Y Y Y Y Y FE057 to FESS B RHR ROOM COOUNG COIL F R"" No - U3 914 R34 99 N/A ABS CRS Y Y Y Y Y 3FE058 to 3GE57 D CORE SPRAY ROOM COOUNG COrL G R=h BldB - U3 91 4 R3-12 104 N/A ABS CRS Y Y Y Y Y 3GE057 to 3GE58 D RHR ROOM COOUNG COfL G Ra m Wg-U3 11e R3-19 116 N/A ABS CRS Y Y Y Y Y 3GEos8 to 3HE57 0 CORE GPRAY ROOM COOUNG COtt H R"** WO - U3 91 4 R312 104 N/A ABS CRS Y Y Y Y Y 3HE057 Cernficanon.
Certificaton: As the informs 6cn contained on tNs Screening Verification Data Sheet (SVDS)is, to the best of our The informagon provided to the Setemic CapabWty Engineers regansng systems and operauona or the L." includes som entry and cnnclusion (whh et er equipment contained in the SVDS is.1o the test of our knoutedge and besef. conect and accurate knowledge and beser, correct and accurate verined m be seismicany adequate or noo. "AE ;.L.. Approvet (One signature of Systems or Operadons Engineer is required N the Setemic Capsbety Engineers deem it necessary.) Approved (Signatures of aR Sersmic Capabluty Engineers on the Setemic Review Team (SRT) are required; there should be at least two on the SRT. As signatories should agree with aH the entries and j conclusions. One signatory should be a Rcensed ,,,a 2,. ; engineer.) Charbel Abou-Jaoude e, fy7.)QL vhw /2/g7/<j3-Signafure Date Print or Type Name Signature Date Print or Type Name Dimitrious Antonopolous .j,[_ ' M /M7 ( Date Signature Date Print or Type Name Signature Print or Type Name Richard Daniels [. [ . h,/77 Print or Type Name Signature Date Print or Type Name Signature Date
4 PEACH BOTTOM ATORNC POWUER STATION i SCREENING VERIFICATION DATA SHEET (SVDS) 7d Eq. Eq. ID Equipment Description Skig. ' FL El. Room Base EL @ . Cap Demd. Cap > Coweste h h Equip Cl PmfS ID Spec. Spec. Demd? 000 000 000 ' 000 10 3HEse D RHR ROOM COOUNG CON. H h 8Me-US 91 6 RS-8 100 WA ABS CRS Y Y Y Y Y 3HEo9e 13 30037 STATIC INVERTER ruremaus U3 135 T3-74 135 NA ABS CRS Y Y Y Y Y 300037 1e Socs7 HPCIINSTRUMENT RACK m sue-U3 Cee RS-15 88 WA BS GRS Y Y Y Y Y Soccer is 3oco5 RCgC INSTRtJMENT RACK m eng-U3 008 R3-15 88 MA BS GRS Y Y Y Y Y ww-am M4 m eus-U3 001 R3-16 91 WA NA WA Y WA y y y ! 21 RHR HEAT EXCHANGER A M RHR HEAT EXCHANGER g m aus-U3 001 R3-te 91 WA WA NrA Y MA y y y 21 3eE24 3eEo24 3CE24 n e areMe-U3- 001 R3-17 91 feA NfA WA Y lea U Y U 21 RHR HEAT EXCHANGER C 3cEo24 3DE24 n unweMe-U3 001 R3-19 91 WA NA MA Y WA y y y 21 RHR HEAT EXCHANGER D
- wwm4 w a risen 8tU t/N2 RELF VLV FOR 08VO35 AND 0(A.8)VU34 neemm aus 105 R W 2e 165 WA ABS RRS Y Y *^ Y Y
' 7 FANS PO VVS w a "714e4 wari4ee BrU tes2 RELF VLV FOR OAVO35 AND 0(A.8)VO38 m sup 165 RM32 165 NA ABS RRS Y Y *^ Y Y 7 FANS PO VVS w e rises coro*3 nee m maug 165 R/W-32 165 MA ABS RRS Y N N U N 10 EMERG SWGR VENT SUPPLY ROLL-FILTER coro43 Ceriscamort Ceriscesen. As the infbrmaton entained on this Screening vergiceman Data Sheet (SVDS) is, to tie best at ow The informeson provided to sie Seismic t'M Engineers regen 9ng erstems and opereenne or sie knowiedge and beset, correct and euuruse. Aainebrmonon includes secfienvy and concsusion enhether equipment contained h the SVDS is, to sie best of ow knowledge and beast, eened and securses. veruled to be seismicour adequate or nog. Approvedt (One signeeure of Systems or Operesons Enghoor is mquest f sie Solomiccarmheer Approved- (Signelures or se Seismiccar=hou rEnginee's on the Seismic Review Team (SRT) are Engineers deem R rm) required; there should be et toast two on the SRT. As signatories should eyee wiei en the enstes and j , cor-*h One signatory should be o Econeed protossional engineerj Charbel Abou-Jaoude O./J7 jQQ7a fg/g7df Print or Type Name Signelure Date Print or Type Nome Signature Delo Dirnitrious /My7(( Print or Type Name Signature ' Date Print or Type Name Signature Date Richard Daniels - Signature M7k Date Print or Type Nome Signature Dele Print or Type Name
i
- PEACH BOTTORE ATORAC POVUER STATION Page 1 SCREEIGNG VERIFICATION DATA SHEET (SVDS) 1artares Eq. Eq.ID Equipment Description Bldg. FL EL Room Base EL <40'? Cop Demd. Cop > Caveste Anchor interact Equip Cl Spec. Spec. Demd? OK7 OK7 OK? OK7 PIMS ID 2 20sto 400 V BUS E124 naareue-U2 165 R2-41 165 WA GERS CRS P N N N N 2 1 400 V BUS E224 near ese-U2 165 R2-116 165 WA GERS CRS P N N N N meno,,
2 2ce12 400V BUS E324 neareMg U2 165 R2-41 165 NA GERS CRS P N N N N t v E 324(20o12) 2 2ae13 400 V BUS E424 maarsus-U2 165 R2-116 165 WA GERS CRS P N N N N ; E-424f2ce13) 4 20X30 LOAD CENTER XFMR E124 8"tr sus-U2 165 R2-41 165 WA ABS CRS N N N Y N , I 4 20x31 LOAD CENTER XFMR E224 maarsWe-U2 195 R2-116 165 WA ABS CRS N N N Y N 20Mo31 4 20R32 LOAD CENTER XFMR E324 #"k"eue U2 te$ R2-41 165 WA ABS CRS N N N Y N E.1em==
. max 33 LOAD CENTER XFMR E424 n eareue.u2 105 R2-11e 165 NA ABS CRS N N N Y N E-1e17(20X33) gg sV2-23c44 HPCI TUROME EXHAUST DRAM POT DRANI neareMe-U2 See R2-13 88 Y BS GRS Y Y WA Y Y !
SOLENOIDVALVE ; sv#234s4 1e LT4123A TORUS MTER LEVEL TRANSMITTER FOR nascer eue-U2 001 R2-10 91 WA ABS CRS Y Y Y Y Y LI-8123A LT4123A ; sv3 23c44 HPCI TURBINE EXHAUST HDR DRAM POTS nearer sus-U3 One R3-13 88 Y BS GRS Y Y WA Y Y es DRAM VALVE sv-3-23454 to LT4123A TORUS WATER LEVEL TRANSMITTER FOR Rester eue-US 091 R3-11 91 MA ABS CRS Y Y Y Y Y LI-e123A LT4123A Coreliessort Cerenesson: As the inrormason contained on this Screening Vertnesson Delm Sheet (SVDS) le, to Wie best or our The informsson provkW to me Setemic e=pammy Engineare reportsne systeme and opermeone of pia equipment canamned in the SVDS is, to the best at our knoweedse and baner, conect and scuersen. knessedge and beset, conect and accurate "An informsener indudes escsi entry and conesuelon (whether vorWied to be seismicasy adequate or no4 Approve (One signeeure of Systems or Opersenne Engineerle mqubed if the Seierder=p=hmey Approvedt (Signeeures or as Seismicc=r=*asy Engineers on me Seismic Rowleur Team (SRT) are Ergineers deem R necoseery) j required; there should be et least two on Wie SRT. AE signatorise should agree ulti at 9te entries and l condusenne One signolary should be a uconood profoselonel engineer.) ci - oUa cen A t l.s., Signature a/shr Date Print or Type Name Signature Date Print or Type Name Don Fiorello /Z/p[9f
' Date Print orType Nome Signature Date Print orType Nome r ;
I Signature Date Print or Type Nome Signature Date Print or Type Name
,.]
PEACH BOTTORA ATOGAC POWER STATION ' SCREEIGNG VERIFICATION DATA SHEET (SVDS) , Eq. Eq. 30 Equipment Description Bldg. FL EL Room Bose EL <*r? Cap Demd. Cop > Coveets Andor intered Equip Cl pius D Spec. Spec. Demd? OK7 OK7 OK7 OK7 o AOSitM8A RHR LOOP A CHECKVALVE omne-Us $34 ow3 21 134 WA WA NA Y WA NA Y' Y 6 A041&oseA o AOS1M RHR LOOP B CHECKVALVE omns-U3 $34 ow3.te 134 WA WA WA Y WA WA Y Y A0-Stooses o A03-23418 HPCIDISCHARGE CHECKVALVE h Inde-U3 135 R3-30 135 WA W A' WA Y WA WA Y Y A u 23o,e o vnv>2.soseA VACUUM REUEF VALVE FOR MAM STEAM LINE orymes-U3 154 DM3-2s 154 WA NIA NA Y WA NA Y Y REUEF W A vnv4c2-soseA orynes-US N/A NA Y WA WA Y Y I ., o vnv3-2-oosso VACUUM REUEF VALVE FOR MAIN STEAM UNE 154 DM3-29 154 N/A REUEF W B vnvoer4ones o vwv>240sec VACUUM REUEF VALVE FOR MAIN STEAM UNE orymes -U3 154 oms.2s 154 WA WA WA Y N/A WA Y Y REUEF W C ; vnv4ariosec o vnv3-240seo VACUUM REUEF VALVE FOR MAIN STEAM UNE orynes U3 154 DMS-27 154 WA WA WA Y WA WA Y Y - REUEF W D vnv4creasso o vnv>2 soseE VACUUM REUEF VALVE FOR MAIN STEAM UNE orywes -U3 154 ow3 29 154 N/A N/A N/A Y N/A N/A Y Y REUEF W E t vnv4arsomeE a vnv3 2.soser VACUUM REUEF VALVE FOR MAIN STEAM UNE orynes -US 154 DMS-29 154 N/A N/A NA Y N/A WA Y Y ; REUEF W F vnv4ar-soser > a vows 2-soseG VACUUM REUEF VALVE FOR MAIN STEAM UNE orysse -U3 154 DMS-35 154 N/A WA N/A Y NfA WA Y Y [ REUEFW G t vnv442.arman o vnv3-2-sageH VACUUM REUEF VALVE FOR MAIN STEAM UNE omne-U3 154 DM3-35 154 N/A N/A N/A Y N/A N/A Y Y t REUEF W H vnv4e240seH o vnv3-2-ooseJ VACUUM REUEF VALVE FOR MAIN STEAM UNE prymes -U3 154 OM3-32 154 N/A N/A N/A Y N/A N/A Y Y RELIEF W J vnv4c2 -! . Com [ Cerenczean. I As ew Hbrmsson cenamined on this Screening Vermesson Data Shoot (SVDS)le to the best or Ow The infonnegon provitled to the Seismic ParaNay Engineare regunAng systems and operesone or the knessedge and baser, correct and accwste As irsonnsmore incsudes each erer and cerv **n (whether equipment contained in the SvoS te. to the best or our knamnedge and beast conen and accureen. vermed to be seismicser sesquete or noO-Approvett (One signature or systems or Opersuone Engineer le required W the Selande Capetsny c Approvect (signetsee or su Seismic =r=Naty Engineers on the Seismic Review Team (SRT) are Engineers deemit necessary) j required; the's should be at seest two on sw SRT. As signseories should agree w4h a5 the enktes and conclusions. One signatory should be a noenned mJ : engineer.) Chartiet Abou-Jooude d N, // /1. 7.f ' Signature Date Print or Type Name Signature Date Print or Type Name James W Print or Type Name whh Signature M
) }/hU Date Printor Type Name Signature Date i i
Signature Date Print or Type Nome Signature Dele Print or Type Name
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PEACH BOTTOM ATORAC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) (( , Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Coveste Ancliw Interact Equip Cl PIMS 10 Spm S m Do msf7 OK7 OK7 OK7 OK7
'Aty n soseK VACUUM REUEF VALVE FOR MAM STEAM UNE Ory=se-U3 154 DM3-M N/A N/A N/A Y 0 154 N/A WA Y Y i RELIEF W K VRv4 er40 sex !
O vRv3-2409st. VACUUM REUEF VALVE FOR MAM STEAM LME Dryses -U3 154 DM/3-31 154 N/A N/A N/A Y N/A WA Y Y REUEF W L v w a m 40eet 7 A034148aA A MAM STEAM LME IN9OARD ISOLATION VALVE D'y*se - us 134 Dmps-te 134 N/A ABS CRS Y N N/A Y N I Acn e1Aestm 7 A03414eos 8 MAM STEAM UNE INBOARD ISOLATION VALVE D'Y"se U3 134 omr318 134 N/A ABS CRS Y N N/A Y N Ao441Aesoe 7 A03414eoC C MAM STEAM UNE INBOARD ISOLATION VALVE D'Y"*e - U3 134 DMf3-19 134 N/A ABS CRS Y N N/A Y N l A0441AceoC 7 Ao m asco D MAM STEAM UNE INBOARD ISOLATION VALVE Drynes -U3 134 DMP3-20 134 N/A ABS CRS Y N WA Y N j i Aose1Ameno y pose 14esA A MAM STEAM UNE OUT9OARD ISOLATION Romer sus-U3 135 R3-30 135 N/A ABS CRS Y N N/A Y N VALVE i , AooetA4eeA ! y Ao3414ees B MAIN STEAM UNE OUTBOARD ISOtATION numer sus-U3 135 RS-30 135 N/A ABS CRS Y N N/A Y N VALVE A0401Acese y Aose14eeC C MAIN STEAM UNE OUTBOARD ISOLATION neuer sus-US 135 R3-30 135 WA ABS CRS Y N N/A Y N VALVE A0441AmeeC y Aosetasso D MAIN STEAM UNE OUTBOARD ISOLATION neuer sus-US 135 RS-30 135 N/A ABS CRS Y N N/A Y N VALVE i AO4c1A40eo WWW1A A SAFETY REUEF VALVE Drywes-U3 154 DMfM7 154 N/A ABS CRS N Y N/A Y N 7 i Rv4M471A i Rv m ete 8 SAFETY REUEF VALVE Drywas-U3 154 DMf3-29 154 N/A ABS CRS N Y N/A Y N 7 Rvo er471e ! Cerseessort Cerencomort I Au me Normoson anisined on Me Screenmg Verinesson Dean Sheet (SvDS) is, e me best or ow The insormsson provided to me Seismic em Engmeers regensne syseerne and operemons or se i knowledge and baser conect and amurste. "As Normoeon includes each entry and ancsusion eehscher equipment contemed m me SVDS is, to me best of ow Imouledge and besef, conect and accusee , vermed to be setemicesy adequale or nog. Approved (One signseure or Systems or Operemone Engmoer is required WIhe Selemic Pap =he4y Approvee (Signeeures or se Setemte Capsbety Engmeers on me seismic Review Team (SRT) are Engineers deem It necessary.) requesd; mere should be at least two on the SRT. As segnmearies should agree wNh at me enstes and J ; eenceusions. One signatory should be a scensed prossesionet engmeer.) charbeiwaOude S///-/QLAA /4 /. f f Print or Type Name Signature Date I Print or Type Name Sidmours Date James W MM Signature
]Nthf Print or Type Name Signature Date Print or Type Name Q Date
. l Print or Type Name Signature Date Print or Type Name Signature Date I
C ( PEACH BOTTORI ATORAC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq. ID Equipment Description Bkig. FL EL Room Bose EL <4r? Cap Demd. Cap > Cavests Anchw Iritorect % Cl PIMS ID Spec. Spec. Demd7 OK7 OK7 OK7 OK7 7 av3MMic C SAFETY REUEF VALVE Drya8-US 1H DMS-28 1M N/A ABS CRS N Y NfA Y N W442Mic 7 WW471D D SAFETY REUEF VALVE D'yme -U3 1H DMS-28 1M N/A ABS CRS N Y WA .Y N W4M471D 7 W W 471E E SAFETY REUEFVALVE Dry"8-U3 1M DM3-29 1M N/A ABS CRS N Y WA Y N W4M471E 7 WW471F F SAFETY REDEF VALVE D'yme US 154 DMS-29 1M N/A ABS CRS N Y NfA Y N W4M471F 7 NmM10 G SAFETY REUEF VALVE Dryne U3 1H DM3-29 1M N/A ABS CRS N Y N/A Y N W4M471G 7 W 3 4 471H H SAFETY REUEF VALVE D'yme US 1H DM3-35 154 N/A ABS CRS N Y N/A Y N W44471H 7 WWM1J J SAFETY REUEFVALVE D'yme.us 154 DM3-32 154 NfA ABS CRS N Y N/A Y N W442471J 7 WWMSK K SAFETY REUEF VALVE D'yme .u3 154 DM3-34 154 N/A ABS CRS N Y N/A Y N W 4 4 471x 7 W W 471L L SAFETY REUEF VALVE D'7"8 - u3 154 DM3-32 154 N/A ABS CRS N Y N/A Y N W4M471L 8A Mo3-to4MA RHR LOOP A FULL FLOWTEST UNE BLOCKW neeer side.us . 125 R3-110 125 Y BS GRS Y Y N/A Y Y eso.uo4MA 8A tso3-104Me RHR LOOP B FULL FLOW TEST UNE BLOCK mener esse-U3 125 R3-to5 125 Y BS GRS Y Y N/A Y Y VALVE teo4104pe 8A MOM 2415 RWCU INLET we80ARDISOLAT10N VALVE D'yme us 154 DM3-25 154 N/A ABS CRS Y N N/A Y N 080-3-12415 Cergnesson. Cerenessorr As the irdormagen contained on this Screening VerNicollon Date Sheet (SVDS) le. to sie boet at our 11 e inpormaton provided to sie Seismic Capotemy Enginsors regensne systems and operaenne of sie knousedge and beset, conect and securate *As informoeon" tidudes eseti eney and concsunion (whether equipment conesined in the SvDS is, to the best at our anonesses and esset, conect and secursee. verined to be seismicacy adequale or non. Approved (One signature of Systems or Operseone Engineer is requbed W Wie Seismic CapabENy Approved. (Signatures of an Seismic Capsbeer Engineers on the Seismic Review Team (SRT) are Engineers deem it necessary.) required; there should be at least two on the SRT. As signeseries should agree weih as the entries and J cwiceunions. One signatory shoukt be a utensed professional engineer.) charbewaDude d./h.jdLM- . a ^ ff Print or Type Name Signature Dele . Print w Type Name Signature Date
- n.he % C,o1e A+ nMr ~
Print or Type Name Signature Dale Print or Type Nome Signature { Date Print or Type Nome Signature Date Print or Type Name Signature Dole
\
w-- - PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [*
- Eq. Eq.ID Equipment Description Bldg. FL EL Room Base El. <4tT7 Cap DartL Cap > Coweste Anctior Intered %
C1 pmes ID Spec. Spec. Dems? on7 on? on? on? sA M03-1241e RWCU MLET OUT9OARDISOLATION VALVE numer sue-U3 105 R3-33 165 WA ABS CRS N Y WA Y N Mf%312418 i sA m23419 HPCIDISCHARGE TO FEEDWATER LINE A D'amrsus-US 135 RS-30 135 NA ABS CRS Y N WA Y N l MO-3-23419 ! tg PT,35088 CONTAINMENT ATMOS ORYWELL PRESS numer ses.us tg5 R3-53 195 WA ABS CRS N Y Y Y N l TRANSRAITTER FOR PR-350s i PT-3Soes 21 3AT540 MSTRUMENT N2 ACCUMULATOR FOR RV-71A DW -US 154 Dw3-27 154 WA WA NA WA Y Y Y Y I t 3AT540 21 3AT545 MSTRUMENT N2 ACCUMULATOR FOR RV-71A D'Y"*8 U3 154 DM3-27 154 WA WA NA WA Y Y Y Y ; , 3A m s l set 540 INSTRUMENT N2 ACCUMULATOR FOR RV-71g crywee.us 154 DM3-27 154 WA WA WA WA Y Y Y Y 21 38Ts80 21 3etses MSTRUMENT N2 ACCUMJLATOR FOR RV-712 D'V"'8 - U3 154 Dm3-27 154 MA NA WA WA Y Y Y Y 8' * ' i 21 scTsao INSTRUMENT N2 ACCUMULATOR FOR RV-71C DTees-v3 154 DM3-27 154 WA WA WA WA Y Y Y Y , scT5ao ! 21 3 cms MSTRUMENT N2 ACCUMULATOR FOR RV-71C D'7"se - us 154 DW3-27 154 WA WA' WA WA Y Y Y Y ! actses , 21 3GT54o MSTRUMENT N2 ACCUMULATOR FOR RV-71G D'y as.us 154 DM3-27 154 WA NA WA WA Y Y Y~ Y f t 3075e0 21 Som5 MSTRUMENT N2 ACCUMULATOR FOR RV-71G D'Y"*8 - U3 154 DW3-35 154 WA NA N/A WA Y Y Y Y sorses ! 21 mmo MSTRUMENT N2 ACCUMULATOR FOR RV-71K D'Y"*8 - U3 154 Dws-27 154 WA WA WA N/A Y Y Y Y i *mo Cerenesson. Cersnesson. As sie insbemason contained on INe Screening Verecemon ones Sheet (SvoS) is, to the best at ow The insonneson provWed to the Seierwer =r=hary Engineere resonang eraseme and operemons or to knameedge end beset, conect and secweie As informenore includes each enty and concsusion (whether equipment contained in the Sv0S to, to the best or ow knoustedge end tener, coned and securese i vermed to be sommicacy adequeen or nog. Approved: (One signetwo or Syseems or Operemone Engineer le required r the Seismic Capabmy Approved: (Signelures of se Seemic Cepobey Engineere on the Seismic Revleur Team (SRT) are Engineere deem R noosesory ) j requesd; there shouW be et isoet two on ese SRT. AR signatories should agree wHh eE the enstes and concsusions. One signatory should be e Rcensed professional engineer.) Charbel AbOu-JaOude d M.hM // / V Print or Type Name Signature Date Print or Type Name Signature Dole s- n~ n Print or Type Name
%e GffdA taNrr Segnature Q Date Print er Type Nome Signature Date Print or Type Name Signature Date Print or T)pe Nome Signature Date
. __ __ _.__ _ - _ _ _ . ~
j O O PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) (( Eq. Eq. ID Equipment Descriphon Bldg. FL EL Room Base EL <407 Cop Demd. Cap > Caveets Anchor Interact Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 21 3KT545 INSTRUMENT N2 ACCUMUt.ATOR FOR RV-71K D'Y"' - U3 154 DMf3-34 154 N/A N/A WA N/A Y Y Y Y 3KT545 CertmceGort. Certmcetion. AR the informe6cn contemed on this Screening VertRcation Date Sheet (SVDS)is, to the best of our The information provided to the Seismic Capet$lty Engineers regarding systems and opere9ans of the knewiedge and benef, correct and accurate. As anthrmenon incsudes each eney and mnclusion (whether equipment contained in the SVDS is, to the best of our Imowledge and benef, correct and oo: urate vertfled to be seismice#y adequate or not). Approved: (one signature of Systems or Operstons Engineer le required N the Setemic Capsbety Approved- (Signatures of mR Seismic Capetsity Engineers on the Seismic Review Team (SRT) are Engineers deemit necessary.) required; there should be et leest two on the SRT. AE signatones should agree with mR the entries and y conclusions. One signatory should be e scensed professional engineer.) Charbel Abou-Jaoude d f77.[ A~ d h /e4_. M/W Print or Type Name Signature Date Print or Type Nome Signature Dele Jasms Rahefty Print or Type Name Q hef Signature 7 Date lklyf Print or Type Nome Signature Dole i Print or Type Name Signature Date Print or Type Nome Signature Deto
( . PEACH BOTTORA ATORAC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq.10 Equipment Desertpuon Bldg. FL EL Room Base EL <407 Cap Demd. Cap > Coweste Anchor leserect Equ5-Cl pass ID Spect Spec. Dems? oK7 oK7 on? og7 9 2cese 480 V TURBINE AREA EL 135' MCC 20850 Tween sue-U2 135 T2-71 135 WA GERS CRS Y Y Y Y Y (E124-T-tQ E12s-T4(2coSS) i scoso 480 V TURBINE AREA EL 135' MCC 20800 Tweensus-U2 135 T2-71 135 WA GERS CRS Y Y Y Y Y AT-8) E22474(2ces0) 3 m ts (20A015) EMERG AUX SNTCHGEAR Tweensus-U2 135 T2-171 135- WA ABS RRS Y N- Y. N 'N annets 3 m ie (20A016) EMERG AUX SNTCHGEAR Twetesus-U2 135 72-71 135 WA- ABS -RRS Y N Y N N E22 3 N 17 (20A017) EMERG AUX SMTCHGEAR Tm aus-U2 135 T2-170 135 NA ABS RRS Y N Y N N Est 3 2cAte (20A018) EMERG AUX SNTCHGEAR Tweensus-u2 135 T2-172 135 WA ABS RRS Y N Y N N E42 4 2ax133 PANEL 20Y33 TRANSFORMER Tweensus-u2 135 T2-171 135 WA ABS RRS Y N Y- Y N zoxt33 __, 4 20xtso PANEL 20Y50 TRANSFORMER Tweemsun-u2 135 T2-171 135 WA ABS RRS Y N Y Y N 20K15e eA mo2-toetsA RHR PUMP 2AP035 MNMUM FLOW VALVE nouse sue-U2 001 R2-5 91 Y BS GRS Y N WA Y N eso2-104 tea eA aso2-1ootes RHR PUMP 2BP035 MNMUM FLOWVALVE nomansue-ut Oct R2-e 91 Y BS GRS Y N WA Y N tso 2-to41eo eA eso2-tootec RHR PUMP 2CP035 MMMUM FLOWVALVE "'esesus-U2 001 R2-7 91 Y BS GRS Y N WA Y N aso-2-tootec eA eso2 tocteo RHR PUMP 20P035 MNMUM FLOWVALVE namnwsus U2 0e1 R2-8 91 Y BS GRS Y N WA Y N act 2-toeteo Corsacesort Cerescasort As the inibrmeuen conseined on ede Saeoning vertacecon Deep Sheet (SVDS) le. to tie best of our The inlbrmagon provided to the Seismic Capetsey Engineore regeneng eyeesmo end operemone of ein knessesse end benen, correct and securene. Au ineormenon indudes each eney and cunctusion phether equipment conesined in the SVOS 5. to the best at our knessedge and toast. conect and securate. vermed to be seismicouy adequase or noo. Approved. (One signeswe at Systems or Operesons Engineer le seguiredIthe Seiernic e W Approvee (Signemsee or en Setemicr=r=Nmy Engineers on sie Seismic Review Team (SRT) are Engineere deemit noosseery) required; siere shouM be et enest two on the SRT. As signatories shouM ogree wilh et the enktes and j condusions. One signatory should be a neensed prosessiones engineer.) Charbel Abou-Jaoude c. /J7.Mgw1h My/9j-Print or Type Name Sigristure Dale Print or Type Name Signature Date RM M S. bbM6 hfMfV Print or Type Name Signature Date Print or Type Nems Signetwo Date Print or Type Name Signature Date Print or Type Nome Signature Date
PEACH BOTTOM ATOMIC POWER STAiM)N SCREENING VERfFICATION DATA SHEET (SVDS) [d . Eq- Eq.ID Equpment Description Bldg. FL EL Room Base Et <40'? Cap Demd. Cap > Coweets Anchor M Equip Cl Spec. Spec. Demd? OK7 OK7 OK7 OK7 PIMS ID uo2-104e4 neemreMe-U2 116 R2-16 116 Y BS GRS Y Y WA .Y Y 8A RHR HX 2AE024 HPSWOUTLET VALVE MO-2-to49e4 mo2-104se RHR HX 29E024 HPSWOUTLETVALVE R'"ereMe-U2 116 R2-18 116 Y BS GRS Y Y WA Y Y eA MO.2-to4eGe mo2-1o4sc neemrsue-U2 11e R2-17 116 Y BS GRS Y Y WA Y Y BA RHR HX 2CE024 HPSWOUTLETVALVE McL2-to4 esc mo2-to.eoo neuer sue-U2 116 R2-19 116 Y BS GRS Y Y WA Y Y sA RHR HX 2DE024 HPSW OUTLETVALVE uo-2-to4eso I 14 20Y33 120VAC DISTRIBUTION PANEL Tween sue-U2 150 T2-81 150 N/A ABS RRS Y Y Y Y Y 20Yo33 14 2cv50 120VAC DISTRIBUTION PANEL Twetesue-U2 150 T2-81 150 WA ABS RRS Y Y Y Y Y 20voso 14 2AD1T 250 VOLT FUSE BOX Twomesue-U2 135 T2-189 142 N/A ABS RRS Y Y Y Y Y 2Acetr 2ADie 250 VOLT FUSE BOX Tutow aus-U2 135 T2-109 142 N/A ABS RRS Y Y Y Y Y 1.s 2AD01e 14 2eD17 250 VOLT FUSE BOX Tutow aus-u2 135 T2-109 142 WA ABS RRS Y Y Y Y Y 250017 I 14 2e01e 2DPS 250V DC DISTRIBUTION PANEL 29D018 Teton eue-U2 135 T2-108 142 N/A ABS RRS Y Y Y Y- Y seco1e 14 2eD19 250 VOLT FUSE 80X TuteneMe-U2 135 T2-tes 142 N/A ABS RRS Y Y Y Y Y j zoooto 2eo3ae TweeneMe-u2 135 T2-71 135 N/A ABS RRS Y Y Y Y Y 14 125vDC DIST. PANEL (29030s) 2eD3os Cerencatiort Corescocon. As the insormogon contained on this Soesning vertliceeon Data Sheet (SVDS) is, to sie best or our The irdarmoton proveded to tw seismic FM Engineers regartsng eyesome and operssons of me equipment cordained in the SVDS is, to the best or ovr knandedge and beger, coned and emeses. kroatedge and beast, corred and occurate *As informoson"indudes each enty and conduelon (umsmer vertned to be seemiceny adequale or non. Approved (One signelure et Systems or Operemons Engineer is requbed N the Seismic FM e W Engineers on the Solande Reviour Team (SRT) are Engineers deem t necessary.) Approved (Signatures at es Seismic required; there should be et toast two on the SRT AA signatories should agree vreh ed the enstes and j amdusions. One signosory should be a skansed prossesioner engineer.) Charbel Abou.Jaoude 6 M h3rf' - /E/t7/eff _ Print or Type Home Signature Date Print or Type Name Signature Date Richard Daniels k. E bMu b M-/u[I Print or Type Name Signature Date Print or Type Name Signature Date [ i i i Print or Type Name Signature Date ! Print or Type Name Signature Dele
. = _ _ _ _ _ _ - _ - _ _ . - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - .-
O -- PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq. ID EqtW Description Bldg. FL EL Room Base EL <4(r? Cap Demd. Cap > Ceveale W Interact Equip Cl PIMS ID Spec. Spec Demd? OK7 OK7 OK7 OK7 14 2C017 250 VOLT FUSE BOX Twtwo Beds-U2 135 T2-109 142 WA ABS RRS Y Y Y Y Y 2 Coo 17 14 2C019 250 VOLT FUSE BOX Twtwa seds-U2 135 T2-189 142 WA ABS RRS Y Y Y Y Y 2 Coo 19 14 20017 250 VOLT DC FUSE BOX Tween ends-U2 135 T2-189 142 NA ABS RRS Y Y Y Y Y 200017 14 20019 250 VOLT FUSE BOX Twtem side -U2 135 T2-189 142 N/A ABS RRS Y Y Y Y Y 200o19 15 2Acot *2A* 125V DC BATTERY Twt *w side -U2 135 T2-70 135 N/A ABS RRS Y N Y N N 2A0001 15 seooi *28"125V DC BATTERY Twtwo side- U2 135 T2-16e 135 WA ABS RRS Y N Y N N 2e0001 13 2 coot *2C"125VDC BATTERY Twekw elde-U2 135 T2-70 135 N/A ABS RRS Y N Y N N 2 coco 1 15 20001 *217125V DC BATTERY Twt *w side -U2 135 T2-169 135 N/A ABS RRS Y N Y N N 200001 13 2Aco3 *2A"125V STATION BATTERY CHARGER Twt *w Base -U2 135 T2-171 135 N/A ABS CRS Y Y Y Y Y 2Accas 13 28003 *28"125V STATION BATTERY CHARGER Twe** Inds -U2 135 T2-171 135 N/A ABS CRS Y Y Y Y Y 2eonos te 2 coo 3 2C"125V STATION BATTERY CHARGER Twtemends U2 135 T2-171 135 WA ABS CRS Y Y Y Y Y 2 cocos is 20003 "2tr 125V STATION BATTERY CHARGER Twt *= ends-U2 135 T2-172 135 MA ABS CRS Y Y Y Y Y 200cos Cergnesson. Corskasort All the Informston centsined on this Screening VertRcouan Date Sheet (SVDS)is, to Wie best of our The informagon provided to the Seiernicrep=huny Engineers regenang systems and operssons of sie knowledge and bemer, arrect and accurnee. As informoson indudes each enty and condusion tuhether equipment contained in the SvDS te. to the best at our knamendes and beast, conect and securase vernied to be seemicacy adequeen or no0-Approved- (One signature at Systems or Operemons Engineer is requiroq r the Seismicrapseeny Approved. (Signatures of as Seismic r ap=humy Engineers on the Seismic Review Team (SRT) are Engmeers deern E necessary.) required; there should be at leest two on the SRT. As signatories shouki aqpee wilh sE the enktes and j condusions. One signmecry should be e scensed professiones engineer.) Chesbel Abou-Jaoude 41)]7, hL g nfgy/9f Print or Type Name Signalture Date Print or Type Name Segnature Date Richard Daniels [. b /t/i.'J[W Print or Type Name Signature Date Print or Type Name Sigr.ature Dole
.t Print or Type Name Signature Date Print or Type Nome Signature Dato
o . PEACH BOTTORA ATOtsC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) i Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <407 Cop Demd. Cap > Com Anchor 1rdered Equip Spec. Spec. Demd? Cl PIMS ID OK7 OK? OK7 OK7 18 PT 4eo5 DRYWELL PRESSURE TRANSMITTER FOR Reader sus-U2 116 R2-20 116 MA ABS CRS Y Y Y Y Y PR-4905 PT m 20 20en4 MO2-23-015 MOTOR CONTROL POWER Twtwo sus-U2 135 T247 140 N/A ABS RRS Y Y~ Y Y Y TRANSFER SVWTCH l 20e324 20 20c32 ENGMEERWG SUB SYSTEM 1RELAYCABINET Twtee sus-U2 150 T2-81 150 MA ABS RRS Y N Y N N 2cco32 20 20c33 ENGINEERMG SUB SYSTEM N RELAY CABMET Twtwo sus-U2 150 T241 150 N/A ABS RRS Y N Y M N recon 20 20c34 RCIC RELAY PANEL Twt *= sus-U2 150 T2 81 150 N/A ABS RRS Y Y Y Y Y 20co34 20 20c3e HPCI RELAY CABINET Tut *wsus-U2 150 T241 150 N/A ABS RRS Y Y Y Y Y moco3e 20 20c722A ACCIDENT MONITORMG INSTRUMENTATION Twtensu s-U2 150 T2-e1 150 N/A ABS RRS Y N Y N N PANEL 20c722A 20 20c722e ACCIDENT MONfTORING INSTRUMENTATION Twt *w sue -U2 150 T2-81 150 N/A ' ABS RRS Y N Y N N PANEL 20c722e i sosse 480 V TUR8ME AREA EL 135' MCC 30859 Twthe sus-U3 135 T3-171 135 N/A GERS CRS Y Y Y Y Y (E134-T-8) E134-T-e(30eSO) g sones 480 V TUR8ME AREA EL 135' MCC Tut *wBus US 135 T3-171 135 N/A GERS CRS Y Y Y Y Y 30800(E234-T-8) i' E234-T4(30eso) 3 30A15 (30A015) EMERG AUX SVWTCHGEAR Twtemaus-U3 135 T3-171 135 N/A ABS RRS Y N Y N N E13 , 3 30Ais (30A016) EMERG AUX SWriCHGEAR Tut *w sus -U3 135 T3-171 135 N/A ABS RRS Y N Y N N E23 Cersacason. Corsilcamort As the irdormadon contained on tde Saeoning Vermespan Dele Sheet (SVDS) le, to sie best at our The Inibrmogon provided to the Solomic r'=P=Nety Engineere regawinns systems and opersenne or sie knowledge and beset, correct and saursee As irdormogon" includes each eney and ocvw** (whether equpment contained in the SVDS le, to the boet at our amontedge and beger, conect and occurate. j vermed to be seismkasy adequete or not). Appragdt tone aloneame et Syeesmo or opersenne Engineer le squbed W the Solemic W i Approved (Signetwee of as Setemicr'aPaNety Engineers on the seismic Reh Team (SRT) are Enginen's deem it necessary.) required, there should be et leest two en the SRT. As signatories should agree with og the enkles and j conchreions. One signatory should be a scanned processionalengineer.) Charbel Abou-Jaoude d h7. k d ,2, /1/D/7f Print or Type Name Signature Date Print or Type Name Signature Does ; Richard DartWs k[ b4 h 4/DhI Print or Type Name Signature Date Print or Type Name Signature Date
,t Print or Type Name Signature Date Print or Type Nome Signature Dele t
J O J { i PEACH BOTTOM ATONIC POWER STATION l Eq. Eq.10 Equipment Descriptkm SCREENING VERIFICATION DATA SHEET (SVDS)
. Room
(( ' BIdg. FL EL Base EL <4(T? Cap Demd. Cap > Coweste Ancfior interact Equip
- Cl Pm4S 10 Spec. Spec. Demd? OK7 OK7 OK7 I OK7 MF Twete ess-U3 3 (30A017)EMERG AUX SVWTCHGEAR 135 T3-170 135 WA ABS RRS Y N Y N N [
E33 3 me (30A018) EMERG AUX 'WWTCHGEAR Tween msg-U3 135 T3-172 135 MA ABS RRS Y N Y
- N N k
- E43 4 3axtn PANEL 30Y33 TRANSFORMER Tweem ess.U3 150 T3-81 150 WA ABS RRS Y N Y Y N [
3cxt33 4 3cxiso PANEL 30YSO TRANSFORRIER Tweem msg-US 135 T3-171 135 WA ABS RRS Y N Y Y N i sontSo aA anos-toeteA RHR PUMP 3AP035 MIN FLOW RECORC BLOCK nearner shag-Us 091 R3-5 Y BS GRS N VALVE 91 WA Y N l aso.a soeten j eA eso3-toetse RHR PUMP 38P035 esN FLOW RECIRC BLOCK newser mas-u3 001 R34 Y GRS Y VALVE 91 US N WA Y N i eso4-tooses aA '803-1**sec RHR PUMP 3CP035 MIN FLOW RECIRC SLOCK Reactermas U3 ogt R3-7 Y BS GRS Y-VALVE 91 N WA Y N t eso4-tootec eA eso3-tooteo RHR PUMP 3DP035 neN FLOW RECRC SLOCK nuecser mas.us 001 R3-8 Y BS 0%9 Y VALVE 91 N WA Y N iso 4-,oe,eo [ 14 3oV33 120VAC DeSTRIBUTION PANEL Tween msg-U3 15o T341 150 WA ABS RRS .Y Y Y Y Y 1g SoYSo 120VAC DISTRIBUTION PANEL Tween sies-U3 150 T3-81 150 WA ABS RRS Y Y Y Y Y ! 888 14 38D17 250 VOLT FUSE 80X Tweem ess-US 135 T3-70 142 NA ABS RRS Y Y Y Y Y Seco17 3eoie 30P8 DISTRIBUTION PANEL,250V DC Twtwo msg-U3 14 135 T3-70 142 WA ABS RRS Y Y Y Y Y- ' 3ecots ! Certscesan. Cerencomon. l As the insormeson contehed on 1No Screenho vertacason Deem Sheet (SVDS) is, to me best of our The inkwmason provided to the Selenec CepeMMy Engheers regenAn0 systems and operemone of me knomeedse end beast, correct and secureen. *As inamnemore hceudos each oney and conclusion (whether equipment contehed h me SVDS le, h me best or our knoutedge and beset, aonect and occurate. vermed to be seemicos, y or nog. Approved- (One aloneewe at Systems or Operemons Engheer le required N the Setemte Capsbety Approved- (signatures or en Selender=r===tr Engheers on me Selande Review Team (SRT) are Engheers deem R necessary) , requtat there shouM be et inest two on me SRT. As signatortes should agree wth sE me enkles mid j ! condusions. One signatory shouM be e aconsed pressesiones engineer.) Cherbel Aboudsoude g /77,11g ,,,, /f/g 7/ht,- Print or Type Nome S$neture Dele Print or Type Nome Signature Date r Richard Daniels Print or Type Nome [bhM Signature
/t./a;7/7 Date Print or Type Nome Signature Dele l I
Print or Type Nome Signature Date Print or Type Nome Signature Date
w i . 3 . s-PEACH BOTTOM ATOMIC POWER STATION SCREENING VERFICATION DATA SHEET (SVDS) Yd Eq. Eq.10 Equipment Description Bidg. Fl. EI. Room Base EL <40"I Cop Demd. Cop > Caveste Anchor Interact Egslp CI PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 14 soote 250 VOLT FUSE 90X T**** mes U3 135 T3-70 142 WA ABS RRS Y Y Y Y Y 3ecote 14 scotr 250 VOLT FUSE 90X Tweew use-U3 135 T3-;0 142 NA ABS RRS Y Y Y Y Y scoo17 14 scote 230 VOLT FUSE BOX Tween mes-US 135 T3-70 142 WA ABS RRS Y Y Y Y Y scoose 14 30017 250 VOLT FUSE 80X Tween mes-U3 135 T3-70 142 WA- ABS RRS Y Y Y Y Y , 300017 14 3ocio 250 VOLT FUSE BOX Tween mes-U3 135 T3-70 142 NA ABS RRS Y Y Y Y Y A 30 cote 14 3oo30s 125VDC DIST. PANEL (3 PPD) Tween ads-US 135 T3-172 135 WA ABS RRS Y Y Y Y Y wm n. 15 34001 *3A* SATTERY 125V DC Tweenmes U3 135 T3-70 135 WA ABS RRS Y N Y Y N 3ADoot 13 seco1 "38" BATTERY 125V DC Tweensee U3 135 T3-180 135 WA ABS RRS Y N Y N N 3e0001 15 3 Coot =3C" 9ATTERY 125V DC Tweem ede-U3 135 T3-70 135 MA ABS RRS Y N Y Y N "aai is 30001 "31T SATTERY 125VDC Tween mes U3 135 T3-100 135 WA ABS RRS Y N Y N N
= aat 13 3aD03 "3A* 125V STATION BATTERY CHARGER Tweew meg-us 135 T3-170 135 WA ABS CRS Y Y Y Y Y unna.
38003 Tween msg-Us 133 73 171 135 WA ABS CRS Y Y Y Y Y 13 39C8 BATTERY CHARGER 125V DC
*=nant Cerencesort Cerunresorr AR the inbrmsson entained on site Saeoning verenceman Data Sheet (SVDS)le, to tie heat of our The trAprmagon provided to Wie Setemic P===h88r Engineare regangng systems and operegone of tie knoweedse and bemer. coneet and meermee. Aa insormoson inesudes each eney and concousion (whether equipenent conesined in the SvDS is,1o the best or our amansedge and beset, anus and securses vermed to be seismicour adequeen or not Approvet (one signature of Systems or opersuone Engineer le requhal N the Setemic CapabERy Approved (Signatures of en Setemic Par =Me rEngineers on Wie Setemic Review Toom (SRT) are Engineere deem R necessary.)
requirst. Viere should to et loset huo on ete SRT. As olytegories should agree wigt sE Wie entrtet and j conclusions. One signatory shouts be a scensed procesotonal engineer.) Charbel Abou-Jaoude a m, Mg ///f7/yf-Print or Type Name SigAsture Date Print or Type Nome Signature Date
~B,ms g.c. bans aju/fr Print or Type Nome Signature Date Print or Type Nome Signature Dele Print or Type Name Signature Date Print or Type Nome Signature Date
f
- .j PEACH BOTTOM ATOMIC POWER STATION
- SCREENING VERIFICATION DATA SHEET (SVDS)
Eq. Eq. ID Equipment Descripten Bldg. FL EL Room Base EL <407 Cap Demd. Cap > Coveets Anchor Interact Equip Cl' Pats D Spec. Spec. Demd7 OK7 OK7 OK7 OK7 16 ScDos 38CC BATTERY CHARGER,125V,DC Turten ends-U3 135 T3-170 135 MA ABS CRS Y Y Y. Y Y Scocos 13 3DDG3 3BCD BATTERY CHARGER,125V DC Twtem ende-U3 135 T3-172 135 MA ABS CRS Y Y Y Y Y i 3DDoo3 20 30e324 MO3-23415 MOTOR CONTROL POWWER Tweme side-U3 135 T3-87 140 N/A ABS RRS Y Y Y Y Y TRANSFER SVWTCH 3ae324 20 30C32 ENGINEERING SUB SYSTEM I RELAY CABINET M** eing - US 150 T3-81 150 N/A ABS RRS Y N Y N N soco32 20 30c33 ENGINEERING SUB SYSTEM N RELAY CA8INET Twa
- ende-US 150 T341 150 MA ABS RRS Y N Y N N soco33 20 3oC34 RCIC RELAY PANEL Twtmo side-U3 150 T3-81 150 WA ABS RRS Y Y Y 'Y Y soco34 20 Soc 3e HPCI RELAY CABINET www side-u3 150 T3-81 150 MA ABS RRS Y Y Y Y Y
, 30cose 20 soc 722A ACCIDENT MONITORING INSTRUMENTATtON Tut *w ends - U3 150 T3 81 150 N/A ABS RRS Y Y Y Y Y PANEL ' ACCIDENT MONITOResG INSTRUMENTAT10N ! 20 soc 722e Twt *w eede-U3 150 T3-et 150 N/A ABS RRS Y N Y N N PANEL soc 722e 1 casse 4e0 V TUR81NE AREA MCC 00849 (E324-T-8) Twt *w ends -U2 135 T2-172 135 N/A GERS CRS Y Y Y Y Y casse 1 coeSo de0 V TURBINE AREA MCC 00850 (E424-T-8) M** ends - U2 135 T3-172 135 N/A GERS CRS Y Y Y Y Y o0890 1 CertNiceeon. Certmcomon. i AR the informagen contained on this Screening Vermesson Dean Sheet (SVDS) le, to Wie boot of our The inlbrmegon provided to the Sesemic Capst ENy Engineers regertens eyesome and operegens of the i knowledge end bemer, conect and secureen Au informoson indudes sedi enty and conclueton (whether equipment conomined in the SVDS te, to the best of our knowledge and beset, conect and occurese, vermed to be solemicacy adequate or nog. Approvee (One signehne of Systems or Operosione Engineer le required if tie Seismic CapabEly i Approved (Signeswee or se Seismic Par = heerEngineers on the Solomic Revlow Team (SRT) are Engineere deem it nacneeery.) ! required, there ohnum be et least two on the SRT. As signesertse should scree wah as the eneise and j conesuoione. One signatory shouW be a Econood r. f _ engineer.) Ch8rbel Abou-Jaoude 4 /Jf, c.4_ y/t 7/p,- Print or Type Name Sign'oture Date Print or Type Nome Signature Date Rich 8td D8nsels [. /2/zy[W Print orType Name Signature Date Print orType Name Signature Dele Print or Type Name Signature Date Print or Type Name Signature Date [ i l
. .. .m _ __ . . __ _ _. _m_. _ _ _ . .. - .. . . . .~._ .. .. .. . , . _ . _ . ...
D v .. . v PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL c40'? Cap Demd. Cap > Caveats Anchor Interact Equip CI PIMS ID Spec. Spec. Demd? OK? OK? OK? OK? mo2424ess Dood Gewspar sA HPSW RETURN VALVE TO DISCHARGE POND 121 OtG-2 121 Y BS GRS Y Y N/A Y Y Mo-24244es sA mo242 m HPSW RETURN VALVE TO EMERGENCY DinalGemmar 121 D/G-2 121 Y BS GRS Y Y N/A Y Y COOLING TOWER uo 242 2eos sA mo34244es HPSWRETURN VALVE TO DISCHARGE POND DimiGewser 121 DG2 121 Y BS GRS Y Y N/A Y Y i mo4424ees, sA mom 24eas HPSW RETURN VALVE TO EMERGENCY Dw Geweser 121 DrG-2 121 Y BS GRS Y Y N/A Y Y COOLING TOWER wo432-seos 5 04P163 EMERGENCY SERVICE WATER BOOSTER PUMP A Deseet Geweiar 121 DIG-1 127 Y BS GRS Y Y Y Y Y omP163 5 oAP164 E1 OtG AIR COOLANT AUXILIARY PUMP DW Geweiar 127 DG4 127 Y BS GRS Y Y Y Y Y oAP164 5 oAPies Et DC JACKET COOLANT AUX PUMP Dw Gewca' 127 D/G-4 127 Y BS GRS Y Y Y Y Y 04 Pie 6 5 oAP167 Et DIG LUBE OIL AUXILIARY PUMP DwselGemmar 127 D/G-3 127 Y BS GRS Y Y Y Y Y OAP167 5 oeP163 EMERGENCY SERVICE WATER BOOSTER PUMP B Danel Gewstor 121 DIG-1 127 Y BS GRS Y Y Y Y Y oeP163 5 ceP164 E2 DIG APR COOLANT AUXtilARY PUMP DW Goarme' 127 DIG-6 127 Y BS GRS Y Y Y Y Y asp 164 5 cePies E2 DC JACKET COOLANT AUX PUMP Deed Gewser 127 DIG 4 127 Y BS GRS Y Y Y Y Y ! cePtse 5 osP167 E2 DIG LUBE OfL AUXILIARY PUMP DweelGewmar 127 DG5 127 Y BS GRS Y Y Y Y Y osP167 Certficeben: Cer9fice6cn. As the information contained ori this Screerdng Vertitcsson Data Sheet (SVDS) is, to em nest of our The infbrmogon provided to the Seismic Capability Engineers regen 9ng systeme and operations of the knourledge and betet, cerfed and occurate. *AE infbrmegorf Indudes each entry and condusion (whether equipment cxmtsined in the SVDS is, to the best of our knowledge and bene', cerfect and occurele verWied fa be solemiceny adequate or no0 Approvee (One signature of Systems or Operseone Engineer le required rthe Setsmic Capsbety Approved (Signatures of et Seismic Capability Engineers on the Setemic Review Team (SRT) are Engineers deem it necessary.) required; there should be et teost two on the SRT. As signatories should agree wth at me entries and j conclusions. One sigr%ry should be a ncensed prosessionet engineer.) Dan Fiofello a , /g/pf Print or Type Name ' Sign Date Print or Type Name Signature Date Dimitnous Ardvr -- '- Pibt or Type Name (( M Signature /
/ 27[ff Date Print or Type Name Signature Date i
Print or Type Name Signature Date Print or Type Name Signature Date
_____m m. . _ _ _ _ _ _ m_ _ __ l O J O O , PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [ Eq. Eq. ID Equipment Desenption Bidg. FL El. Room Base EL <4C'? Cap Demd. Cap > Caveats Anchor Intered Equip CI PIMS ID Spec. Spec. Demd? OK? OK7 OK? OK? 5 oCP164 E3 DG AIR COOLANT AUXtLIARY PUMP Doest Gemmer 127 004 127 Y BS GRS Y Y Y Y Y oCP164 5 cCP M E3 D/G JACKET COOLANT AUX PUMP DW Gerwear 127 DC-8 127 Y BS GRS Y Y Y Y Y oCPie6 oCP187 E3 DG LUBE OfL AUXfLIARY PUMP Dhseal GewWor 127 DC-7 127 Y BS GRS Y Y Y Y 5 Y oCPie7 eDP164 Dional Genormer 127 DG-10 127 Y GRS Y Y 5 E4 DG AIR COOLANT AUXILIARY PUMP BS Y Y Y oDets4 5 oDP185 E4 DG JACKET COOLANT AUX PUMP DW Gew* 127 DC-10 127 Y BS GRS Y Y Y Y Y oDPies 5 oDPie7 E4 DC LUBE Ott AUXILIARY PUMP Dw Gerwear 127 DC-9 127 Y BS GRS Y Y Y Y Y oDP167 y Ao-334241A ESW OUTLET BLOCK VALVE FROM DIESEL GEN DesselGenerwer 127 DC-3 127 Y BS GRS Y Y N/A Y Y Et COOLERS Ao433M41A 7 Ao.334241s ESW OUTLET BLOCK VALVE FROM DIESEL GEN Diend Genormer 127 DIG-5 127 Y BS GRS Y Y N/A Y Y E2 COOLERS A0433M418 7 Ao434241C ESW OUTLET BLOCK VALVE FROM DIESEL GEN Donel Generstar 127 OC.7 127 Y BS GRS Y Y N/A Y Y E3 COOLERS Ao4334241C y AO.3342410 ESW OUTLET BLOCK VALVE FROM DIESEL GEN D seat Gewmar 127 DG-9 127 Y BS GRS Y Y N/A Y Y E4 COOLERS Ao4334241D gg e EMERGENCY SERVICE WATER RETURN TO Desse Gewator 121 DG-2 121 Y BS GRS Y Y N/A N N DiSCH POND uom344se 9 OM084 E1 DG BUILDtNG VENTRATION SUPPLY FAN A Dined Gewwor j$t Og.t 3 j$j y g3 gp3 y y y y y 0Avoe4 Cerencason. Coronesson. Au the informenon contained on WWs Screening Verillemson Dela Sheet (SVDS) is, to the best of our The infbrme8on provided to the Seismic Capetusty Engineers regen 5ng systems and operagons of the knowledge and bemer, coned and accurate "As inebrmanore includes each eney and andusion (whether equipment contained in the SvDS is, to the best of our knowledge and tweer, corred and securata vertned to be seismkany adequate or not). Approved (One signature of Systems or Operseons Engineer is required N the Seismic CapebNity Approved: (Sgnatures of sE Seismic Capetsuty Engineers on the Seismic Review Team (SRT) are Engineers deemit necessary) required, there should to at leest two on Ow SRT. AI signatories should agree with sE the enties and j condusions. One signatory should be a licensed professionsi engineer-) Dari Fiorello em /g[/ ff Print or Type Name # Signature / Date Print or Type Name Signature Date Dimitrious AritonOpolous h,g M /[zMf Print or Type Name Signature ' Date Print or Type Name Signature Date i Print or Type Name Signature Date Print orType Name Signature Date
. __ - - - _ _ __ . . _ _ . . _ . - -- - . . _ _ ~.
e r k ' PEACH BOTTOM ATOMIC POWER STATION
- SCREENING VERIFICATION DATA SHEET (SVDS) ((
Eq. Eq. ID Equpment Description Bkig. FL EL Room Bene EL <4(T? Cap Demd. Cap > Cavests Anchor Interact Egi$ Cl PWIS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 g oevoe4 E2 DC BUILDING VENTRATION SUPPLY FAN 8 Doest Generskr 151 DIG-15 151 Y BS GRS Y Y Y Y Y i
, ocwee E3 DC BUILDING VENTRATION SUPPLY FAN C Desse Generskr 151 DG-17 151 Y BS GRS Y Y Y Y Y ocese 9 cons
- E4 DG BUILDING VENTIt.ATION SUPPLY FAN D Deses Generek" 151 OfG-19 151 Y BS GRS Y Y Y Y Y covose
, to Poco 272-1 MASTER FOR E1 DG BLDG VENT SUP FAN pesas Omnerskr 151 DG-13 155 Y BS GRS Y Y Y Y Y OAVo64 OUTSIDE AIR LAMPER Po44araor7241 to Po40272-2 MASTER FOR Et DfG BLDG VENT SUP FAN Otsest Generskr 151 DfG-13 151 Y BS GRS Y Y Y Y Y OAVo64 RETURN AIR DMAPER Po44r4ar7242 .i 10 Po40273-1 MASTER FOR E2 DG BI DG VENT SUP FAN meses Owurator 151 DfG-15 155 Y BS GRS Y Y Y Y Y 08Voe4 OUTSIDE AIR DAMPER Po44ar4ar734 to Po4ar7M MASTER FOR E23G OLOG VENT SUP FAN messe Genereur 151 0 4-15 151 Y BS GRS Y Y Y Y Y 08voe4 RETURN AIR DAMPER Po44araor7342 10 Poco 2741 MASTER FOR E3 DfG BLDG VENT SUP FAN Demons Omnerseer 151 DG-17 155 Y BS GRS Y Y Y Y '
Y OCVoe4 OUTSIDE AIR DAMPER Po44cr4ar7441 ! Pomor74-2 MASTER FOR E3 DG BLDG VENT SUP FAN Desses Generator 151 DG-17 151 Y BS GRS Y Y Y Y in Y i ocVoe4 RETURN AIR DAMPER Po44aF4027442 gg Poco 275-1 MASTER FOR E4 DfG BLDG VENT SUP FAN Deuses Generesar 151 00-1g 155 Y BS GRS Y Y Y Y Y ' oDvoe4 OUTSIDE AIR DAMPER Po44 armor 7 set i Poco 27M MASTER FOR E4 OfG BLDG VENT SUP FAN Omass consrekr 151 DG-19 Y BS GRS Y Y Y in 151 Y Y oDVoe4 RETURN AIR DAMPER Po44aF4o27542 - o4D13 Deser Genwahr 127 DC-4 127 Y GRS Y 14 125VDC DIST. PANEL (oAD13) BS Y Y Y Y omot3 c- c-As em inIbrmogen conselnad on WWs Screening vergicsson Data Sheet (SVDS) Is, to the best of ow The indbnneton provided to the Salemicr h=haa Engheers r regenNng eyelems and operegone of the i knoursedge and benef, conect and secuses. As inibnnesore kissudes escfi eney and cor% $shelhor equipment antained in the SVDS is, to the best of our kr-emkre and besef, conect and scarste. vertned to be seismiceny We or nog. c .p.maer ! Approved (One signature of Syeesmo or Opersuone Engineeris required if tie Selonde Approvee (Signeswee of eA Seismic r'mFamy Engineers on Wie Seismic Revleur Team (SRT) are Engineers clearn it necessary.) i required; there shout $ be et least too on sie SRT. AA signatortes should agree wNh ed the enkles and j ! concsuasons. One slenatory should be a noensed pr*==aanel engheer.) , D*ft M - s /Z ff Print or Type Nome ' ~ Dele Print or Type Name Signature Dole ! Print or Type Nome Y Signature ' Y Dele ( Print or Typ3 Name Signature Date h 4 Print or Type Name Signature Date Print or Type Nome Signature Dele
t .. . . ._ 3, PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) 7d_ Eq. Eq.10 Equipment Desa1ption Bldg. FL EL Room Beee EL < 10*? Cop Demd. Cap > Caveste Anchor Intered Equip Cl PSAS ID Spec. Spec. Demd? OK? OK7 OK7 OK? 14 coo 13 12svDC DIST. PANEL (08013) D*' 0"'r 127 004 127 Y BS GRS Y Y Y Y Y 0e013 14 ocD13 125VDC DIST. PANEL (OCD13) Densi N 127 DC-e 127 Y BS GRS Y Y Y Y Y oCD13 14 o0013 12SVDC DIST. PANEL (oD013) oms omne:iner 127 DG-to 127 Y BS GRS Y Y Y Y Y o0013 to # 5804 Et DG CARDOX HEAT DETECTOR DM O'n"'8'r 127 DG-3 151 Y BS GRS Y Y WA Y Y
- 888" to p esos Et DG CARDOX HEAT DETECTOR melon'* 127 DG-3 151 Y BS GRS Y Y WA Y Y m ason 5 85'A Et DG CARDOX HEAT DETECTOR DM 0"'* 127 DC-3 151 Y BS GRS Y Y WA Y Y 1e .
DO8s1A to e ssie Et DG CARDOX HEAT DETECTOR DM 0"'m 127 DC-3 151 Y BS GRS Y Y WA Y Y i masie ig HD-ss2A El DG CARDOX HEAT DETECTOR DimiG"'* 127 DC-3 151 Y BS GRS Y Y WA Y Y e ss2A to HD-ss2e Et 00 CARDOX HEAT DETECTOR DW G="eser 127 DG-3 151 Y BS GRS Y Y WA Y Y e ssas . 1g HD-ss3A Et DG CARDOX HEAT DETECTOR meest Generosor 127 DG-3 151 Y BS GRS Y Y WA Y Y to e ssse E1 DG CARDOX HEAT DETECTOR Der Generosor 127 DC3 151 Y BS GRS Y Y WA Y Y l seasse 1g m es*A Et DG CARDOX HEAT DETECTOR meses Generosor 127 DC-3 151 Y BS .GRS Y Y WA Y Y .! m es4A Cersneumort Cerenceman. AN me Irdormegon contained on ins Screening Veruicemen Dean Sheet (SVDS) le. to sie best of our The irdarmagen provkled to the Setemicr=p=heny EngIrisere regenNng eyesome and operemons of me knousedge and baner, conect and scurose. "As intbrmosore incsudes each enty and concsuelon (whether equipment centsined in the SVDS te. to the best of our knowledge and betet, correct and securate. verined to be ensemiceny =*=& or not). Approved- (One signeeure or systems or Operemons Engkieer le requked r me Solandecarahmur Approved- (Signetwee of og Setemic r =rahmur Engineere on me Solemic Revleur Team (SRT) are Engineare deem It i=r===='y.) requbed; there should be et Inest two on the SRT. As signatories should agree wilh e5 the enktes and j conclusions. One signatory shouki be a licensed prosseelonal engineer. ~
~~
Print or Type Name 42J/ J Signatip6 ' ' Date n/Wer Print or Type Name Signature Dele [
~
Print or Type Name
.dD Signature '
n/& Dele Print or Type Name Signelure Date Print or Type Name Signature Date Print or Type Name Signature Date ;
a - PEACH BOTTOM ATOMIC POVUER STATION SCREENING VERIFICATION DATA SHEET (SVDS) (( Eq. Eq. ID Equipment Description Bldg. Fl. El. Room Bose El. <40'? Cop Demd. Cop > Cavests Anchor interact Equip Cl PIMS ID Spm Spec Demd? OK? OK? OK? OK7 ig esse Et DdG CARDOX HEAT DETECTOR Diesei Generehr 127 DC3 151 Y BS GRS Y Y WA Y Y
*S8" ig HD-55sA E1 OfG CARDOX HEAT DETECTOR D**sl osure 127 Oc.3 1$j y gg ggg y y gg y y m assA is e ssse E1 DG CARDOX HEAT DETECTOR Desef Oeumear 127 DG-3 151 Y BS GRS Y Y WA Y Y HD-sses tg HD-SesA Et DG CARDOX HEAT DETECTOR DW 0"ummer 127 DG-3 151 Y BS GRS Y Y WA Y Y HD-sesA 19 HD-$see E1 DG CARDOX HEAT DETECTOR D W 0"""88' 127 DG3 151 Y BS- GRS Y Y WA Y Y e ssee 19 HD-657A E1 DG CARDOX HEAT DETECTOR DM 0"*'888' 127 DG-3 151 Y BS GRS Y Y WA Y Y le-s57A ig e s57e E1 DC CARDOX HEAT DETECTOR D*8 0="'* 127 DC3 151 Y BS GRS Y Y WA Y Y HD-es7e to HD-7se^ E2 DG CARDOX HEAT DETECTOR D**'8 0"ummer 127 DC5 151 Y BS GRS Y Y WA Y Y HD-resA to e rsee E2 DG CARDOX HEAT DETECTOR ow Omumner 127 DC-5 151 Y BS GRS Y Y WA Y Y HD-7see 19 HD-7e7A E2 DG CARDOX HEAT DETECTOR DheadOmemar 127 DG-5 151 Y BS GRS Y Y WA Y Y le-797A 19 HD-797e E2 DG CARDOX HEATDETECTOR Diessi Ow"'" 127 DG-5 151 Y BS GRS Y Y WA Y Y s to7e ts MD-78eA E2 DC CARDOX HEAT DETECTOR Dhmet O*"r* 127 OG-5 151 Y BS GRS Y Y WA Y Y m 7 sea Cortlecocon. Cerenceton.
As to Irdbrmagen contained on thee Screerdng vertecesan Date Sheet (SVDS) le, to Wie best of our The informeGon provkled to the Solomic f'at=h""y Engheers negangne erstems and operstone of Wie knoussedge and benet, conect and ecewete. As inebrmenon" hr*=*== esem eney and conesueton (whether equipment contelnad h 1he SVDS le, to the best of our imentedge and benef, correct and occurses, veruisd to be sommiceny -e-y=a= or nos). Approved (One signeeure of Systems or Operstone Engineer le requhed W9 e Selemic t'ap=hmey Approvet (Signelures of as Setemic t'=rahmer Engheers on the Seismic Rowlew Toern (SRT) are Enginsors deem R r=r==eary.) j required; there shoued be et least two on the SRT. As oisnesortes shouts agree wnh on the enetes and conesusions. One signatory should be e acer.aed pressesiones engheer Dan M ,
/g,[jgff Print or Type Nome ' ~ Signepfe Date Print or Type Name Signature Date DimitriouS N [me Signature mM /h7[f Dele Print or Type Nome Signature Date Print or Type Name Print or Type Name Signature Date Print or Type Nome Signature Date
O , PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq.10 Equipment Description Bldg. FL EL Room Beee EL 6 Cap t)emd. Cap > Caveste h interact Equip Cl pass to Spec. Spec. Demd? OK? OK7 OK? OK7 Ig HD-MS E2 DC CARDOX HEAT DETECTOR D8'' G""*** 127 04-5 151 Y BS GRS Y Y WA Y Y enee 19 *M8A E2 DG CARDOX HEAT DETECTOR Diosd Genwahr 127 DG-5 151 Y BS GRS Y Y WA Y Y HDJean is HD-Me E2 DG CARDOX HEAT DETECTOR Dead Omwear 127 Os.5 151 Y BS GRS Y Y WA Y Y HDJese is HD40m E2 D4 CARDOX HEAT DETECTOR ommelonneraar 127 DG-5 151 Y BS GRS Y Y WA Y Y HD4oon is HD40ce E2 DG CARDOX HEAT DETECTOR D***O'"**k" 127 DG-5 151 Y BS GRS Y Y WA Y Y HD4oos to HD401A E2 DG CARDOX HEAT DETECTOR Dh*WD*"**k" 127 D4-5 151 Y BS GRS Y Y WA Y Y HD e01A to HD4ote E2 DG CARDOX HEAT DE1ECTOR oised onneuer 127 0G-5 151 Y BS GRS Y Y WA Y Y HD4ote 1g HD4o2A E2 DG CARDOX HEAT DETECTOR D***lD**'k" 127 D C-5 Y BS GRS Y Y WA Y 151 Y HD4o2A HD4o2e E2 DG CARDOX HEA1 DETECTOR omed Generen" 127 DC-5 Y BS GRS Y Y WA Y 19 151 Y HD402e HD403A E2 DG CARDOX HEAT DETECTOR Dl'sW Generuew 127 0 G-5 Y BS GRS Y 19 151 Y N/A Y Y HD403A ig HD4oM E2 DG CARDOX HEAT DETECTOR chess Genmehr jgy Og.5 151 Y BS GRS Y Y WA Y Y HD4o3e HD404A Dhed Genereur 127 DC-7 Y' BS GRS Y Y WA Y tg E3 DG CARDOX HEAT DETECTOR 151 Y HD404A Cerenceton. Certinceuort As the informegon contained on see Screening vertAceton Date Sheet (SVDS) le, to tie best of our The informenon provided to the Seismicrarah'"y Engineers regarding eyotome and operegone of tie knowledge and beset. correct and secureem *As insormenore indudes esem eney and condusion (wheeier equipment contained in the SVDS is, to the best of our knowledge and beget, conect and easrate. vertned to be seiendeepy adequate or not). Approved: (One signature of Systems or Operemone Engineerle required f tie Setemic c ap haoy Approved: (signatures of se Seismic Capsbelly Engineers on the Seismic Revleur Team (SRT) are Engineers deem a necessary) required; there should be et temet two on sie SRT. As signatortes should agree with eN the entries and j condusione. One signatory should be e Rtansed profeestonal D* M // /Z /N $$ Print or Type Name / Signature Date Print or Type Name Signoture Date MW Print or Type Nome h Signature ' l Date 7W Print or Type Name - Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
- - . - _~ .. .
PEACH BOTTOM ATOMIC POWER STATION , SCREENING VERIFICATION DATA SHEET (SVDS) [h , ! Eq. Eq.10 Equipment Description Bldg. FL EL Room Base EL <4(r? Cap Demd. Cop > Coweets Anchw Interect Equip Cl PIMS 10 Spec. Spec. Demd? OK7' OK7 OK7 OK? ig HD4oes E3 DG CARDOX HEAT DETECTOR D'sel Generesar 127 DG7 151 Y BS GRS Y Y WA Y Y to HD4o5A E3 DG CARDOX HEAT DETECTOR Dummicensresar 127 DG7 151 Y BS GRS Y Y WA Y Y HD406A ig HD40se E3 DG CARDOX HEAT DETECTOR D" 0'n'k" 127 DG-7 151 Y BS GRS Y Y WA Y Y , HD*888 1e HD4aeA E3 04 CARDOX HEAT DETECTOR D"el omnermar 127 DG-7 151 Y BS GRS Y Y WA Y Y HD408A to HDiose E3 DG CARDOX HEAT DETECTOR Deses consrumr 127 DG-7 151 Y BS GRS Y Y WA Y Y ig HD4o7A E3 DG CARDOX HEAT DETECTOR D" 0'"*'aer 127 DG7 151 Y BS GRS Y Y WA Y Y IW4o7A 1s HD4o78 E3 DG CARDOX HEAT DETECTOR Dl'"8 O*"'*8'r 127 D/G-7 151 Y BS GRS Y Y WA Y Y
***** i HD4oeA E3 OG CARDOX HEAT DETECTOR Dl Generwar 127 DtG-7 151 Y BS GRS Y Y WA Y Y is l
'* *88" i is HD4ose E3 DG CARDOX HEAT DETECTOR D**'8 08"'resar 127 DG7 151 Y BS GRS Y Y WA Y Y HD4ase is HD4oeA E3 DG CARDOX HEAT DETECTOR D8 0"""'k" 127 DC-7 151 Y BS GRS Y Y WA Y Y y
}
j to HD 6 E3 DG CARDOX HEAT DETECTOR D' 0'"*'*k" 127 DG7 151 Y BS GRS Y Y WA Y Y Ho40ee t is HD4104 E3 DG CARDOX HEAT DETECTOR oemealGenereur 127 DG7 151 Y BS GRS Y Y WA Y Y 6 06 41o4 Cerencesort Cersaceeon. [ As the informoeon contained on viis Screenhavwinceton Deen Sheet (SVDS)lo, to the best etour The informagon provided to the Seismic Capsbety Engineers regartAng systeme and operssons at the knowiedge and beset, correct and securate As insonneson indudes endi envy and conceueion (whether equipment contained in the SvDS is, to the best at our knowledge and beset, conect and scnnsee. l' verwied to be seismiceny adequase or nog. Approved: (One signeeure at Systems or Operemons Engheer is required it the Seismic Capsbety ! Approved (Signehees of au Seismic Par =M'y Engineers on tie Setemic Review Team (SRT) are Engineers deemit necessary) required, there should be et enest two on Ow SRT. AR signatories should agree with og the enties and j condusions. One signosory should be a neensed prw .) Den M [g fg/ ff Print or Type Name Elgniglure Date Print or Type Name Signature Date Dmmious AntOnopoious Print or Type Name [ Signature
=I Date E7 (
Print or Type Name Signature Dele 4 Print or Type Name Signature Date . Print or Type Name Signature Dele I
n v O V (V 3 v . l/ PEACH BOTTOM ATOlWC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) (( Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Caveats Anchor Intered Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 1g HD4108 E3 D/G CARDOX HEAT DETECTOR Dimet Gewer 127 D/G-7 151 Y BS GRS Y Y N/A Y Y Ho41oe 19 HD411A E3 DG CARDOX HEAT DETECTOR DW Gewer 127 DIG-7 151 Y BS GRS Y Y N/A Y Y HD411A ig HD41te E3 D/G CARDOX HEAT DETECTOR Dimet Gewer 127 DG-7 151 Y BS GRS Y Y N/A Y Y 60 811e 1g HD412A E4 D/G CARDOX HEAT DETECTOR D' met Gewer 127 D/G-9 151 Y BS GRS Y Y N/A Y Y PO412A 19 HD412e E4 D/G CARDOX HEAT DETECTOR D* G**** 127 DC-9 151 Y BS GRS Y Y N/A Y Y HD412e 1g HD413A E4 DIG CARDOX HEAT DETECTOR Dw Gewer 127 D/G-9 151 Y BS GRS Y Y N/A Y Y DO 413A HD413e DW Gewer DC-9 ig E4 DG CARDOX HEAT DETECTOR 127 151 Y BS ,GRS Y Y N/A Y Y HD413e 19 HD-814A E4 DIG CARDOX HEAT DETECTOR D* G**** 127 D/G-9 151 Y BS GRS Y Y N/A Y Y HD414A 13 HD414e E4 OtG CARDOX HEAT DETECTOR D* G**** 127 DIG-9 151 Y BS GRS Y Y N/A Y Y HD4tas 19 HD415A E4 OG CARDOX HEAT DETECTOR D W G erer 127 D/G-9 151 Y OS GRS Y Y N/A Y Y HD415A 19 HD415e E4 DG CARDOX HEAT DETECTOR D* G"'*" 127 DIG-9 151 Y BS GRS Y Y N/A Y Y HD41$e 2 416A E4 DIG CARDOX HEAT DETECTOR Desas omrer 127 D/G-9 Y GRS Y Y 19 151 BS N/A Y Y HD416A Certificaten. CeMication: As the informanon contamed on this Screening Verificaten Data Sheet (SVDS) is. to the best of our The infbrms6cn provided to the Seismic Capabety Engineers reganling systems and operations of the knowledge and belief, corred and accurale. *AEm' fbrme6on"indudes endt entry and conclusion (whether equipment contamed in the SVDS is, to the best of our knowledge and belief, corred and securate verified to te seisr'1lcally adequate or not). Approved: (One signature of Systems or Operations E.Wis required if the SeismicCapsbety Approved: (Signatures of as Seismic Capsbesty Engmeers on the Seismic Review Team (SRT) are Engineers deem it necessary.) required, there should be at leasttwo on the SRT. AR signatories should agree wNh sN the entries and j condusions. One signatory should be a licensed professenal .) Dan Fiorello
// / ff Print or Type Name ig6aiture Date Print or Type Name Signature Date Dimitrious Antonopolous [
Signature / Date 27/9[ Print or Type Name Signature Date Print or Type Name Print or Type Name Signature Date Print or Type Name Signature Date
i O . J J PEACH BOTTOM ATOMIC POUVER STATION SCREENING VERIFICATION DATA SHEET (SVDS) .[E l Eq. Eq. ID Equipment Description Bldg. FL EL Room Bose Et <40'? Cap Demd. Cap > Coweets Anchor Interact Equip j Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 HD41ee Dmsed esemer 127 DG-9 151 Y BS GRS Y Y WA Y Y to E4 DG CARDOX HEAT DETECTOR HD41ee HD417A E4 DG CARDOX HEAT DETECTOR Diesel Geweer 127 DC-9 151 Y BS GRS Y Y WA Y Y is BO 417A is HD417e E4 DG CARDOX HEAT DETECTOR th*'el G**8h' 127 DG-9 151 Y BS GRS Y Y WA Y Y HD417s is HD4 tea E4 DG CARDOX HEAT DETECTOR Deensomweur 127 DC-9 151 Y BS GRS Y Y WA Y Y HD41eA ig HD41ee E4 DG CARDOX HEAT DETECTOR Dneed oewmar 127 DC-9 151 Y BS GRS Y Y WA Y Y HD41ee is HD41e4 E4 DG CARDOX HEAT DETECTOR Dnem Gemmer 127 DG-9 151 Y BS GRS Y Y WA Y Y HD41e4 19 HD41se E4 DG CARDOX HEAT DETECTOR Deses omwear 127 04-9 151 Y BS GRS Y Y WA Y Y HD41ee 20 omC2ie DIESEL CO2 SYSTEM ELECTRICAL CONTROL Dieses oewmar 127 00-3 127 Y BS GRS Y Y Y Y Y onc21e 20 onc47e Et DG ROOM SUPPLY TEMP CONTROL 0" G8"8'r 151 DG 13 151 Y BS GRS Y Y Y Y Y Ticao272 20 onc21e DIESEL CO2 SYSTEM ELECTRICAL CONTROL Dmeseoeweer 127 DG-5 127 Y BS GRS Y Y Y Y Y (20S102) , cocrie oscere E2 DG ROOM SUPPLY TEMP CONTROL Di essGewmar 151 DG-15 151 Y BS GRS Y Y Y Y Y 20 Ticio273 l 20 occ2ie DeESEL CO2 SYSTEM ELECTRICAL CONTROL Disees Geweer 127 DG-7 127 Y BS GRS Y Y Y Y Y occ216 Cerencosort Coruscesort As the informagen contained on file Screening VertReston Data Sheet (SVDS)lo, to sie best of our The Informagen p.truided to tie Suomicrat=h"y Engineers sogenSng systems and opersuone of the knowiedge end beast. coned and accureen, *As informenon" includes each eney and corwe==vi(whether equipmect contained in sie SvDS is, to the best at our knowledge and bener, conect and occurate. vertned to be seismicacy edequeen or nos). Approved (One signature of Systems or Opere8cne Engineerle required Nthe Seismicr ap=8eer , Approved. (Signahees of as Setemic r ap=huny Engineers on sie Seismic Revleur Team (SRT) are Engineers deem It riacmenery ) required; there should be et least two on the SRT. As signosortes should egree wNh og the anstes and j ' conduelone. One sipistory should be a noensed profeeskms engineer-) DariFe p/ s /t, f[ Print or Type Name Date Print or Type Name Signature Dele
" ['Sidneture Dimitrious Aritortopolous
_ -; M7[ Print or Type Name Signature Dele Print or Type Name Signature Date i Print or Type Nome Signature Date Print or Type Name Signature Date l
PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [$ Eq. Eq. ID Equipment Description Bldg. FL EL Room Base El. <40'? Cap Demd. Cap > Cavests Anchor interact Equip Cl PIMS 10 Spec. Spec. Demd7 OK7 OK7 OK7 OK7 20 ocC479 E3 [WG ROOM SUPPLY TEMP CONTROL Dioed Gene'* 151 DC-17 151 Y BS GRS Y Y Y Y Y TICw74 20 eDC21e DIESEL CO2 SYSTEM ELECTRICAL CONTROL Damed Genereer 127 [WG-9 127 Y BS GRS Y. Y Y Y Y cDC21e 20 cDc47s E4 DG ROOM SUPPLYTEMP CONTROL D"8 G8""*'" 151 DG 19 151 Y BS GRS Y Y Y Y Y TICM75 21 mToes Et DG LUBE OIL STORAGE TANK Dioed Generm 127 DC-3 127 WA WA WA NA Y Y Y Y onToes 21 CA N Et DG COOLANT EXPANSION TANK DhmsGenmusw 127 DC-4 127 WA WA WA NA Y Y Y Y oAroer OAN DIESEL FUEL OIL STORAGE TANK Diessi Genww 113 YARD 113 N/A WA WA N/A Y Y Y Y 21 cATose coms E2 DC LUBE OIL STORAGE TANK DioeW Genwm 127 DC-5 127 WA N/A N/A N/A Y Y Y Y 21 ceTeos 21 cew E2 DG COOLANT EXPANSION TANK D**G""*'* 127 DG4 127 N/A WA N/A WA Y Y Y Y 21 co m DESEL FUEL OIL STORAGE TANK D'W Generse" 113 YARD 113 N/A N/A N/A NA Y Y Y Y j ceTose 21 octose E3 DG LueE OIL STORAGE TANK Dame Gens'* 127 DG-7 127 N/A N/A - N/A N/A Y Y Y Y ocms octeer E3 DG COOLANT EXPANSION TANK Dems Genes
- 127 DG4 127 N/A WA N/A N/A Y Y Y Y 21 octoe7 21 oc m DIESEL FUEL OIL STORAGE TANK D**' 08""" 113 YARO 113 N/A N/A N/A N/A Y Y Y Y Cerencomort Cerienceson.
AB the Irdormation contained on this Soesning vertikanon Date Sheet (SVDS)Is. to tie best or our The Intbrmeson provided to the Setemic t'apahuny Engineers regensne eyeleme and operegone er the knessedge and bemer, conect and securses. Aa hw indudes eedi erty and condusion (whether equiprnent contained in the SvDS to, to the best or our knowledge end tener, conect and secursie. vermed to be seismicour =*='e=*= or no4 Approved (One signature or Systems or Operemons Engineer le required N the Seismic Capahesy Approved (Signeeures or en Sebrnic t'=r asu rEngineers on the Seismic Review Team (SRT) are Engineers deemit necessary.) required; there enould be et least two on the SRT. As signosorise should agree wilh sA the er$tes and j mndusions. One signatory should be e beensed professional .) Den H h// , p /zkgh[ Print or Type Name / Date Print or Type Name Signature Date Dirrutrious AntOnOpOIOus . _ &7 [ Print orType Name Signature Date Print orType Nome Signature Date
\
Print or Type Name Signature Date Print or Type Name Signature Dato
I PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [$ ; Eq. Eq. ID Equipment Descriphon Bldg. Fl. EL Room Base El <40'? Cop Demd. Cap > Coweets Anchor Interact Equip Cl Spec. Spec.' Demd? OK7 OK7 OK7 OK? PIMS ID 21 00T088 E4 [WG LUBE OIL STORAGE TANK M Genessor 127 DG9 127 NA N/A WA WA Y Y Y Y octose 21 OC N E4 (WG COOLANT EXPANSION TANK Dimi omrator 127 [WG-10 127 WA N/A N/A N/A Y Y Y Y , cotoe7 21 cor3e DfESEL FUEL Cil STORAGE TANK w Genweier 113 YARD 113 N/A N/A N/A N/A Y Y Y Y co - i 9 AR the inibnneton conselnad on this Screening Vertacagon Does Sheet (SVDS) le. to the best of our The indbrmagon provided to sie seismic CapabERy Engineers regen 5ng synisme and operemone of the knowledge and bemer, conect and acxurene AR inibnneson includes each er*y and concluelon (whether equipment contained m the SvDS is, to the best or our knossedge and bouer, conect and securses. vermed to be setemicesy adequeen or non. Approvet (One signature or Syenema or Operellone Engineer is required if eie Setemic Capsbeir Approvee (Signeluresof as Seismict'ar adorEngineersontheSeismicReviewTeam(SRT)are Engineers deem R necessary) requesd,; _ sue,r.there shoukt be et le,ast two on the
~ e-t.- - SRT. AR eignatories should agree wth mA the entries and oen n-~ 9/A ?;J /dehr Date Print or Type Name - / $ignature ~ Date Print or Type Name Sk;;neture Dimitrious Antonopolous . / Yp((
' Date Print or Type Name Signatute Date Print orType Nome Signature i
Signature Date Print or Type Name Signature Date Print orType Name
l m ,
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PEACH BOTTORE ATORMC POWER STATION [d SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Equipment Descriptkm Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Cavests Anchor Interact Equip i Cl PIMS ID Spec. Spec. Demd? OK? OK7 OK7 OK7 ; coess D6eseloenerseer igy DG4 127 Y GERS CRS Y U ! 1 400 V Et DG MCC 00853 (E124-D A) U Y U oce53 f 1 00e54 480 V E2 DG MCC 00854 (E234-D-A) D"8G 6 127 DG4 127 Y GERS CRS Y U U Y U r e234 f 0e855 480 V E3 DG MCC 00855 (E324-D-A) D 0*"*'esar 127 DG8 127 Y GERS CRS Y U U Y 1 U l E324 y cesse Deeens omweier 127 0 0-10 Y GERS CRS Y 1 480 V E4 DG MCC 00856 (E434-EM) 127 U U Y U ! j E434 10 Po40541 E1 DG 8LDG VENT SUPPLEMENTAL SUP FAN Dwees osewseer 127 DG4 149 Y BS GRS Y Y Y Y Y OAVO91 DAMPER , Po4-doF40!Mo41
}
qg Po40542 E2 DG BLDG VENT SUPPLEMENTAL SUP FAN Doest oorwater 127 DGe 149 Y BS GRS Y Y Y Y ' Y 08V001 DAMPER L Po44aF4054o2 gg Po405e3 E3 DG 8LDG VENT SUPPLEMENTAL SUP FAN D6eeni Generuser 127 DG8 149 Y BS GRS Y Y Y Y Y I OCV001 DAMPER Po4 doreo8404s : go pocose4 E4 DG 8tDG VENT SUPPLEMENTAL SUP Fang Dieses Gerweiar D G10 127 149 Y BS GRS Y Y Y Y Y { ODVO91 DAMPER i Poo dor 4o5ee4 l 17 ono12 Et STAND 8Y DIESEL GENERATOR DW G*"**r 127 DG3 127 Y BS GRS Y N Y N N onoo12 l 17 08012 E2 STAND 8Y DIESEL GENERATOR D 0*""esar 127 DG5 127 Y BS GRS Y N Y N N osoo12 ! 17 oco12 E3 STAND 8Y DOESEL GENERATOR D"' G8"888' 127 DG7 127 Y BS GRS Y N Y N N ocoo12 ; 17 0Do12 E4 STAND 8Y DIESEL GENERATOR D G*" soar 127 DGS 127 Y BS GRS Y N Y N N I oDoct2 i Cerencation. Certniessort As the informoeon contained on this Screening Vertecemon Data Sheet (SVDS) is, to Wie boat of our The Ineormagon provided to the Setemic CapabEly Engineers negansne systerne and operseone of the knoutedge and bemer, coned and accurate As informoeon"indudes escfi eney and condugion (whelhor equipment conleined in the SVDS te, to the best of our knowledge and baser, correct and somrete. vertned to be setemicacy adequate or nott Approved- (One signature of Systems or Opersenne Engineer is required Itie Seismic f'aFMey Approved- (Signatures of as Seismic Capsbety Engineers on Wie Seismic Review Team (SRT) are Engineers deem it necessary.) required; there should be at least two en the SRT. As signosortes should agree wah as the enertes and j condusione. One signatory should be a Bcensed profeselonel engineer ) fy[Ag/g Dari Fiorello [// Print or Type Name Kgflature Dele ' Print or Type Name Signature Dale Demetrious Aritoriopolous [ 7 / [ Print or Type Name Signature ' Date Print or Type Name Signature Dele
- James W Print or Type Name (/
O[hMQ Signature kjfM Date Print or Type Name Signature Date _ _ - = _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ - _ . _ - _ _ _ _ - _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ - - - _ _ _ _ - _ _ _ _ _ - _ _ _ - - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _
I w) PEACH BOTTOM ATOlWC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <4(r? Cap Demd. Cop > Cavests Anctier kiteract ' Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK? OK7 21 onTe Et DG FUEL OIL DAY TANK DW Ge'** 127 DG4 127 WA WA WA WA Y Y Y Y ontoe 21 oste E2 DG FU(._001. DAY TANK O'*d G8"*'* 127 DG-5 127 MA WA WA WA Y Y Y Y esTom 21 oste 5 Et DG STARTING AIR RESERVOIR (AUTOn4ATIC Dmmes omerskr 127 DG-3 127 WA NA WA WA Y Y Y Y START) 21 ocTe E3 DG FUEL OIL DAY TANK Donal Germehr 127 Og.7 j27 gA gA gA gA y y y y ocTom 21 CDT# E4 DG FUEL OIL DAY TANK DW Geriorskr 127 DC-9 127 MA NA NA WA Y Y Y Y oDToe 21 eDT95 E2 DG STARTING AIR RESEm/OtR (AUTOMATIC DW Geriorskr 127 D G-5 127 N/A WA WA WA Y Y Y Y START) 21 orTes E3 DG STARTING AIR RESERVOIR (AUTOMATIC Dead Georskr 127 DC-7 127 WA NA N/A WA Y Y Y Y START) orToes 21 OHis5 E4 DG STARTING AIR RESERVOIR (AUTOMATIC poses Generskr 127 OfG-9 127 N/A WA WA N/A Y Y Y Y START) oHvoos Cerenesmort Cessnesson. As the insbemason mntained on ens Screening vertEstion Dale Shset (SVDS)Is, to sie best of our The indbrmosan provided to the Seiervde Capahmer Engineere regarteng systems and operseone of Wie knowledge and beast ocned and scarste *As informenorr tidudes each enry and condusen (ehether equipment contained in the SVDs is, to the best of our knowledge and beast. mned and accurses. vermed to be seismicacy adequate or noo. Approved (One signesure of Systems or Opersenne Engineer le required N the Seismic Copeasy Approved (Signatures at as Seismic Par =hemy Engineers on the Seismic Review Team (SRT) are Engineere deem a necessary.) required; there should be at seest two on the SRT. As signatortes should agree with e5 the entries and j mndusens. One signesory should be a lkansed proposelonel engineer.) Dan Fiorello
/ /g /g Date Print or Type Name Signature Date Print or Type Nome W '
l [ Print or Type Nome Signature Dale Print or Type Name Signature Date 0* & 0* $ l Print or Type Nome Signature Date Print or Type Name[ j Signature Q Dole m- -:------..~-- - _ . - _ - - _ - - -- - - - - - - _ - - - - - - - , - - - - ---___J
Y b PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) [d Eq. Eq. ID Equipment Desenption Bkig. Fl. EL Room Base EL <407 Cap Demd. Cap > Caveats Anchor interact Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 y Ao24343 SCRAM DtSCHARGE VOLUME INBOARD Reeder Bug -U2 135 R2-22 135 N/A ABS CRS Y N N/A Y N ISOLATION DRAIN W AO-20433 y ACJ433s SCRAM DISCHARGE VOLUME OUTBOARD Reedor aus-U2 135 R2-22 135 N/A ABS CRS Y Y N/A Y Y ISOtATION DRAIN W . Ao-243438 [ eA wn 12415 RWCU INLETINBOARD ISOLATION VALVE D W -U2 134 DMl2-28 134 N/A ABS CRS Y Y N/A Y Y W12-12415 r* 3AsN RHR PP 3AP035 SUCTION STRAINER Tm Repur-U3 111 Torus 111 N/A N/A N/A N/A Y N/A Y Y 3As7ee 3es N RHR PP 3BP035 SUCTION STRAINER Tm Reper-U3 111 Torus 111 N/A N/A N/A N/A Y N/A Y Y o 3esres 3cs7eo RHR PP 3CP035 SUCTION STRAINER Torue Roper-U3 111 Torus 111 N/A N/A N/A N/A Y N/A Y Y 0 3csres ; 30s N RHR PP 3DP035 SUCTION STRAINER Torum Reper -U3 111 Torus til N/A N/A N/A N/A Y N/A Y Y O 3os7ss 0 3,y," HPCI SUCTION STRAINER Reacier DHD -U3 111 Torus 111 N/A N/A N/A N/A Y N/A Y Y 6 f Certificanon: Certificabon. AR the infbrmation cxmtsined on this Screerdng Venfication Data Sheet (SVDS) is, to the best of our The information provided to the seismic Capabihty Engmeers regarding systems and operations of the knowledge and beNef, correct and accurate "AB information* Includes each entry and condusion (whether equipment contained in the SVDS is, to the best of our knowledge and benef, correct and accurate verified to be seismicapy adequate or not). Approved (One signature of Systems or Operatons Engineer is required if the Seismic Capabinty Approved. (Signatures of at Seesmic Capabihty Engineers on the Seismic Review Team (SRT) are Engmeers deem it necessary ) required; there should be at least two on the SRT. At signatories should agree with all the entries and j conclusions One signatory should be a ticensed professional engineer.) James Flaherty y(( f k(g[ff Print or Type Name Signature Date Print or Type Name Signature G Date Dimitrios Antonopoulos [ /E[/ph Print or Type Name Signature ' Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
(" p h- / PEACH BOTTOM ATOMIC POWER STATION p.,, , SCREENING VERIFICATION DATA SHEET (SVDS) 12tims Eq. Eq. ID Equipment Desenption Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Caveats Anchor interact Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 20 20 Coo 3 REACTOR AND CONTAINMENT COOUNG AND Tutune eMg -U2 165 T2-100 165 N/A ' ABS RRS Y Y Y Y Y ISOtATION 20ccos 20ccosc RCIC CONTROL PANEL Tata suo-U2 165 T2-100 165 N/A ABS RRS Y Y Y Y Y 20 20co04c 20coasA REACTOR MANUAL CONTROL PANEL Twt *= eus-U2 165 T2-100 165 N/A ABS RRS Y Y Y Y Y 20 20coosA 20 20c012 PLANT SERVICES CONSOLE Twt *w sus-U2 165 T2-100 165 N/A ABS RRS Y Y Y Y Y 20C012 20c124 CRT AND RFPT TEST PANEL Twt *w eMg -U2 165 T2-100 165 N/A ABS RRS Y Y Y N N 20 20C124 20 2AC272 HPCI STEAM LEAK DETECTION CABINET Twt *w sus -U2 165 T2-100 165 N/A ABS RRS Y Y Y Y Y 2Ac272 2eC272 HPCI STEAM LEAK OETECTJON CABINET Tut *wsus U2 165 T2-100 165 N/A ABS RRS Y Y Y Y Y 20 2ec272 20 30 Coo 3 REACTOR AND CONTAINMENT COOUNG AND Twt *w eMg -U3 165 T3-100 165 N/A ABS RRS Y Y Y Y Y ISOLATION wvm socco4c RCIC VERTICAL BOARD Tut *w eeg -U3 165 T3-100 165 N/A ABS RRS Y Y Y Y Y 20 socooec 20 30CoosA REACTOR MANUAL CONTROL PANEL Tatmseg U3 165 T3-100 165 N/A ABS RRS Y Y Y Y Y socoosA 20 30Co12 PLANT SERVICES CONSOLE Tates eMg -us 165 T3-100 165 N/A ABS RRS Y Y Y Y Y 30co12 20 soc 124 CRT AND RFPT TEST PANEL Tut *w seg -93 165 T -00 165 N/A ABS RRS Y Y Y N N 30C124 Certmcation. Certmenton. As the information contained on this Saeoning Vermca5on Data Sheet (SVDS) Is, to the best of our The Irdormation provkted to the Seismic Capotely Engineers reconNng systems and operations of the knowledge and benet, mrred and accurate 'As informenon includes eedt entry and condusion (whether equipment antained in the SVDS is, to the best of our knowledge and beNef, corred and accurate vertned to be seistnicacy adequate or not). Approved: (One signature of Systenw w Opatkms Engineer is required N the Sersmic Capetety Engineers deem it necessary.) Approved (Signatures of as Seismic Capability Engineers on the Seismic Review Team (SRT) are requhed; there should be at least two on the SRT. AR signatories should agree with at the entries and j conclusions. One signatory should be a scensed rn ; engineer.) Richard Daniels 8.T. h[27[9f Date Signature Date Print or Type Name Signature Print or Type Name Dimitrious Antonopolous j '
/2-[g,7[yf Print or Type Name Signature Date Print or Type Name Signature Date Signature Date Print or Type Name Signature Date Print or Type Name
.. - ...- - .- - . _ - - - - - ~ . - . - . - - . . . ~ . . - . - - ~ . - - .-..- . _.- -- - . .. . ....- - -.-- - .
PEACH BOTTOM ATORNC POWER STATION pe,e SCREENING VERIFICATION DATA SHEET (SVDS) iwises Eq. Eq. ID Equipment Description Bkig. FL EL Room Base EL <40'? Cap Demd. Cap > Caveste Anchor interact Equ5 ; Cl pgMS to Spec. Spec. Demd7 OK7 OK7 OK7 OK7 20 sac 272 HPCI STEAM LEAK DETECT:ON CABINET Tuerm aus-U3 165 T3-100 165 WA ABS RRS Y Y Y Y Y P sac 272 20 seC272 HPCI STEAM LEAK DETECTION CABPfET Tumen ene.us 165 T3-100 165 MA ABS RRS Y Y Y Y Y 20 00C2m EMERGENCY PROTECTION RELAY BOARD Tumensus-U2 165 T2-100 165 WA ABS RRS Y Y Y N N
)
20 30c2se EMERGENCY PROTECTION RELAY 80ARD Tueen sus-U2 165 T2-100 165 WA ABS RRS Y Y Y N N oocarse j 20 coc2sc EMERGENCY PROTECTION RELAY BOARD TueeneMe-U2 165 T2-100 165 WA ABS RRS Y Y Y N N ! aa m ac 20 aoc2so EMERGENCY PROTECTION RELAY BOARD Tumeneus-U2 185 T2-100 165 WA ABS RRS Y Y Y N N [ i coco 2eo i i l i Cerenceson. Certuicecon. As the howmason contained on ene Screening Verukseen Dale Shoot (SVDS)is, h me best of our The inibnneson provided to me Salemic r'W Engineore regenNng systems and operegone of me . knancedge and bemer, correct and accurses *As insormemon"incsudes seca eney and concsusion (whosher equipment nonesined in me SvDS te. to the best or our knoweedse and meest, coned and accurene. vermed to be seismicour adequate or nog. Approvect (One eisnature of Systems or Operemone Engheerle required tthe Seismic r'=r=May , Approvee (sagnelures or es Setemic t'ar=May Engineers on me Salemic Revleet Team (SRT) are Engineare deemit m.) l requket there should be et least two on me SRT. AE eigneezies should agree wilh og me enties and ; i condusions. One signosary should be a scanned prosessioner engineer.} Richard Darnels [ b b8f"*bSignature
/2/thf7 Date Print or Type Name Signature Date Print orType Name Domstrious Print or Type Name
.d Signature /
_ k ks7[ff" Date Print or Type Name Signature Date i i Print or Type Name Signature Date Print or Type Name Signature Date i
N w ./ ._.? PEACH BOTTOM ATOMIC POWER STATION p.,, i j SCREENING VERIFICATION DATA SHEET (SVDS) satts/es l Eq. Eq. ID Equipment Descrip6on Bldg. FL EL Room Bene El. <40'? Cap Demd. Cap > Coweets Anchor Interact Equip l Cl PIMS ID Spec. W Demd? OK7 OK7 OK7 OK7 Ao2-todeA RHR LOOP A CHECKVALVE Dyne -U2 134 OM2-21 134 WA N/A N/A Y Y N/A Y Y 0 AO-2-100eeA 0 Ao2-10-see RHR LOOP B CHECKVALVE DT"a-U2 134 DM2-18 134 N/A N/A N/A Y Y N/A Y Y l 1 AO-2-104ees O A02 2me HPCIDISCHARGE CHECKVALVE Runar me-U2 135 R2-30 135 N/A N/A N/A Y Y N/A Y Y Aoo-2sete vRv2-2. sea VACUUM REUEF VALVE FOR MAIN STEAM UNE Drynes -U2 158 DM2-28 158 N/A N/A N/A Y Y N/A Y Y 0 REUEF W A vRv-2. == vRv2-2.ees VACUUM REUEF VALVE FOR MAIN STEAM LINE orynes-U2 158 DM2-29 158 N/A N/A N/A Y Y N/A Y Y o REUEF W 8 VRv.2. === o vmV2440sec VACUUM REUEF VALVE FOR MAIN STEAM UNE Drynes -U2 158 DM2-28 158 N/A N/A N/A Y Y N/A Y Y REUEF WC VRv44240sec o vRv2-240st0 VACUUM REUEF VALVE FOR MAIN STEAM UNE Drywee -U2 158 DM2-27 158 N/A N/A N/A Y Y N/A Y Y REUEF W D vRv-242:oseD 0 VRV244oseE VACUUM RELIEF VALVE FOR MAIN STEAM UNE Drywee -U2 158 DM2-29 158 N/A N/A N/A Y Y N/A Y Y REUEF W E _4..se. O VRV244oseF VACUUM REUEF VALVE FOR MAIN STEAM UNE Dryees -U2 158 DM2-29 158 N/A N/A N/A Y Y N/A Y Y REUEF W F _ e, vRV244aseG VACUUM REUEF VALVE FOR MAIN STEAM UNE orysse -U2 158 DM2-35 158 N/A N/A N/A Y Y N/A Y Y O REUEF WG
-4 seo ;
O vRV244ceeH VACUUM REUEF VALVE FOR MAIN STEAM UNE Drywes -U2 158 DM2-34 158 N/A N/A N/A Y Y N/A Y Y l REUEF W H ! _4 e. WRv2-240ssJ VACUUM REUEF VALVE FOR MAIN STEAM UNE Dryses-U2 158 DM2-32 158 N/A N/A N/A Y Y N/A Y Y O i REUEF WJ l to,_ _ - - Se _ _ -gs,s me .dc.e, eo, A._,e_ _ .d. - D.e.She _ ~ equipment contained in the SvDS le to the best or our knoudedge and beset, correct and accursen knoudedge and beast, correct and accurses As insormosoreine* a== each eney and conesusion enhether vertRed to be solemicepy aday* or ncQ. Approv4Mi- (One signature of Systems or Opereenne Engineerle seguired if to Seismic r ap=heer Approved (Signatur:e of as Seismic Capabety Engineere on the Setemic ReviewTeam (SRT) are Engineers deemit noosenery.) requiret. there enould in at inest two on sw SRT. As signmeories shoued agree wah as the enene and j
-a engineer.)
conclusions. ~ One signmeory shoued aMrr be aLr-r 04ALL Print or Type Name Signature Date Print or Type Name Signature Date James Flaherty /24/-f[ Date Print or Type Name Signature Date Print or Type Name ' [ Signature , i Print or Type Name Signature Date Print or Type Name Signature Date
T I s_.- PEACH BOTTOM ATORAC POWER STATION Page2 i SCREENING VERIFICATION DATA SHEET (SVDS) 12ttems , Eq. Eq. ID Equipment Descriptkm Bldg. FL EL Room Base EL <4'T7 Cap Demd. Cap > Caveste Andtor interact Equip i Cl PIMS ID Spec. Spec. Domd? OK7 OK7 OK7 OK7 i vm2-24ossK VACUUM REUEF VALVE FOR MAM STEAM UNE orywee- U2 158 DM2-M 158 WA WA WA Y Y WA Y Y 0 ! REUEF W K ! vetv.m - _ i 0 VRv2-2 acost VACUUM REUEF VALVE FOR MAM STEAM UNE orywes-U2 150 DM2-32 158 WA NA NA Y Y WA Y Y j
*MEUEF WL vRv4m4oest ;
7 Ao2414eoA A MAM STEAM UNE IN80ARD ISOt.ATION VALVE DT"es.u2. 1M DM2-18 134 WA ABS CRS Y N WA Y N A6241Amn. 7 Ao2414soe 8 MAM STEAM UNE INBOARD ISOt.ATION VALVE orywas -U2 1M DM2-18 134 MA ABS CRS Y N N/A Y N j t Ao-2e1A4eos 7 Ao2414eoc C MAM STEAM UNE IN80ARD ISOLATION VALVE orywes -U2 iM DM2-19 134 WA ABS CRS Y N N'A Y N Ao..s - i 7 mo2414eoD D MAM STEAM UNE IN80ARD ISOLATION VALVE orysee -U2 1M DM2-20 134 WA ABS CRS Y N WA Y N Ao-241a m 7 mo2414esA A MAM STEAM UNE OUTBOARD ISOtATION Reeder sus-U2 133 R2 30 135 NA ABS CRS Y N N/A Y N i VALVE l Ao-241. . _ . ; 7 Ao2414ses a MAM STEAM UNE OUTBOARD ISOLATION Reedor Bug -U2 135 R2-30 135 N/A ABS CRS Y N N/A Y N i VALVE l Ao-241. . _ _ _ _ , 7 Ao2e14eec C MAIN STEAM UNE OUTBOARD ISOI.ATION Reedersus U2 135 R2-30 135 N/A ABS CRS Y N N/A Y N , VALVE i Ao-241A4eec ; 7 Ao2414eso D MAN STEAM UNE OUTBOARD ISOLATION Reeder BMs -U2 135 R2 30 135 N/A ABS CRS Y N N/A Y N i VALVE AO-241A488o 7 Rv2m eta A SAFETY REUEF VALVE D'ywes - U2 154'-9" DM2-27 155 N/A ABS CRS N Y N/A Y N i Rv-2MW1A 7 Rv2ew18 8 SAFETY REUEF VALVE DT"es-U2 g $4.e" DM2-27 155 N/A ABS CRS N Y N/A Y N I Rv-2mais Corspcogon. Cerencellon.. As the Hbrmegon amteined on siis Screening Verletzeon Dale Sheet (SVDS) le, to tie boot of our The indbrmellon provided to tie Seismic Capabety Engineers regartAng systems and operegone of sie ! knoupledge and betet, conect and accurate, *AE informeNon" Includes each enty and concluelon (ushetter equipment contained in Wie SVDS is, to Wie best of our knoupledge and besef, correct and accurate vermed to be seismicaey adequate or nog. Approved: (One signeeure of Systems or Operstone Engineer le require ( N the Setemic CapabMy Approved: (Signatures of eA Seismic Pat = heer Engineers on the Setemic Revleur Team (SRT) are Engineers deem R nomesary.) , required; Wiere should be et least teso on the SRT. AE eignatortes should agree with e5 Wie enkles and
^
J conclusions. One signalary should be a Noensedr_ __ Dari FsOfello
/ /9[6 Date Print or Type Name Signature Date Print or Type Name [ hignature !
James W ph i T Print or Type Nome Signature Q Dale Print or Type Name Signature Dale i Print or Type Name Signature Date Print or Type Name Signature Date f'
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. -./
PEACH BOTTOM ATORMC POWER STATION page SCREENING VERIFICATION DATA SHEET (SVDS) inrisms Eq. Eq. ID Equipment Deecription Bldg. FL El. Room Beee El. <4(Y? Cap Demd. Cap > Cavests Anchor Intered Equip Cl PSAS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 7 RV242471C C SAFETY REUEF VALVE oryne.u2 1WY Dm2-27 155 MA ABS CRS N Y WA Y N ; RV-242471C y N242471o D SAFETY REUEF VALVE Dryne.U2 1W-9" Dm2-27 155 WA ABS CRS N Y Pe/A Y N RV-242471D 7 Rv242471E E SAFETY REUEF VALVE Dryme .u2 t w.g" Dm2 27 155 WA ABS CRS- N Y WA Y N W-242471E y RV242471F F SAFETY REUEFVALVE D'yme . U2 1 W.9" Dm2-27 155 MA ABS CRS N Y N/A Y N mam471F 7 W242&10 G SAFETY REUEF VALVE D'yme U2 q w.e= Dm2-27 155 MA ABS CRS N Y N/A Y N wa424710 7 Rv242471H H SAFETY REUEF VALVE D'yme .u2 q w.9" Dm2-27 155 MA ABS CRS N Y N/A Y N Rv442471H 7 W242471J J SAFETY REUEF VALVE D'yme u2 I W.9* Dm2-27 155 N/A ABS CRS N Y N/A Y N t Rv4424712 y RV242471K K SAFETY REDEF VALVE D'yme .02 1 W-9" Dm2-27 155 N/A ABS CRS N Y N/A Y N Rv-242471x y RV242471L L SAFETY REUEF VALVE D'yme .U2 154'# Dm2-27 155 N/A ABS CRS N Y N/A Y N RV442471L 8A M02-1241e RWCU INLET OUTBOARD ISOLATION VALVE # "8'rous U2 165 R2-33 165 N/A DOC CRS Y Y N/A Y Y MO.2-1241e eA M024341e HPCI DISCHARGE TO FEEDWATER UNE A Roomysue.U2 135 R2-30 135 N/A ABS CRS Y N N/A Y N MO-2-2341e 8A Mo26 UI2 HPSW DISCH INLET OUTER W
,,,,, y94 ECT-1 114 Y BS GRS Y Y N/A Y Y t o 2 4 2eoeA Certlicagorr Cerencallart As the irsormogon contained on see Screening Verutcselon Does Sheet (SVDS) le. to the best of our The information provided to sie Setemicrat=May Engineers regenan0 systems and operemone of tie knowtedge and beset corred and secwate equipment conseined in the SVDS le. to the best of our knowledge and toast, conect and secwate verined to be setemicsey adequeen or non. "As informsuon indudes each eney and condusion (whether W (One signature of Systems or Operegone Engineer le required llSie Solomic Capabety Approved- (Signatures of sit Seismicr=r=May Engineers on sie Solomic Revleur Team (SRT) are Engineere doom it noosesary.) '
required; there should be at least two on sie SRT. AN signatories should wlet es me entiee and j mncluelons. One signatory should be a Bmneed r- _^ Dan Fiorello / // ff Date Date Print or Type Name Signature Print or Type Name / Signature
- % CA9ht nW Print or Type Name Signature Q Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Nome Signature Date
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t PEACH BOTTOM ATOMIC POWER STATION page 4 SCREENING VERIFICATION DATA SHEET (SVDS) 12rtstos , Eq. Eq.10 Equpment Desenption Bldg. FL EL Room Base EL <40'? Cap Demd- Cap > Caveats Anchor Interact Equip C3 PIMS ID Spec. Spec. Demd? OK7 OK7 OK? OK? M026 E Co*g ECT-1 114 Y BS GRS Y Y N/A Y Y 8A U/2 HPSW BAY INLET INNER _ , 6 0 2 4 2804e 18 2 Aces RX VESSEL LVL ANO PRESSURE INST RACK A R**sm BMs - U2 165 R2-40 165 N/A ABS CRS N N N .Y N 2Acos5 18 2AC91 JET PUMP INST RACK A RusaeMe-U2 135 R2-81 135 N/A ABS CRS Y Y Y Y Y , i 2AC091 18 2eces RX VESSEL LVL AND PRESSURE INST RACK B RomsareMg U2 165 R2-40 165 N/A ABS CRS N N N Y N ! 2ecos5 13 2ecs' JET PUMP INST RACK g Reess BMs U2 135 R2-29 135 N/A ABS CRS Y Y Y Y Y 2ecooi 20 2Ac2s5 RESERVOIR FLOW PUMP BAY MO-2004A ,,,, W 3,4 ECT-1 114 Y BS GRS Y Y Y Y Y 2Ac2 5 20 2ec2ss RESERVOIR FLOW PUMP BAY MO-29048 %coeg , ECT-1 114 Y BS GRS Y Y Y Y Y [ 2eC265 21 2Ams INSTRUMENT N2 ACCUMULATOR FOR RV-71A DW U2 154 DNv2-27 154 N/A N/A N/A N/A Y Y Y Y 2AT545 21 2eT545 INSTRUMENT N2 ACCUMULATOR FOR RV-718 DW - U2 154 DNv2-27 154 N/A N/A N/A N/A Y Y Y Y 2t W5 21 2cTt 55 INSTRUMENT N2 ACCUMULATOR FOR RV-71C D W -U2 154 DNv2-27 154 N/A N/A N/A N/A Y Y Y Y 2CT545 21 2Gms INSTRUMENT N2 ACCUMULATOR FOR RV-71G o W -U2 154 DNv2-35 154 N/A N/A N/A N/A Y Y Y Y 2GT545 21 2KT545 INSTRUMENT N2 ACCUMULATOR ory en-u2 154 tWW2-34 154 N/A N/A N/A N/A Y Y Y Y 2KT545 Cerencason. Certmesson. An uw k*wmaton contained on this Screening Vertkneon Data Sheet (SVDS) is, to the best of our The Informagon prowlded to the Se6smic Capabety Engineers regereng syse e ms and operssons of tw knowiedge and bener, corred and accurate *As inebrmeeen" andudes endi eney and conduelon (whether equioment contained in the SVDS is, to the best of our knou4 edge and bemer, correct and securate. vermed ts be seismiempy adequate or nog. Approved (One signature or Systems or Operssons Enghwer is required N the Setsmic Capsbety Apprt,ved (Signatures of sq Seismic Capabety Engineers on the Seismic Rowlew Team (SRT) are Engineers deem it necessaiy.) required, there should be at toest two on the SRT. AC signatories should agree with at the entries and j condusions. One signatory should be a noensed prosessioner engineer.) Dari FM Print or Type Name (( w
' gnature
"~
/ /9 Date
[ Print or Type Name Signature Date James Flaherty Q hj j l Date Print or Type Name Signature Q Date Print or Type Name Signature
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Print or Type Name Signature Date Print or Type Name Signature Date .
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I i I
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i' ! PEACH BOTTOM ATOGRC POVVER STATION Pese s SCREENING VERIFICATION DATA SHEET (SVDS) 1artees Eq. Eq. ID Equipment Description BIdg.~ FL EL Room Base EL <40'? Cap Demd. Cap > Coweste Anctior Intemet Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK7 OK7 CK7 SA mos-tosse . RHR HX 38E024 HPSW OUTLET VALVE Ramsar Bede-u3 11e R3-te 116 Y BS GRS Y Y MA Y Y moo-toosse eA r>os-tosoo RHR HX 30E024 HPSWOUTLETVALVE R**'sar esse -us ile R3-19 116 Y BS GRS Y Y MA Y Y uo4 to4Isso eA N Uf3 HPSW SAYINLET OUTER W 9,4 ECT-1 114 Y BS GRS Y Y N/A Y Y N eA MON Ur3 HPSW SAYINLETINNER ceanie ECT-1 114 Y BS GRS Y Y N/A Y Y
, 9,4 13 ances RPS INSTRUMENT RACK "'"8" M -U3 185 R3-40 165 N/A ABS CRS N N N -Y N ancoes
. 18 3*C'1 JET PUMP INST RACK A 88"8 olds U3 135 R3-81 135 NIA ABS CRS Y Y Y Y Y ancest 18 seces RPS INSTRUMENT RACK Rommer side -US 135 RS-2e 135 N/A ABS CRS Y Y Y Y Y secoes 18 seco1 JET PUMP INST RACK 8 messor ese.us 135 R32e 135 N/A ABS CRS Y Y Y Y Y 3eCost E Caoure 20 sac 2es RESERVOIR FLOW PUMP BAY MO-3e84A _ 4 ECT-1 114 Y BS GRS Y Y Y Y Y sac 2es sec2es C *9 ECT-1 114 Y BS GRS Y Y Y Y -Y 20 RESERVOIR FLOW PUMP BAY MO-30048 , 9,4 sec2es 0 '*A DIESEL *A* EXHAUST SILENCER Dw oerurma' 127 OG-3 159 N/A N/A N/A Y Y Y Y Y 0 8eA DIESELT EXHAUST SILENCER O 0"'88' 127 DC-5 . 159 N/A N/A N/A Y Y Y Y Y 1 CerWRestort Cerencesort As the inIbemosen contained on eie Saeoning VertAccean Date Sheet (SVDS) le. to tie boot of our The MIormston provided to Wie Setemicrap=Nu rEngheers reportEng systems and operemone of me knoweedse and tisser, conoce and accurses "As inIermosore indudse each envy and conesusion fuheeher equipment canamned in me SVDS is, to the best or our Imoneedse and emner, correct and secursee vertand to be secondency =navan= or nog. Approved- (One signetwo of Systems or Opermeone Engheer le requbed W the Sciende Par = Mar Approvet (Signahoes at as Sesemicrap=Nu Engheers r on the seismic Revleur Team (SRT) are Engheers deemit necessary.) requeed; more shoidd be et isent two on the SRT. As signatories shound agree allh mE the enktes and j conesunione. One signosory shouM be e scanned pran===aanst .) D8t' H / /t Print or Type Name ' Dole Print or Type Name . Signature Date James Flaherty w J - l Print or Type Name Signature Q Dele Print or Type Nome Signature Dele
\
Print or Type Nome Signature Date Print orType Nome Signature Date
~
PEACH BOTTOM ATOlWC POVVER STATION Pese e SCREENING VERIFICATION DATA SHEET (SVDS) tarisms Eq. Eq.1D Equipment Descriphon Bidg. Fl. EL Room Base EL <40'? Cap Demd. Cap > Coweets Anchor Intered Equip Ci pluS ID Spec. Spec. Demd7 OK7 OK7 OK7 OK7 0 WA DIESEL"C" EXHAUST SILENCER DelGerurm 127 DG7 159 N/A N/A N/A Y Y Y Y Y 0 ** DIESEL *tY EXHAUST SILENCER D " 8G8'"'esar 127 DS9 159 N/A N/A N/A Y Y Y Y Y cose7 480V MCC 00897(E13A4-EC-A) C"'*"o ECT-3 153 N/A GERS CRS Y N Y N 1 153 N coser 1 oosse 480 V MCC 00808 (E23A4-EC.A) _e cacen 153 ECT-4 153 N/A GERS CRS Y N Y N N 1 cosee 480V MCC00809(E43A4-ECA) _ cams 153 ECT-5 153 N/A GERS CRS Y Y Y N N oosso 2 cose* 400 V SUS E13A4 T cang 153 ECT-3 153 N/A GERS CRS Y N N N N , comee 2 cases 400 V BUS E23A4 came ECT-4 153 N/A GERS CRS Y N N N N
,,,,, 153 oness 2 ooses 480 V BUS E43A4 Em_Caserg 153 ECT-5 153 N/A GERS CRS Y N N N N ooses 4 oMQ8 LOAD CENTER XFMR (OAX28) W ECT-3 153 N/A ABS CRS N N N Y N onero 153 E-13AetoNQ8) co m caeg 4 LOAD CENTER XFMR (08X28) _ 153 ECT-4 153 N/A ABS CRS N N N Y N E-23AetooX26) 4 ocx2s LOAD CENTER XFMR (OCX28) E y _ cams 153 ECT-5 153 N/A ABS CRS N N N Y N s.43A.iocm>
0*Peo Et DG FUEL OIL TRANSFER PUMP D-I Ge'"'" 127 DG3 127 Y BS GRS Y 5 Y Y Y Y C- C-AN Wie informaton contained on 9de Sassning verInceton Dale Shoot (SVDS) is, to Wie boot of our The infamiegen provided to tie Seismic r 'M Engheers regensng systems and operseone of Wie knowiedes and bemer. conect and scoureen. As insormoson indudes each eney and conduelon (whefter eqidpment contained in the SVDS le, to Wie best of our knowledge end Bessf. coned and occurate. varmed ts be seismiceay adequeen or not). Approved: (one signeswe et Systems or operemone Engheer le regubed Nthe Selandes 'erahesy Approved (Signatures of mR Seismic Capsbety Enginesrs on sie Seismic Revleur Team (SRT) are Engineers deem it necessary.) requiret. there should be et leest two on the SRT. As signatorise shouw agree su the enetes and j mncsuetone. One signatory shouM be a Reensed r_ ^ "%.-) Dan H Print or Type Name # Q ) ,,g g / Date MW Print or Type Name - Signature Dole James Flaherty M / % Print or Type Name Signature Print or Type Name Signature Date (' Date Print or Type Name Signature Date Print or Type Name Signature Dole
Q V d
., a PEACH BOTTOM ATOMIC POWER STATION p.g. 7 SCREENING VERIFICATION DATA SHEET (SVDS) 12risms Eq. Eq.10 Equipment Desenpten Bldg. FL EL Room Base EL <40'? Cap Demd. Cap > Caveats Anchor Interact Equip CI PIMS ID Spec. Spec. Demd? OK7 OK? OK? OK7 OSPeo E2 DIG FUEL OfL TRANSFER PUMP o n eGe w ekr 127 DIG-5 127 Y BS GRS Y Y Y Y Y 5
osPoso oCPeo E3 DG FUEL Ott TRANSFER PUMP DwGews 127 DC-7 127 Y BS GRS Y Y Y Y Y 5 otroso 5 coPeo E4 DIG FUEL Ott TRANSFER PUMP D"' G*"*k" 127 DIG-9 127 Y BS GRS Y Y Y Y Y ODPoso 7 A042C-7231A Et DIG AIR START SOLENOID VALVE ow Gewskr 127 D/G-3 127 Y BS GRS Y Y N/A Y Y AO452C-7231A 7 A042c.7231s E2 DG AIR START SOLENOID VALVE ow Gewehr 127 OlG-5 127 Y BS GRS Y Y N/A Y ) Ao442C-723ta A042C-7231C E3 DIG AIR START SOLENOID VALVE D M Ge w skr 127 D/G-7 127 Y BS GRS Y Y N/A Y Y 7 A0452C-7231C 7 Ao42C-7231D E4 DIG AIR START SOLENOfD VALVE DM Ge==kr 127 D/G-9 127 Y BS GRS Y Y N/A Y Y A04$2C-7231D 7 AOW232A Et DIG AIR START SOLENOID VALVE o w Ge w skr 127 D/G-3 127 Y BS GRS Y Y N/A Y Y AO452C-7232A 7 A042C-7232s E2 DIG AIR START SOLENOID VALVE DW Gewskr 127 DIG-5 127 Y BS GRS Y Y N/A Y Y A0462C-7232e 7 A042C-7232C E3 DIG AIR START SOLENOID VALVE DM Gewskr 127 DC-7 127 Y BS GRS Y Y N/A Y Y AO452C-7232C 7 AO42C-72320 E4 DIG AIR START SOLENOID VALVE DM Gewskr 127 DG-9 127 Y BS GRS Y Y N/A Y Y A0452C-72320 SA MO4o501A ESW A INLET TO ECT RESERVOIR W g94 ECT-1 114 Y BS GRS Y Y N/A Y Y MO446-o501A h Cert!ficatort As the inIbrmagon contained on this Screening VerNicagon Date Sheet (SVDS) Is. to N best of our The informegon provided to the Seismic Capabi!Ity Engineers regarding systems and operegons of the knowiedge and benef, amect and accurate. As intbnnesore indudes each erey and concsusion (whether equipment contained in the SvDS is, to the tmt of our knowledge and beRef, correct and accurate-vertried u be seier,lesey adequate or non. Approved: (One signature of Systems or Operemons Engineer le required N the Seismic Cam Approved- (Signatures of ou Seismic r 'W Engineers on the Seismic Review Team (SRT) are Engineers deemit necessary.) j , required; there should be et toest two on the SRT. AE eignatories should agree with og the enktoo and conclusions. One signatory should be a Rooneed m^ : .) Dan M Print or Type Name [ sture
/ g 3' Date Print or Type Name Signature Date
- s. S n.m w Signature Ia}at whskr Print or Type Name Q Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
_ . _ _ _ . _ _ . .. ..m_ _ . - .. - . _. - _ _ _. _ _._ _ _ _ _ _ _..-.._ _. _.. _ _ . _.__ __ w .. PEACH BOTTOM ATORNC POWER STATION page e ; 12ttsas i SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq.ID Equipment Description Bldg. FL EL Room Base El. <4(r? Cap Demd. Cap > Coweets Anchor Interad Equip , Cl pigs 30 Spec. Spec Demd? OK7 OK7 OK7 OK7 f t eA Momosois ESW P INLETTO ECT RESERVOIR W ,,4 ECT-1 114 Y BS GRS Y- Y N/A Y Y j 9 _e Mo44501c ESWC INLET TO ECT RESERVOtR canno 114 ECT-1 114 Y BS GRS Y Y N/A Y Y eA i MO44o501C eA Momo302c HPSWC INLET TO ECT RESERVOIR '74 W 9,4 ECT-1 114 Y BS GRS Y Y N/A Y Y g oAnn32 "A* EMERGENCY COOUNG TOWER FAN E- - Camg 195 ECT4 195 N/A ABS CRS N Y Y Y N g OAvoet Et DS BUILDING VENT SUPPLEMENT SUPPLY Doest Genereur 151 OfG-14 151 Y BS GRS Y Y Y Y Y ' FAN o_e, , camg ECT4 195 N/A ABS CRS N Y Y Y N e con 332 "B" EMERGENCY COOUNG TOWER FAN 95 2 g cavoet E2 DfG BUILDING VENT SUPPLEMENT SUPPLY D M Omnemkr 151 OfG-1e 151 Y BS GRS Y Y Y Y Y FAN c;; = e ocx032 "C" EMERGENCY COOLING TOWER FAN cm*"8 195 ECT4 195 N/A ABS CRS N Y Y Y N oCVoet E3 OfG BUILDING VENT SUPPLEMENT SUPPLY puest Genereur 151 DfG 1e 151 Y BS GRS Y Y Y Y Y g FAN ocvoet cowest E4 OfG SUILDING VENT SUPPLEMENT SUPPLY Deest Generehr 151 OfG-20 151 Y BS GRS Y Y Y Y Y e FAN o 0%9 01 20 oACo87 DOESEL GENERATOR OAG12 CONTROL PANEL Deend Generskr 127 DfG-3 127 N/A ABS CRS N Y Y N N wu7 l 20 OAG 3 E1 OfG P.T. AND EXCITATION EQUIPMENT Dee'8 C C- 127 DfG-4 127 Y ABS CRS N Y Y N N caco 13 C D S- - ,0.u.-o,_ _ -,0 _ C.p y En ore , _ d ope, s o. A._ _ _..S.e_. $ enty and contfuelon $shether equipment conleined in .e SVDS lo, to the best of our knoededge and belief, oor'ect and occurale. knoustedge and benef, correct and accurate, vermed to be seismiceer aM* or non. "AA informegon"Indudes esi Approveit (One signature or Systems or Opersuone Engineer le required N Ihe Solemic CapabERr e Engineers deem it ver=ammy.) Approvet (Signetwee or en Seismic =p=NWr Engineers on the Salemic Review Team (SRT) are enkles and j r_equired;inere
- sh.... should be-at inest.two on the SRT, AE elyistories should agree wth Den Fiofello / j9 ff'
~$lgn De Print or Type Name SignWum De Print orType Nome
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%pW 'Na&4 mhr/fr Print or Type Name Signature Date Print or Type Name Signature Q Date Date Print or Type Name Signature Date Print or Type Name Signature
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V v s PEACH BOTTOM ATOMIC POWER STATION p.g. g SCREENING VERIFICATION DATA SHEET (SVDS) 12tistes Eq.ID Equipment Description Bldg. FL EL Room Bare EL <407 Cap Demd. Cap > Caveats Anchor interact Equip Eq. Cl Spec. Spec. Demd7 OK7 OK7 OK7 OK7 PIMS ID 20 oscoo7 DIESEL GENERATOR OBG12 CONTROL PANEL Dw G--- 127 DGe 127 N/A ABS CRS N Y Y N N cecoef OBG13 E2 DIG P.T. AND EXClTATION EQUtPMENT DW C a- 127 DGe 127 Y ABS CRS N Y Y N N 20 08G013 occoe7 OfESEL GENERATOR OCG12 CONTROL PANEL Ow Generstar 127 DG8 127 N/A ABS CRS N Y Y N N 20 occoef ocG13 E3 DIG P.T. AND EXCtTATION EQUfPMENT Doest Generer 127 DGe 127 Y ABS CRS N Y Y N N 20 0CG013 oDcoB7 DIESEL GENERATOR ODG12 CONTROL PANEL Dw C--- 127 DIG-10 127 N/A ABS CRS N Y Y N N 20 uuC5i7A CDG13 ow c J- 127 DG10 127 Y ABS CRS N Y Y N N 20 E4 D/G P.T. AND EXCITATION EQUtPMENT 00Go13 Certdicetkn Cerencebon. The information provided to the Seismic CapetWhty Engineers regarding systems and operadons of the t AE the informaton contained on this Screening Venficsson Data Sheet (SVDS)is, to the best of our equipment contained in the SvDS is, to the twst of our knowledge and benet, correct and somrate knowledge and beset.merect and acxurate An informeeon inchies each eney and conc:usion (whether verined to be seismicany adequate or no0 Approved: (One signature of Systems or Operstons Engineer is required W the Seismic CapabMy Engineers deem R pecessary ) Approved: (S62nstures of all Seismic CapaitWnty Engineers on the seismic Review Team (SRT) are j required; there should be et least two on the SRT. AI signatories should agree se the entries and conclusions. One signatory should be a Econsed rm^_- ; .) Dan Fiorello // / gf[ Date Date Print or Type Name Signature Print or Type Name # pnatufe James Flahefty M / [ ff V Date Print or Type Name Signature Date Print or Type Name [ Signature ~ Date Print or Type Name Signature Date Print or Type Name Signature
OO O O PEACH BOTTOM ATOMIC POWER STATION p.g.1 SCREENil4G VERIFICATION DATA SHEET (SVDS) 12r12ms Eq. Eq. ID Equipment Description Bldg. Fl. El. Room Base EL <407 Cap Demd. Cap > Cavests Andor Intered Equip Cl PIMS ID Spec. Spec. Demd? OK? OK? OK? OK7 g PCv-se17A NITROGEN PRESS CTRLVALVE FOR BACKUP Reedor Bus -U3 135 R3-23 135 N/A N/A N/A Y Y N/A Y Y SUPPLY TO ADS PCV416A4917A g PCV-99179 NTROGEN PRESS CTRL VALVE FOR BACKUP Reactor BMg -U3 135 RS23 135 N/A N/A N/A Y Y N/A Y Y SUPPLYTO ADS PCV416A-99178 0 PCV-9917C MITROGEN PRESS CTRL VALVE FOR BACKUP Reactor BMg - U3 135 RS23 135 N/A N/A N/A Y Y N/A Y Y SUPPLY TO ADS PCV416A-9917C y Aos e-32A SORAM DISCHARGE VOLUME INBOARD Reactor BMg-U3 135 R3-22 155 tVA ABS CRS N Y N/A Y N ISOLATION VENTW Ao-3 m m2A 7 Ao343-32s SCRAM DISCHARGE VOLUME INBOARD ReactorBMg U3 135 R3-23 155 N/A ABS CRS N Y N/A Y N ISOLATION VENT W Ao-3434328 7 A034335A SCRAM DISCHARGE VOLUME OUTBOARD Reedor BMs -U3 135 RS26 155 N/A ABS CRS N Y N/A Y N ISOLATION VENTW A0443mSA y Ao3453se SCRAM DISCHARGE VOLUME OUTBOARD Reedor SMg - U3 135 R3-24 155 N/A ABS CRS ii Y N/A Y N ISOLATION VENTW Ao44343% 8A Mo3-to425A RHR INNER INKCTION VALVE TO RECIRC LOOP A Reedor BMg- U3 135 RS25 135 N/A ABS CRS Y N N/A Y N Mo41042sA sA Mos-to425s RHR INNER INKCTION VALVE TO RECIRC LOOP 8 Reedor BMs- US 135 R3-27 135 N/A ABS CRS Y N N/A Y N Mo410425e 8A Mo&104s4 RHR HX 3AE024 HPSW Ot ~.LET VALVE Reedor sus-U3 116 R3-16 116 Y BS GRS Y Y N/A Y Y
.Mo->104esA 8A M03if W RHR HX 3CE024 HPSW OUTLET VALVE Reedor BMg - US 116 R3-17 116 Y BS GRS Y Y N/A Y Y Mo41' mx 68 sV-91 ACS BACKUP NITROGEN A HOR SUPPLY TO Reedor BMg -U3 135 R3-23 135 N/A ABS CRS Y Y N/A Y Y DRYWELL SV416A-911oA Certinesson Certincation.
AR the Infbrmogon contamed on this Screening VertRcation Dets Sheet (SVDS)Is, to the best of our The information provkled to the Seismic CapetWilly Engineers regarding systems and opere#ons of the knowledge and benef, conect and accurs'3. *AR information indudes each entry and conclusion (whether equipment contamed in the SVDS is, to the best of our knowledge and besef, correct and securale verilled to be seismicour adequate or noQ. Approved (One signature of Systems or Operseone Engineer is required K the Seismic CapabWty Approved (signatures of as Seismic Capsbety Engmeers on the seismic Review Team (SRT) are Engineers deem R necessary.) reaused; there should be at least two on the SRT. As signatories shoukt agree wMh sE fie entries and j conclusions. One signatory should be a licensed pecsessionet engbeer.) Dari Fiorello [g /g,[/g[9g Print or Type Name ign Date Print or Type Name Signature Dele Peter GUglielmeno y v /2,/fp[pf Print or Type Name l/ 86n Date ' Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
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.-.s PEACH BOTTOM ATORMC POWER STATION %
SCREENING VERIFICATION DATA SHEET (SVDS) 12r12res Room Base EL <4(r? Cap Demd. Cap > Coweste Andor hitered Equip i Eq. Eq.10 Equipment Description Bldg. FL EL C pgus 10 Spec. Spec. Demd? OK7 OK7 OK7 OK7 i gg sv-stsas ADS BACKUP NITROGEN B HDR SUPPLY TO Restser BWg -U3 135 R3-25 135 NA ABS CRS Y Y WA Y Y DRYWELL ! sv49en-staas 21 3 Assn BACK-UP N2 SUPPLY TO ADS RVS R*'esBMg-U3 135 R3-23 135 N/A WA WA WA Y Y Y .Y 3AS3n sesan BACK-UP N2 SUPPLY TO ADS RVS Rootsar sus-U3 135 R3-23 135 N/A WA N/A WA Y Y Y Y 21 3es3n l 21 3Cssn BACK-UP M2 SUPPLY TO ADS RVS Rootser BMg -U3 135 R3-23 135 N/A N/A N/A N/A Y Y Y Y t t 3Cs3M Cerimessort Certmeston. As the irdermoson contained on this Screening veraceeon Date Sheet (SVDS)Is. to the best of our The Irdormagon proveed to IN Seismic r'or=NNIy Engineers regenang om and opermears of en knowiedge and besef, correct and occurate. "As irdarmenore indudes each entry and conclusion (whether equipment contemed in the SVDS is, to the best of our knowledge and beset, coned sud accurele vermed to be seentasy adequeen or natt Approvee (One signetsa of Systems or Operegons Engineer is required N the Setemic CapabWty Approvee (Signatures of as Seismic Capstely Engireers on the Seismic Review Team (SRT) are Engineers deem it nemetery ) j required; there should be et leest two on the SRT. AI signatortes should agree wift eR the ensies and J.~ One signatory should be a scensed prossesional engineer.) Dan FloreRo 9// o j /2.[/g[ff Date Print or Type Name Sagnature Date Print or Type Name Peter G6'.4 O ~
/2[/f/ff DeRe ' Print or Type Narre Signature Date Print orType Name Signature Date Print or Type Nome Signature Date Print or Type Name
_ _ _ _ - _ _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ - _ _ - - - _ _ ____ - ____=____ _ ____ ___ -
(~ im PEACH BOTTOM ATOMIC POWER STATION p.g. , SCREENING VERIFICATION DATA SHEET (SVDS) 12 twos Eq. Eq.ID Equipment Description Bldg. FL Et Room Base EL <40*? Cap Demd. Cap > Caveats Anchor Interact Equip Cl PIMS ID Spec. Spec. Demd? OK7 OK? OK7 J '? to ts2 3 74 CONDENSATE STORAGE TANK LEVEL SWITCH Twt *w e g U2 135 T2-55 140 N/A ABS CRS Y Y Y Y Y to ts2375 CONDENSATE STORAGE TANK LEVEL SWITCH Tutte eq -U2 135 T2-55 140 N/A ABS CRS Y Y Y Y Y ta ts2 M eta SUPPRESSION POOL LEVEL SWITCH men rog U2 91 4 R2-10 112 N/A ABS CRS Y Y Y Y Y 18 ts2 a ste EUPPRESSION POOL LEVEL SWITCH m esorseg-U2 91 4 R2-10 112 N/A ABS CRS Y Y Y Y Y 1s LT2-15170 SUPPRESSION POOL LEVEL SWITCH FOR RCIC Twtmo eMg -U2 116 T2-14 120 Y BS GRS Y Y Y Y Y INmATION . 13 (T215171 SUPPRESSION POOL LEVEL SWITCH FOR RCIC Tates eMg -U2 116 T2-14 120 Y BS GRS Y Y Y Y Y I INmATION , to ts>2574 CONDENSATE STORAGE TANK LEVEL SWITCH TwtWe eug -U3 135 T3-55 140 N/A ABS CRS Y Y Y Y Y 7 to ts3-257s CONDENSATE STORAGE TANK LEVEL SWITCH Twt *= suo - U3 135 T3-55 140 N/A CRS RRS Y Y Y Y Y 1e LSS2SetA SUPPRESSION POOL LEVEL SWITCH menorsus-US 914 R3-11 112 N/A ABS CRS Y Y Y Y Y 18 ts>23ste SUPPRESSION POOL LEVEL SWITCH medorsus U3 91 4 R3-11 112 N/A ABS CRS Y Y Y Y Y
\
te (T3-15170 SUPPRESSION POOL L'EVEL SWITCH FOR RCIC Twt *w sus- U3 116 T3-17 120 Y BS GRS Y Y Y Y Y INmATION 3g LTitit71 SUPPRESSION POOL LEVEL SWITCH FOR RCtC Twtmo sus-U3 116 T3-17 120 Y BS GRS Y Y Y Y Y INITtATION Certification: Cert 6caBon. As the information contained on this Screening Verliicanon Dets Sheet (SVDS) is, to the best of our The Intbrmenon provided to the Seismic Capabety Engineers regennng systems and operoWons of the knowledge and belief, com!d aM securate *AR infbrmsborf includes each entry and tenclusion (whether equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate. verined to be seismicacy adequase or non. App 7ved: (One signature of Systems or Operseens Engineer is required if the Seiernic Capsbety Approved (Signatures of sE Seismic Capabill'y Engineers on the Seismic Review Team (SRT) are Engineers deem R necessary.) required; there should be et feest two on the SRT. AE signatories should agree witi mR the entries and j cxmetusions. One signatory should be a licensad 4.a ; ~ Dan Fiorello Print or Type NarrF
% S-
/g_ /g_9f Data Print or Type Name Signature Date Richard DanielS Print of Type Name
((. hM Signature
/s/zv/fJ'
' Date Print of Type Name Signature Date i
Signature Date Print or Type Name Signatum Date Print or Type Name
v w PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <4(r? Cap Demd. Cap > Caveats Anchor Interact Equip CI PIMS ID Spec. Spec. Demd7 OK7 OK7 OK7 OK7 2AVo60 HPSW PUMP ROOM SUPPLY FAN A Pump House 112 PM4 $ ,2 Y BS GRS Y Y Y Y Y g 2Avoe3 HPSWPUMP ROOM EXHAUST FAN A Pump House ,112 PM4 *' y Y BS GRS Y Y Y Y Y 2eVo60 HPSW PUMP ROOM SUPPLY FAN B Pump House 112 PM4 Q1,2 Y BS GRS Y Y Y Y Y 2evoe3 HPSW PUMP ROOM EXHAUST FAN B Puny House 112 PM4 $$ Y BS GRS Y Y Y Y Y to Po20223-1 HPSW PUMP ROOM"D" LOOP SUPPLY DAMPER Pump House 112 Pma 12e Y BS GRS Y Y Y N N 10 Po20223-2 PDSW PUMP ROOM "B" LOOP EXHAUST DAMPER Pung House 112 PM4 126 Y BS GRS Y Y Y Y Y to PO2o223-3 HPSW PUMP ROOM"A" LOOP SUPPLY DAMPER Pump House 112 PM4 12e Y BS GRS Y Y Y N N 1o PO26 HPSW PUMP ROOM "A" LOOP EXHAUST DAMPER Pump House 112 Pir44 12e Y BS GRS Y Y Y Y Y 18 DPS2o224-1 HPSW PUMP ROOM i SUPPLY Pt ENUM PW House 112 PM-8 118 Y BS GRS Y Y Y N N DIFFERENTIAL PRESSURE SENSOR t3 DPS2o224-2 HPSW PUMP ROOM i EXHAUST PLENUM Pump House 112 PM-8 tis Y BS GRS Y Y Y Y Y DtFFERENTIAL PRESSURE SENSOR DPS20224-3 HPSW PUMP ROOM i SUPPLY PLENUM Pump House 112 .PM4 no Y BS GRS Y Y Y N N jg DIFFERENTIAL PRESSURE SENSOR 18 ops 202244 HPSW PUMP ROOM t EXHAUST PLENUM Pump House 112 PM-8 11e Y BS GRS Y Y Y Y Y DIFFERENTIAL PRLSSURE SENSOR Certencatkn Certincaten. At the infonnation contained on this Screening Veripcotson Data Sheet (SVDS) is, to the best of our The infonnation provided to the Seismic Capat#ty Engineers regenSng systems and operegens of the knowledge and belief, conect and accurate "Allinformabon" includes each entry and conclusion (whether equipment contained in the SVDS is, to the best of our knowledge and belief, coned and accurate.. verined to be seismically adequate or non. Approved: (One signature of Systems or Operations Engineer is required W the Setsmic Capabiuly Approved. (Signatures of se Se6smic Capability Engineers on the Seismic Review Team (SRT) are Engineers deemit necessary ) j required, there should be at least two on the SRT. As signatories should agree with mR the e'itries and conclusions. One signatory should be a licensed professional engineer.) Richard Daniels b 88$fIe N2 0 Signature Date Print or Type Name Signature Date Print or Type Name Dan FlOfello /[ / g g-g Date Print or Type Name Signature Date Print or Type Name ggfiature Signature Date Print or Type Name Signature Date Print or Type Name
T :t PEACH BOTTORA ATORRIC POVUER STATION SCREENING VERIFICATION DATA SHEET (SVDS) muss Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <4(r? Cap Demd. Cop > Coveals Anchor Interact Equip Cl PAIS ID Spec. Spec. Demd? OK7 OK7 OK7 OK7 Ticaa223 HPSW PUMP ROOM EXHAUST TEMP INDICATING Pump House 112 Pne 12e Y BS GRS Y Y Y Y Y te CONTROLLER L is T5m1 HPSW PUMP ROOM "N LOOP AUTOMATIC Pump House 112 PM4 11e y g3 gg3 y y y y y TEMPERATURE SENSOR 9g TS m HPSW PUMP ROOM T LOOP AUTOMATE Pump House 112 PM4 no Y BS GRS Y Y Y Y Y TEMPET4ATURE SENSOR t is TTaa2n HPSW PUMP ROOM EXHAUST TEMPERATURE Pump House 112 Pma 124 Y BS GRS Y Y Y Y Y TRANSMIT 1ER 20 2cC13e HPSW PUMP ROOM LOCAL CONTROL PANEL- Pump House 112 Pne tto Y BS GRS Y Y Y. N N HVAC m voso HPSW PUMP ROOM SUPPLY FAN A Pw p House 112 PM-9 ',2 y gg ggg y y y y y mvoes HPSW PUMP ROOM EXHAUST FAN A Pump House 112 PM-8 $',% Y BS GRS Y Y Y Y Y 9 3eVUe3 HPSW PUMP ROOM SUPPLY FAN 8 Pump House 112 PM., Qt,2 y gg ggg y y y y y 3eWUe3 HPSW PUMP ROOM EXHAUST FAN 8 Pump House 112 PM-9 ', Y BS GRS Y Y Y Y Y , 13 PO30223-1 HPSW PLWP ROOM T LOOP SUPPLY DAMPER Pump House 112 PM-9 126 y 33 ggg y y y y y 1 10 PO30223-2 HPSW PUMP ROOM T LOOP EXHAUST DAMPER Purry House 112 Pm4 12e y gg ggg y y, y y y to P030223-3 HPSW PUMP ROOM T LOOP SUPPLY DAMPER Pump House 112 PM4 12e y gg ggs y y y y y CerWReston: , Cert l Reagan. AN to informoson contained on thle Saeening vertAcagon Data Sheet (SVDS)le. to We best of our The Ireorrnmeon proveed to Wie Seismic FM Engirgers regenang erstems and operemons of sie knowiedge and tener, correct and seewese. As insonnesore indudes each eney and conr* (whoiher equipment conesined in the SvDS is, to the best or our knowesepe and baser, conect and accurese. verthed to be seierniceer adequets or no0 Approvet (One signeswe of Systems or Operssons Engineer le seguired N the Solemic P=p hany Approved (Signelures of se Setemic Capet$lly Engineore on tie Se6emic Reviour Team (SRT) are Engineers doom it necessary.) required; tiere should be et toast toro on ein SRT. As signatortes should agree wist og sie entries and j conckretone. OnesignatoryshouWbeelicensed J engineer.) Richard Daniels [f. /[aM9(o Print or Type Nome Signetwo Date i Print or Type Nome Signetwo Dele F l~ 288{. Print or Type Nome / 'Signetwe Dale Print or Type Name Signetwo Date ! 4 Print or Type Name Signetwo Date Print or Type Nome Signetwo Date
l s~ - PEACH BOTTOM ATOMIC POWER STATION SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <4(r? Cop Demd. Cop > Cavests Anchor interact Equip Cl PSAS ID Spec. ' Spec. Demd? OK7 OK7 OK? OK7 10 PO3o2234 HPSW PUMP ROOM *r LOOP EXHAUST DAMPER Pump House .112 PM-9 126 y gg ggg y y y y y 1g DPS3o2241 HPSW PUMP ROOM i SUPPLY PLENUM Pump House 112 PM-9 1'8 Y BS GRS Y Y Y Y Y DIFFERENTIAL PRESSURE SENSOR , ' DPS3o2242 HPSW PUMP ROOMi EXHAUST PLENUM Pump House 112 PM-9 11e Y BS GRS -Y Y Y Y Y 18 j DeFFERENTIAL PRESSURE SENSOR I DPS30224 3 HPSW PUMP ROOMiSUPPLY PLENUM Purry House 112 PM-9 11e Y BS GRS Y Y Y Y Y 1g , DIFFERENTIAL PRESSURE SENSOR ;
^
DPS302244 HPSW PUMP ROOMi EXHAUST PLENUM Pump House 112 Pgg 11e Y BS GRS Y Y Y Y Y 1g DIFFERENTIAL PRESSURE SENSOR 1e PS3o224-1 HPSW PUMP ROOM T LOOP PRESSURE SYYlTCH Pump House 112 PM9 tie y g3 gRs y y y y y PS302242 HPSW PUMP ROOM T LOOP PRESSURE SWITCH Purry House 112 PM-9 118 Y BS GRS Y Y Y Y Y is Ticso223 19SW PUMP ROOM EXHAUST TEMP INCNCATING Pump House 112 PM_g 120 Y BS GRS Y Y Y N N to CONTROLLER 18 tic 3o2241 HPSW PUMP ROOM "W LOOP TEMP INDICATING Pump House ' 112 PM-9 it? Y BS GRS Y Y Y Y Y .. CONTROLLER to tic 302242 HPSW PUMP ROOM T LOOP TEMP MDICATING Pump House 112 PM-9 117 Y BS GRS Y Y Y Y Y CONTROLLER TT30223 HPSW PUMP ROOM EXHAUST TEMPERATURE Pump House 112 PM-9 12e Y BS GRS Y Y Y Y Y in TRANSMITTER 3oC130 Pump House 112 PM-9 11e Y BS GRS Y Y Y Y Y 20 HPSW PUMP ROOM LOCAL CONTROL PANEL Cerenesson: Corsikmeort As the irdormaeon antained on this Saeoning Vernicsson Date Sheet (SVDS) te, to Wie best of our The inibrmellon provided to the Seismic P=P=Nuty Engineers regarding systems and or sresons of Wie knowledge end belief, tzrrect and scarate *AR trdormoson* includes each entry and concluelon (whetier equipment conleined in the SVDS le, to Wie best of our imowledge and Benef, merect and somrele veemed to be seierreceny adequate or noo. Approved: (One signature of Systems or Operemone Engineerle required Wthe Setemic t'apeway Approved: (Signatures at se Setemic Copshtur Engineers on tie Setemic Review Team (SRT) are Engineers deem it nemosery.) required; there shouw be et tenet two on the SRT. As signeeories should agree wilh eE the enbies and j conclusions. One signatory should be e scensed professional engineer.) Richard Daniels Print or Type Name [ C. h M Signature
/k%
Date Print or Type Name Signature Date DenFe Qs / , g,,g, Q Print or Type Name Signature Date pF Signature Dele Print or Type Name 1 Print or Type Nome Signature Date Print or Type Name Signature Dele
O O O PEACH BOTTOM ATOMIC POWER STATION p.g. $ SCREENING VERIFICATION DATA SHEET (SVDS) st12tes Eq. Eq. ID Equipment Description Bldg. FL EL Room Base EL <40'? Cap Decut. Cap > Caveats Anchor Interact Equip Cl PIMS ID Spm Spec. Demd? OK7 OK7 OK7 OK? 7 A0243-32A SCRAM DISCHARGE VOLUME INBOARD Reactor ekse-U2 135 R2-26 155 WA ABS CRS N Y WA Y N ISOLATION VENT W Ao-24Ht32A y A024Kt2s SCRAM DISCHARGE VOLUME INBOARD Reedor Bug -U2 135 R2-24 155 WA ABS CRS N Y WA Y N ISOtATION VENT W AO-24Mt32e Mo2 32,2344 P=p N8* 111 PM-e 120 Y BS GR3 Y Y WA Y Y 8 HPSW LOOPS 2A TO 2B CROSSTIE no04424344 Mo3434344 HPSW LOOP 3ATO LOOP 3B CROSSTIE Pep Nm j11 PM_g 120 Y BS GRS Y Y WA Y Y 8 Mo4324344 Cetificalion. Certificaton: AR the inibrmogen contrined on this f% Vertfice6on Dets Sheet (SVDS) is, b the best of our The inRxmetion provided b the Seismic CapabWty Engineers regarding systems and opera 6one of the knoudedge and belief, cnrrect and accurate *AR infbrmation* Includes each entry and conclusion (whether equipment contained h the SVDS is, to the best of our knowledge and behef, terrect and acx: urate verified b be eersmically adequete or not). Approved: (One signature of Systems or Operanons Engineer is requirep r the Seismic Capsbety Approved (Signahres of sit Sesmic capabety Engineers on the Seismic Review Team (SRT) are Engineers deem it necessary.) required, there should be et least two on the SRT. AR signatories should agree with at the entries and j conclusions. One em should be a licensed professional engineer.) Dan Fiorello Print of Type Name " [ $ignature j 3/f3/g Date Print or Type Name Signature Date Richard DanielS [ f, f/f3/% Print or Type Name Signature Dbte Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
f3 u / PEACH BOTTOM ATOMIC POWER STATION p.g. , ' SCREENING VERIFICATION DATA SHEET (SVDS) 12n2tes Eq. Eq.ID Equipment Description Bldg. Fl. EL Room Base EL <40'? Cap Demd. Cap > Caveats Anchor Interact Equip Cl Spec. Spec. Demd? OK7 Oh? OK7 OK7 PIMS ID 2AS M Tm Proper-U2 111 Torus 111 N/A N/A WA Y Y WA Y Y 0 RHR PP 2AP035 SUCTION STRAINER 2As7es 2ssm Ta Prepw.U2 111 Toms 111 WA NA N/A Y Y WA Y Y O RHR PP 2BP035 SUCTION STRAINER 2sS7e9 Torus Preen-U2 111 Torus 111 N/A N/A WA Y Y N/A Y Y 0 2CS7SS RHR PP 2CP035 SUCTION STRAINER 2CS7e9 Tarus Propw-U2 til Torus 111 N/A N!A WA Y Y N/A Y Y 0 2057es RHR PP 2DP035 SUCTION STRAINER nostes RommerBede u2 111 Torus 111 N/A N/A NA Y Y N/A Y Y 0 HPCI SUCTION STRAINER t Certmcatat Certmcanon. As the informoson antamed on this Screening vertncation Data Sheet (SVDS) is, to the best of our The Wermetton provided to the Seismic CapabWty Engineers regansng systems and operagons of the equipment contamed m the SVDS Is, to the best of our knowledge and betsf, correct and accurate. knowiedge and benet, wrrect and accurate *Au ;..:...ee mesudes each entry and mnclusion tm verined a be seismicaer adequate or noo. Approved (One signature of Systems or Operatons Engineer is requ8 red N the Seismic Capabimy Approved (Signatures of all Seismic Capabaty Engineers on sie Seismic Review Team (SRT) are Engineers deemIt necesssry) j required; there should be at feest two on the SRT. AI signatories should agree with at the entries and condusions. One signatory should be a Incensed m .a ; engineer.) Richard Daniels ** 4 Wha /t.[17 Signature Date Print or Type Name Signature Date Print or Type Name James Flahefty byghp{fy M l 2[7,7[i[
~
Print or Type Name Signature Date Print or Type Name Signature ~ Q Date Signature Date Print or Type Name Signature Date Print or Type Name
-- _ .~-.--._---. - --..-._. -_ =.- __.- - ._ ..- - -.~ ~
[ - v PEACH BOTTOM ATOMIC POVUER STATION p., , ; SCREENING VERIFICATION DATA SHEET (SVDS) tartnos Eq. Eq. ID Equipment Description Bldg. FL EL Room Bose EL <477 Cap Demd. Cap > Caveste Anchor Interact Equ5 Cl Spm Spec. Demd? OK7 OK7 OK7 OK7 PIMS ID Sauss menorsus-U3 135 R3-29 135 WA ABS CRS Y U Y Y U , 4 PANEL 30Y35 TRANSFORMER 3aK135 Aoses-33 SCRAM DISCHARGE VOLUME #890ARD Rootsersug U3 135 RS-22 135 MA A88 CRS Y N WA Y N y i ISOLATION DRAIN W f A040S833 I SCRAM DISCHARGE VOLUME OUTBOARD 7 _ sus-US 135 RS-22 135 WA ABS CRS Y Y MR Y Y y Aoses-se ISOtATION DRAIN W ; Ao 4 03.ese R"8'r sus-US 135 RS-22 135 NE ABS CRS Y- Y MA Y Y gg avs433 INSTR AIR SOLEMOIO VALVE FOR AO-343-033 eV403433 30v35 needer BMg -US 135 R3-29 135 WA ABS CRS Y Y Y Y Y g4 120VAC UtSTRIBUTION PANEL i EMF 1 VJU DRYWELL PRESSURE TRANSMITTCR FOR needer gue.us 118 RS-21 116 MA ABS CRS Y Y Y Y Y to PT.seos PR-SeOS Pimes i Cermer=e=r Casellesson. The intbemason proutded to sie Salemic e===Mar Engheers regendhe systems and operemons of sie As the intbemoson contehed on ede Screenhoverinessen Does Sheet (SVDS)le, b eie best of our equipment coreshed in the SvDS is, no the best at our knoededge and beset, conect and sermress knowledge end beast, correct and secureen. -As inermonon m sacri enty and concsushm (whoiner verWied to be estandcasy =d=taman er nog. Approvet (One signomos or syseene or Operegone Engheer le sequhed Wihe Selsfreer=r=May
~
Engheers deem it naa====sy.) Approved- (Signatures of as Seismic t'=r=May Engheers on the Seismic Moviser Team (SRT) are requked; there shouks to et toast two on sie SRT. As signanaries shouki agree wiih og the enstes and ; conesusiers One signeesry shoukt be a nesneed , J _ engheer.) Richard Daniels [.[. /1i./s7/ya~ Dete' Print of Type Nome Signature Date Print or Type Nome Peter Guglielmino , h fr/27/pg
~Dete Print orType Nome Signature Dese Print or Type Name Date Print or Type Name Stieture Date Print or Type Nome Signature
" v- , e a- -
-. -,n.
l O SEISMI EVALUATI N REPORT FOR PEACH BOTTOM ATOMIC POWER STATION 1 1 i ATTACHMENT D SVS O l The following is a summary of the A-46 equipment outliers. O l
PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 b OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: 20B36 PIMS ID: E124-R-C (20B36) SQUG Class: 1 Desenption: 480 v REACTOR AREA EL 165* MCC 20B36 (E124-R-C) Building: ReactorBido U2 Floor El.: 165 Room: R2 41 l 2 OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eautoment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) . Capacity vs. Demand x Caveats x Anchorage x ! 1 Seismic interaction Other j l
- b. Describe all the reasons for the outlier Poince demand exceeds capacity, the essential relays are not screened out.
- Capacity vs. Demand (GERS vs. CRS) does not screen-out.
- Anchorage was not evaluated.
1
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier. -
- Generate realistic mediunxentered, in-structure SSE spectra by scaling IPEEE RRS.
Evaluate MCC anchorage with reduced seismic demand (i.e., RRS). i
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A 4._ COMMENTS Using the proposed method given in 3a above, an evaluation was performed which documents that the component and anchorage is seismically adequate. Reference VECTRA Calculations No. 0067-00084-C-o14, Rev. 2 and 0067-00084-C-028. Since the MCC is qualifwK!, the essential relay is qualified by the Rule of-the-Box since EPRI NP-7148 states that the ROB can be applied to contact pairs that are in the control path for the MCC.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: O, n LI Date: 9//3/94
) ,A _ _ _ Date: T,b Z,lf4
i l 4 PEACH BOTTOM ATOMIC POWER STATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: 20810 PIMS ID: 20B010 SQUG Class: 2 i
Description:
480 V BUS E124 Building: Reactor Bldg U2 Floor El.: 165 Room: R241
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauipment
- a. Identify all the screening guidelines which are not met. j (Check more than one if several guidelines could not be satisfied.) i Capacity vs. Demand l Caveats x Anchorage x Seismic Interaction x Other l
- b. Describe all the reasons for the outlier
. Unanchored transformer and LVS sections are missing plug welds, therefore anchorage does not screen-out.
- Gap under base of LVS.
. Interaction with breaker hoist.
i m 3. PROPOSED METHOD OF OUTLIER RESOLUTION b a. Define proposed method (s) for resolving outlier.
. Complete MUD F5099 to replace unanchored transformers with ABB 1000 KVA VPE Ventilated Dry Type.
. Add missing plug welds for LVS.
. Restrain breaker hoist or remove.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: M O. Date: 2/{/9/
~
/
Date: f !/3!76
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
. ID: 20B11 PIMS ID: 208011 SQUG Class: 2 I
Description:
480 V BUS E224 Building: Reactor Bidg - U2 Floor El.: 165 Room: R2-116
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauipment
! a. Identify all the screening guidelines which are not met. i (Check more than one if several guidelines could not be satisfied.) ._ l I e Capacity vs. Demand Caveats x
- Anchorage x Seismic Interaction x Other i
! b. Describe all the reasons for the outlier
- Unanchored transformer and LVS sections are missing plug welds, therefore anchorage does not screen-out.
! - Gap under base of LVS.
-Interaction with breaker hoist.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION O a. Define proposed method (s) for resolving outlier.
- Complete MOD #5099 to replace unanchored transformers with ABB 1000 KVA VPE Ventilated Dry Type.
Add missing plug welds for LVS. i
- Restrain breaker hoist or remove.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: h. . Date: 2/9/94 Date: /3!ft
.i /
g PEACH COTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
., ID: 20B12 PIMS ID: E-324(20B12) SQUG Class: 2
Description:
480 V BUS E324 Building: Reactor Bldg - U2 Floor El.: 165 Room: R2-41
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand Caveats x l Anchorage x Seismic interaction x Other l
- b. Describe all the reasons for the outlier Unanchored transformer and LVS sections are missing plug welds, therefore anchorage does not screen-out.
- Gap under base of LVS.
1 Interaction with breaker hoist. l l 1
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION ;
- a. Define proposed method (s) for resolving outlier.
! i - Complete MOD #5099 to replace unanchored transformers with ABB 1000 KVA VPE Ventilated Dry Type. Add missing plug welds for LVS.
- Restrain breaker hoist or remove.
l
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, - and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: *
. Date: 4!f/
l l j- - Date: Zl/3l9L
l g PEACH BOTTOM ATOMIC POWER $'TATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: 20B13 PIMS ID: E-424(20B13) SQUG Class: 2
Description:
480 V BUS E424 Building: Reactor Bldg U2 Floor El.: 165 Room: R2-116
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauloment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) . _ Capacity vs. Demand Caveats x Anchorage x Seismic interaction x Other
- b. Describe all the reasons for the outlier
- Unanchored transformer and LVS sections are missing plug welds, therefore anchorage does not screen-out.
- Gap under base of LVS,
-Interaction with breaker hoist.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
- Complete MOD #5099 to replace unanchored transformers with ABB 1000 KVA VPE Ventilated Dry Type.
Add missing plug welds for LVS. Restrain breaker hoist or remove.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS 4
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: h O. . Date: NNf4 y Date: 7./3![0
1 . g PEACH BOTTOM ATOMIC POWER STATION GtP Rev. 2, corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
-.. ID: 20A15 PlMS ID: 20A015 SQUG Class: 3
Description:
(20A015) EMERG AUX SWITCHGEAR Building: Turbine Bidg - U2 Floor El.: 135 Room: T2171
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauloment
- a. Identify all the screening guidelines which are not met.
l (Check more than one if several guidelines could not be satisfied.) - Capacity vs. Demand Caveats x Anchorage l Seismic interaction x Other
- b. Describe all the reasons for the outlier MV5 cubicle doors use a single point latching mechanism; Top and bottom comers are provided with bolts which are not engaged.
l Equipment contains Low Ruggedness Relay (W-SV). Resolution of Relay issue is addressed on separato Relay OSVS.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
- MVS cubicle should be secured by latch or fasteners. Neoprene pads may be provided around doors.
1 i b. Provide information needed to implement proposed method (s) for resolving outlier. N/A
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: ; I Approved by:
- M Date: //2 M U
[' Date: 'b*b6 o
g PEACH BOTTOM ATOMIC POWER STATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
~. ID: 20A16 PIMS ID: E22 SQUG Class: 3
Description:
(20A016) EMERG AUX SWITCHGEAR Building: Turbine Bldg - U2 Floor El.: 135 Room: T2-71 l
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulomant '
- a. Identify all the screening guidelines which are not met.
1
- (Check more than one if several guidelines could not be satisfied.) - -
l Capacity vs. Demand i l Caveats x 3 Anchorage Seismic Interaction x
- Other
- b. Describe all the reasons for the outlier f
- MVS cubicie doors use a single point latching mechanism; top and bottom comers are provided with bolts which are not engaged.
j - Spare breaker not adequately secured. l - Equipment contains Low Ruggedness Relay (W-SV). Resolution of Relay issue is addressed on separate
- Relay OSVS.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION 1 a. Define proposed method (s) for resolving outlier.
l MVS cubicle doors should be secured by latch or fasteners. Neoprene pads may be provided around doors.
- Remove or secure spare breaker.
i
- b. Provide information needed to implement proposed method (s) for resolving outlier.
, N/A i
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: N O' N Date: //1.f/f/ I* Date: Milo[fL 7f
l g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID; 20A17 PIMS ID: E32 SQUG Class: 3
}
Description:
(20A017) EMERG AUX SWITCHGEAR Building: Turbine Bidg . U2 Floor El.: 135 Room: T2-170
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - Capacity vs. Demand Caveats x Anchorage j Seemicinteraction x Other
- b. Describe all the reasons for the outlier l - MVS cubicle doors use a single point latching mechantsm; top and bottom corners are provided with bolts l which are not engaged.
1 Spare breaker not adequately secured.
- Equipment contains Low Ruggedness Relay (W-SV). Resolution of Relay issue is addressed on separate Relay OSVS.
l 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
- MVS cubicle doors should be secured by latch or fasteners. Neoprene pads may be provided around doors.
- Remove or secure spare breaker,
- b. Provide information needed to implement proposed method (s) for resolving outlier.
I N/A I
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: m N. Date: M2 f/T/ k [' l' Date: ll3*l1C
y PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ! ID: 20A18 PIMS ID: E42 SQUG Class: 3
Description:
(20A018) EMERG AUX SWITCHGEAR 1 Building: Turbine Badg U2 Floor El.: 135 Room: T2-172 i
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Enulomant i a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - _ ) g Capacity vs. Demand Caveats x ] Anchorage l Seismic interaction x 4 Other ! b. Describe all the reasons for the outlier 1 , - MVS cubicle doors use a single point latching rnochanism; top and bottom comers are provided with bolts j which are not engaged.
- Spare breaner not adequately secured.
- Equipment contains Low Ruggedness Relay (W-SV). Resolution of Relay issue is addressed on separate Relay OSVS.
1
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION l a. Define proposed method (s) for resolving outlier. l l . MVS cubicle doors should be secured by tatch or fasteners. Neoprene pads may be provided around doors. )
Remove or secure spare breaker. l
- b. Provide information needed to implement proposed method (s) for resolving outlier.
l N/A 1 4 i 4
- 4. COMMENTS i
- 5. CERTIFICATION:
1 The information on this OSVS is, to the best of our knowledga anc tdef, correct and accurate, i and resolution of the outlier issues listed above will satisfy the rirgpitonants for this item of equipment to be verified for seismic adequacy: Approved by: N* dan Date: I!2 MTg d' I' Date: J f6 i
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: 20X30 PIMS 10: 20X030 SQUG Class: 4 I
Description:
LOAD CENTER XFMR E124 Building: Reactor Bidg - U2 Floor El.: 165 Room: R241
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulomant
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) . _ Capacity vs. Demand > x Caveats x Anchorage x Seismic interaction Other
- b. Describe all the reasons for the outlier 1
- Capacity vs. Demand (ABS vs. CRS) does not screen-out.
l Unanchored transformer, therefore anchorage does not screen-out.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION l O a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEERRS. (Ref. VECTRA Calculation No. 0067-000844-014, Rev. 2). Complete MOD #5099 to replace transformers with ABB 1000 KVA VPE Ventilated Dry Type. Transformer enclosure shall be bolted to the LVS to preclude impact.
- b. Provide information needed to implement proposed method (s) for resolving outlier. l N/A
- 4. COMMENTS VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves capacity vs. demand issue.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: O* b Date: /f1ff9/ Date: / E9!%
.T
PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2. Corrected 2/14/92 b OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: 20X31 PIMS ID: 20x031 SQUG Class: 4
Description:
LOAD CENTER XFMR E224 ! Building: Reactor Bldg - U2 Floor El.: 165 Room: R2-116 l
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauloment ~~
- a. Identify all the screening guidelines which are not met. !
. (Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand x ) Caveats x x ) Anchorage Seismic interaction f Other l f b. Describe all the reasons for the outlier 1
- Capacity vs. Demand (ABS vs. CRS) does not screen-out.
Unanchored transformer, therefore anchorage does not screen-out. i i ~ 3. PROPOSED METHOD OF OUTLIER RESOLUTION j l a. Define proposed method (s) for resolving outlier. l - Generate realistic, median-centered, in-structure SSE response spectra by scahng IPEEE RRS. (Ref. VECTRA Calculation No. 0067-00084-C-014, Rev. 2). Complete MOD #5099 to replace transformers with ABB 1000 KVA VPE Ventilated Dry Type. j Transformer enclosure shall be bolted to the LVS to preclude impact.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
j N/A 4 e
- 4. COMMENTS VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves capacity vs. demand issue.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, - and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: h a & Date: /!2.f'[f[ Date: l Z$ $(a
. = . - -- .__ - - .~ . .. _. . _ __. -. .. - _ _
i 1 l PEACH BOTTOM ATOMIC POWER $TATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: 20x32 PIMS ID: E-1617(20X32) SQUG Class: 4 Desertption: LOAD CENTER XFMR E324 ,i Building: Reactor Bldg - U2 Floor El.: 165 Room: R2-41 l
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulomant
- a. Identify all the screening guidelines which are not mat.
(Check more than one if several guidelines could not be satisfied.) - _
- Capacity vs. Demand x l Caveats x
) Anchorage x . Seismic interaction Other ] ) b. Describe all the reasons for the outfier i { - Capacity vs. Demand (ABS vs. CRS) does not screen-out. 1 - Unanchored transformer, therefore anchorage does not screen-out, i l 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
- Generate realistic, median centered, in-structure SSE response spectra by scaling IPEEE RRS.
(Ref. VECTRA Calculation No. 0067-00084-CA14, Rev. 2). Complete MOD #5099 to replace transformers with ABB 1000 KVA VPE Ventilateo Dry Type. I Transformer enclosure shall be bolted to the LVS to produde impact. i 4 b. Provide information needed to implement proposed method (s) for resolving outlier. j N/A } i i j 4. COMMENTS VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves capacity vs. demand issue. 4 4
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment i to be verified for seismic adequacy: Approved by: h$ Date: /!2I" 4 Date: l 29 [o
/
N 4
_ . _ _ . _ ~ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ . . . _ . _ __ _ . J , g PEACH BOTTOM ATOMIC POWER STATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
.. ID: 20X33 PIMS ID: E-1617(20X33) SQUG Class: 4
Description:
LOAD CENTER XFMR E424 Building: ReactorBldg U2 Floor El.: 165 Room: R2-116
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment i
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - _ j Capacity vs. Demand x Caveats x
- Anchorage x j Seismic Interaction Other
- b. Describe all the reasons for the outlier Capacity vs. Demand (ABS vs. CRS) does not screeneut.
Unanchored transformer, therefore anchorage does not screen-out.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION O o <' a< a e -et" e<><<< '>o e1>><.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS. (Ref. VECTRA Calculation No. 0067-00084-CA14, Rev. 2). Complete MOD #5099 to replace transformers with ABB 1000 KVA VPE Ventilated Dry Type. Transformer enclosure shall be bolted to the LVS to preclude impact.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS VECTRA Calculation 0067-00084-C-014. Rev. 2 resolves capacity vs. demand issue.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: M '
& _ Date: //8f/f/
/ M 16 7.D Date:
4 i y PEACH COTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 { OUTLIER SEISMIC VERIFICATION SHEET (OSVS) i , ID: 20X133 PIMS ID: 20X133 SQUG Class: 4
)
Description:
PANEL.20Y33 TRANSFORMER l Building: Turt>ine Bide - U2 Floor El.: 135 Room: T2171 l ! 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulomant . a. Identify all the screening guidelines which are not met. j (Check more than one if several guidelines could not be satisfied.) . l Capacity vs. Demand j Caveats x Anchorage f Seismic Interadion other i
- b. Describe all the reasons for the outlier
- Transformer coil is held inside enclosure with only 2 bolts instead of 4 bolts.
} 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
) Perform evaluation of coil anchorage and modify anchorage if required.
} i b. Provide information needed to implement proposed method (s) for resolving outlier. ! mA i i ( f 4. COMMENTS
- 5. CERTIFICATION:
The information on this 03VS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: N O. Date: 7[T 4
- , - [' DY Date: ~2./lbhL
.)
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) . ID: 20X150 PIMS ID: 20x150 SQUG Class: 4
Description:
PANEL 20Y50 TRANSFORMER Building: Turbine Bidg - U2 Floor El.: 135 Room: T2-171
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Fautoment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) . - Capacity vs. Demand Caveats x Anchorage Seismic Interaction Other
- b. Describe all the reasons for the outlier
- Transformer coil is held inside enclosure with only 2 bolts instead of 4 bolts.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
i Perform evaluation of coil anchorage and mo@y anchorage if required.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: h O *M Date: .2 f/ i f* Date: Gkl
PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SElSMIC VERIFICATION SHEET (OSVS) ID: 2AP42 PIMS ID: 2APO42 SQUG Class: 6
Description:
HIGH PRESSURE SERVICE WATER PUMP A Building: Pump House Floor El.: 111 Room: P/H 3
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauloment
- a. Identify all the screening guidelines which are not met. _
(Check more than one if several guidelines could not be satisfied.) Capacity vs. Demand , Caveats x l Anchorage x Seismic interaction x ! Other i j b. Describe all the reasons for the outlier j -Pump casing and impeller shaft greater than 20 ft.
. Interaction concems with yard Gantry crane. Space heater supported from ceiling with threaded rods.
] Piping to heater is flexible and may leak steam into room during an SSE event. 4 i l
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION i a. Define proposed method (s) for resolving outlier.
-Review existing documentation and perform analysis to determine seismic adequacy of pump shaft and anchorage.
Yard Gantry crane should be restrained by its supports when not in use, to preclude overtuming during an SSE.
- Flooding of component is not an A-46 concem. It will be evaluated as part of the IPEEE.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS An evaluation was performed which documents that the prmp casing and impeller shaft is seismically adequate, although the length is greater than 20 feet, therefore the intent of the caveat is met. The anchorage is also seismically adequate. This is documented in Calculation 0067-00084-C-027.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: Oi N Date: /!%6!94 w Date: /!Z(!ft
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
, ID: 2BP42 PIMS lD: 2BPO42 SQUG Class: 6
)
Description:
HIGH PRESSURE SERVICE WATER PUMP B Building: Pump House Floor El.: 111 Room: P/H4 I
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met. !
(Check more than one if several guidelines could not be satisfied.) - I Capacity vs. Demand i Caveats x Anchorage x I Seismic interaction x Other l b. Describe all the reasons for the outlier
-Pump casing and impeller shaft greater than 20 ft.
. Interaction concems with yard Gantry crane.
1 i
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
-Review existing documentation and perform anatysis to determine seismic adequacy of pump shaft and anchorage.
- Yard Gantry crane should be restrained by its supports when not in use, to preclude overtuming during an SSE.
4
; b. Provide information needed to implement proposed method (s) for resolving outlier, j N/A l 4. COMMENTS
{ An evaluation was performed which documents that the pump casing and impeller shaft is seismically adequate, although the length is greater than 20 feet, therefore the intent of the caveat is met. The i anchorage is also seismically adequate. This is documented in Calculation 0067-00084-C 027. l
- 5. CERTIFICATION:
- The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: l Approved by: bin Date: N94
'Y -
^ Date: lbli, fl
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) _ . _ ID: 2CP42 PIMS ID: 2CPO42 SQUG Class: 6
Description:
HIGH PRESSURE SERVICE WATER PUMP C Building: Pump House Floor El.: 111 Room: P/H-6
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - Capacity vs. Demand Caveats x Anchorage x l Seismic Interaction x l Other
- b. Describe all the reasons for the outlier
! -Pump casing and impeller shaft greater than 20 ft.
-interaction concems with yard Gantry crane.
l l 3. PROPOSED METHOD OF OUTLIER RESOLUTION f g a. Define proposed method (s) for resolving outlier.
; -Review existing documentation and perform analysis to determine seismic adequacy of pump shaft and anchorage.
- Yard Gantry crane should be restrained by its supports when not in use, to preclude overtuming during an SSE.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A 4.COMMENIS An evaluaten vra. performed which documents that the pump casing and impeller shaft is seismically adequate, although the length is greater than 20 feet, therefore the intent of the caveat is met. The anchorage is also seismically adequate. This is documented in Calculation 0067-00084-C-027.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, ' and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: be N Date: /kNM
- O m Date: ll?4lM
_ _ - _ _ _ _ _ - ~ . _ .__ _ _ _ . _ _ _ ' J. g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) 10: 2DP42 PIMS ID: 2DPO42 SQUG Class: 6
Description:
HIGH PRESSURE SERVICE WATER PUMP D i l Building: Pump House Floor El.: 111 Room- PA+6 I I } 2. OUTLIER ISSUE DEFINITION - Mecharacal and Electrical Equipment ! a. Identify all the screening guidelines which are not met. 4 (Check more than one if several guidelines could Nt be satisfied.) i capacity vs. Demand caveats x Anchorage x seismic interaction x ! Other i
- b. Describe all the reasons for the outlier i
l -Pump casing and impeller shaft greater than 20 ft.
- Interaction concems with yard Gantry crane. ?
i 3. PROPOSED METHOD OF OUTLIER RESOLUTION 4
- a. Define proposed method (s) for resolving outlier.
-Revow existing documentation and perform analysis to determine seisme adequacy of r,um;. shaft and anchorage. ; - Yard Gantry crane should be restrained by its supports when not in use, to preclude overtuming during an SSE.
l ! i i j b. Provide information needed to implement proposed method (s) for resolving outlier. I N/A i i l 4. COMMENTS i An evaluation was performed which documents that the pump casing and impeller shaft is seismically 1 adequate, although the length is greater than 20 feet, therefore the iMant of the caveat is met. The anchorage is also seismically adequate. This is documented in Ca*Au:1 tion 0067-00064-C-027.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: M- Date: /!2/!94
- 0' Date: l 24, f6
I g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) O Q .., ID: A02-03-32A PIMS ID: AO-243-C32A SQUG Class: 7
. Desciiption: SCRAM DISCHARGE VOLUME INBOARD ISOLATION VENT W Building: Reactor Badg - U2 Floor El.: 135 Room: R2-26
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauipment l
- a. Identify all the screening guidelines which are not met. ,
- (Check more than one if several guidelines could not be satisfied.) -
i Capacity vs. Demand x . Caveats Anchorage seismic interaction other i l b. Describe all the reasons for the outlier i f l- Demand exceeds Capacity (ABS vs. CRS). o l 3. PROPOSED METilOD OF OUTLIER RESOLUTION i( a. Define proposed method (s) for resolving outlier. Generate #salistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS. l , 4 l b. Provide information needed to implement proposed method (s) for resolving outlier. ] 4
- 4. COMMENTS VECTRA calculation 0067-0008&O14, Rev. 2 resolves capacity vs. demand issue. Therefore, this j component has been verifod to be seismically adequate.
! 5. CERTIFICATION: ! The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: I Date: .3 - /Z -t/, Date: IhMf6
4 g PEACH BOTTOM ATOMIC POWER STATION GIP P.ev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) 10: A02-03-328 PIMS ID: AO-2-03-0328 SQUG Class: 7
Description:
SCRAM DISCHARGE VOLUME INBOARD ISOLATION VENT W Building: Reactor Badg - U2 Floor El.: 135 Room: R2-24
- 2. OUTLIER ISSUE DEFINITION - Machanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not rnet.
(Check more than one if several guidelines could not be satisfied.) -
)
Capacity vs. Demand & x l caveats Anchorage Seismic Interschon Other I
- b. Describe all the reasons for the outlier
- Demand exceeds Capacity (ABS vs. CRS).
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier. .
i Generate realiste, mediana: entered, in-structure SSE response spectra by scaling IPEEE RRS.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
- 4. COMMENTS VECTRA calculaton 0067-0008-C-014. Rev. 2 resolves capacity vs. demand issue. Therefore, this component has been verified to be seismically adequate.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seistriic adequacy: Approved by: h/ ; Date: 3-/ kf4 3 Date: 3 Mf6
)
i:t
4 i j g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92
- OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
{ ID: A02 03-33 PIMS ID: AO-2-03-033 SQUG Class: 7 l I
Description:
SCRAM DISCHARGE VOLUME INBOARD ISOLATION DRAIN W Building: Reactor Bldg - U2 Floor El.: 135 Room: R2-22
- 2. OUTLIER ISSUE DEFINITION - Mechan! cal and Electrical Eauloment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - capacity vs. Demand caveats x f Anchorace i Seismic Interaction Other
- b. Describe all the reasons for the outlier i
- Distance from pipe centerline to top of operator outside Figure B.71 of GIP.
i 1
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION 1
3 (V a. Define proposed method (s) for resolving outlier. Perform evaluation to demonstrate acceptabihty. If results of evaluation are not r.ceptable, modrfy or replace valve as 4 required. l l b. Provide information needed to implement proposed method (s) for resolving outlier. i 1 i ! 4. COMMENTS 1 l S. CERTIFICATION: ! The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, j and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment { to be verified for seismic adequacy: Approved by: s Date: 3////9/ Date: O/ $$
- # ~ f' 1
1
1 g PEACH BOTTOM ATOMIC POWER STATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: A0241-080A PIMS ID: AO-2-01A-080A SQUG Class: 7
Description:
'.A MAIN STEAM LINE INBOARD ISOLATION VALVE Building: Drywell- U2 Floor El.: W Room: DW2-18
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - Capacity vs. Demand Caveats x Anchorage seismic Interaction Other i
- b. Describe all the reasons for the outlier l - Centerline of pipe to top of operator is outside limit of Figure B.7-2 of GIP.
i i
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
- Perform analysis to demonstrate acceptability.
1
- b. Provide information needed to implement proposed method (s) for resolving outlier.
t
- 4. COMMENTS PECO Calculation PS-285, Rev. O resolves the caveat for operator weight and length by demonstrating that the valve is adequate for a minimum seismic acceleration of 3.0g in the vertical and horizontal directions.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment
- to be verified for seismic adequacy
Approved by: 04md 2 Date: da.g44 Date: 2,!f B!94
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) lD: A02-01-080B PIMS ID: AO-2-01A480B SQUG Class: 7 Descriptkai; B MAIN STEAM LINE INBOARD ISOLATION VALVE Building: Drywell- U2 Floor El.: 134 Room: D/W2-18
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulomant
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand
- Caveats x Anchorage Seismic interaction !
Other
- b. Describe all the reasons for the outlier
- Centerline of pipe to top of operator is outside limit of Figure B.7-2 of GIP.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
Perform analysis to demonstrate acceptabihty.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
- 4. COMMENTS PECO Calculation PS-285, Rev. O resolves the caveat for operator weight and length by demonstrating that the valve is adequate for a minimum seismic acceleration of 3.0g in the vertical and hortzontat directions.
I
- 5. CERTIFICATION: 1 The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, I and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment i to be verified for seismic adequacy: i Approved by: h h8 Date: 4Y!$d
" Date: E EB 94 7,-
l
- r l
/1 i
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) 10: A02 01080C PIMS ID: AO 2-01A480C SQUG Class: 7
Description:
C MAIN STEAM LINE INBOARD ISOLATION VALVE Building: Drywell U2 Floor El.: 134 Room: DW2-19 l l
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulpment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand Caveats x l . Anchorage ! Seismic interaction Other j b. Describe all the reasons for the outlier
- Centerline of pipe to top of operator is outside limit of Figure B.7-2 of GIP.
i
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- n l V 1
- a. Define proposed method (s) for resolving outlier.
Perform analysis to demonstrate acceptability, i 1 j b. Provide information needed to implement proposed method (s) for resolving outlier. l i
- 4. COMMENTS f PECO Calculation PS-285, Rev. O resolves the caveat for operator weight and length by demonstrating that the valve is adequate for a minimum seismic acceleration of 3.0g in the vertical and horizontal directions.
1 l
- 5. CERTIFICATION:
- The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outtiar issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy
Approved by: vm O. M aJ Date: 2 9/
- ,$ Date: ClZ.A/9L 4
4 g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 3 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) i ID: A02-01-o800 PIMS ID: AO-241A4600 SQUG Class: 7
Description:
D MAIN STEAM LINE INBOARD ISOLATION VALVE Building: Drywell- U2 Floor El.: 134 Room: DM2-20 l
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eautoment I
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - Capacity vs. Demand Caveats x Anchorage Seismic Interaction Other
- b. Describe all the reasons for the outlier l
- Centerline of pipe to top of operator is outside limit of Figure B.7-2 of GIP.
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION s a. Define proposed method (s) for resolving outlier.
Perform analysis to demonstrate acceptability.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
- 4. COMMENTS PECO Calculation PS-285, Rev. O resolves the cavest for operator weight and length by demonstrating that the valve is adequate for a minimum seismic acceleration of 3.0g in the vertical and horizontal directions.
4
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, ' and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment to be verified for seismic adequacy: Approved by: W Date: =1.!2 / _- l Date; &f88 V4 j-
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
,. ID: AO2 01-066A PIMS 10: AO-2-01A-086A SQUG Class: 7
Description:
A MAIN STEAM UNE OUTBOARD ISOLATION VALVE Building; ReactorBldg-U2 Floor El.: 135 Room: R2-30 l l
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulpment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - I Capacity vs. Demand Caveats x Anchorage j Seismic Interaction Other
- b. Describe all the reasons for the outlier l Distance from pipe centertine to operator outside hmits of Figure B.7-2 of GIP.
. 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
4 Perform analysis to demonstrate acceptability. i
- b. Provide information needed to implement proposed method (s) for resolving outlier.
- 4. COMMENTS PECO Calculatxm PS-285, Rev. O resolves the caveat for operator weight and length by demonstrating that the valve is adequate for a minimum seismic acceleration of 3.0g in the vertical and horttontal directions.
- 5. CERTIFICATION:
i The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment j to be verified for seismic adequacy: Approved by: N ' JL Date: 2./2[/9/ l0
. % 2 Z.. J, d. A A.
Date e 6./u
I g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) O
'g .. ID: A02-01-086B PIMS ID: AO-2-01A-0868 SQUG Cisas: 7
Description:
B MAIN STEAM UNE OUTBOARD ISOLATION VALVE Building: Reactor Bidg - U2 Floor El.: 135 Room: R2-30 , 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - capacity vs. Demand Caveats x Anchorage seismk: Interaction
- Other
. b. Describe all the reasons for the outlier Distance from pipe centerline to operator outside limits of Figure B.7-2 of GIP. l
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
Perform analysis to demonstrate acceptability. 4
- b. Provide information needed to implement proposed method (s) for resolving outlier.
4
- 4. COMMENTS PEC6 Calculation PS-285, Rev. O resolves the caveat for operator weight and length by demonstrating that the valve is adequate for a minimum seismic acceleration of 3.og in the vertical and horizontal directions.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment
; to be verified for seismic adequacy:
l Approved by: d '
/1 Date: JL/2.8Nf/
^
Date: L/&R fL v i
4 g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: A02-01-oe6C PIMS ID: AO-241A-086C SQUG Class: 7 Descripuc6: C MAIN STEAM LINE OUTBOARD ISOLATION VALVE i Building: RonctorBidg U2 Floor El.: 135 Room: R2-30 i
- 2. OUTLIER ISSUE DEFINITION - Mechan! cal and Electrical Eaulomant
- a. Identify all the screening guidelines which are not met.
j (Check more than one if several guidelines could not be satisfied.) - - 1 j Capacity vs. Demand Caveats X Anchorace Seismic Interaction , Other i l b. Describe all the reasons for the outlier
- Distance from pipe centerline to operator outside limits of Figure B.7-2 of GIP.
i 4 i i i
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION j a. Define proposed method (s) for resolving outlier.
l Perform analysis to demonstrate acceptability.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
- 4. COMMENTS PECO Calculation PS-285, Rev. O resolves the caveat for operator weight and length by demonstrating that the valve ls adequate for a minimum seismic acceleration of 3.0g in tre vertical and horizontal directions.
I
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment ! to be verified for seismic adequacy: l Approved by: Date: I[ YY , Date: Eb8 fi
I i i b PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92
- OUTLIER SEISMIC VERIFICATION SHEET (OSVS) 4
- lD: A02-01086D PIMS ID: AO-241A-0860 SQUG Class: 7
{
Description:
D MAIN STEAM LINE OUTBOARD ISOLATION VALVE j Building: ReactorBlog U2 Floor El.: 135 Room: R2-30 I i 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment i a. Identify all the screening guidelines which are not met. j (Check more than one if several guidelines could not be satisfied.) - - $ Capac!!y vs. Demand Caveats x , Anchorage l Seismic interaction Othef l b. Describe all the reasons for the outlier i 3
. Distance from pipe center 0ne to operator outside hmits of Figure B.7-2 of GIP.
l f
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION j a. Define proposed method (s) for resolving outlier.
- Perform analysis to demonstrate acceptabihty.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
i i 4. COMMENTS
- PECO Calculation PS-285, Rev. O resohres the caveat for operator weight and length by demonstrating that
- the valve is adequate for a minimum seismic acceleration of 3.0g in the vertical and horizontal ditedions.
l i ! 5. CERTIFICATION: I The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, ! and resolution of the outlier issues listed above will satisfy the requirements for this item of equipment j to be verified for seismic adequacy: 1 Approved by: Date: L f[
; O -
(+z2 HAM _ va,e; ms, 7
. __ ___ _ _ .. _ ._ _ _. _ __ _ _ _ _ __ m i
g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 i OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: A02 03-35A PIMS ID: AO-2-03435A SQUG Class: 7 Desenption: SCRAM DISCHARGE VOLUME OUTBOARD ISOLATION VENT W l Building: Reactor Bldg - U2 Floor El.: 135 Room: R2-26 i j 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment i a. Identify all the screening guidelines which are not met. j (Check more than one if several guidelines could not be satisfied.) - - 4 Capacity vs. Demand x Caveats j Anchorage ! Seismic Interaction Other
- b. Describe all the reasons for the outlier Demand exceeds Capacity (ABS vs. CRS) i a
lg 3. PROPOSED METHOD OF OUTLIER RESOLUTION lV
- a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS. l f b. Provide information needed to implement proposed method (s) for resolving outlier. N/A l i J l ! 4. COMMENTS l VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been verified to be seismically adequate. i j 5. CERTIFICATION: The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, { and satisfies the requirements for this item of equipment to be verified for seismic adequacy: a Approved by: .
/
as Date: /!r/ #4
/ /
- b* Date: MMf4 q t #
4
j g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 i OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: A02-03-35B PIMS ID: AO-2-03-035B SQUG Class: 7
Description:
SCRAM DISCHARCE VOLUME OUTBOARD ISOLATION VENT W ! Building: ReactorBldg U2 Floor El.: 135 Room: R2-24 )
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eautoment 1
- a. Identify all the screening guidelines which are not met.
j (Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand l x i Caveats 4 Anchorage j Seismic Interaction i Other
- b. Describe all the reasons for the outlier i
- - Demand exceeds Capacity (ABS vs. CRS) ,
l i
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION i
- a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS. J 1 l b. Provide information needed to implement proposed method (s) for resolving outlier, ! N/A 4
- 4. COMMENTS I VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been verified to be seismically adequate.
l l
- 5. CERTIFICATION:
4 The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: - - Date: / / M
, O n w' Date: e 4
e
1 i i l g PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: RV2-02-071A PIMS ID: RV-2-02-071A SQUG Class: 7
Description:
A SAFETY REUEF VALVE l
; Building: Drywell- U2 Floor El.: 154'-9" Room: DNV2-27 1
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eautoment
! a. Identify all the screening guidelines which are not met.
- (Check more than one if several guidelines could not be satisfied.) - -
- Capacity vs. Demand x Caveats Anchorage Seismic interaction O'h*'
I , b. Describe all the reasons for the outfier Demand exceeds Capacity (ABS vs. CRS) i 1 I i
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION l l a. Define proposed method (s) for resolving outlier.
- - Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS.
d j b. Provide information needed to implement proposed method (s) for resolving outlier. ;
*^
l 1 i 4. COMMENTS VECTRA Calculation 0067 o00844014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been verired to be seismically adequate. 4
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: ' Date: //3#/94 Y& Date: 1.'. tlf&
1 y PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 j OUTLIER SElSMIC VERIFICATION SHEET (OSVS) 1D: RV2-02 071B PIMS ID: RV-2-02-071B SQUG Class: 7 ]
Description:
B SAFETY REUEF VALVE i' Building: Drywell U2 Floor El.: 154'-9" Roont Dw2-27 j 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment I a. Identify all the screening guidelines which are not met. j (Check more than one if several guidelines could not be satisfied.) - Capacity vs. Demand f x Caveats l Anchorage Seismic Interaction , Other , b. Describe all the reasons for the outlier
- - Demand exceeds Capacity (ABS vs. CRS) l 1
l
- 3. PROPOSED METHOD OF OUTLIER RESOLUTIO_N_ l
- a. Define proposed method (s) for resolving outlier. l 1 - Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been verified to be seismically adequate.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: h N' b Date: /!30!9S
,Y -
Date: Cft.ffi
l g PEACH BOTTOM ATOMIC POWER STATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: RV242-071C PIMS ID: RV-2 02-071C SQUG Class: 7
Description:
C SAFETY REUEF VALVE Building: Drywell- U2 Floor El.: 154'-9" Room: DAv2 27
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand 6 x l Caveats Anchorage Seismic interaction Other
- b. Describe all the reasons for the outlier
- Demand exceeds Capacity (ABS vs. CRS)
{
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered. in-structure SSE response spectra by scaling IPEEE RRS.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS VECTRA Calculation 0067-00064-C 014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been verified to be seismically adequate.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: Date: //3d[#/ O GR ",. O.
- Date un r
i
- g PEACH BOTTOM ATOMIC POWER STATION GIF Rev. 2, Corrected 2/14/92 i OUTLIER SEISMIC VERIFICATION SHEET (OSVS) lD: RV2-02-071D PIMS ID: RV-2-02471D SQUG Class: 7
Description:
D SAFETY REUEF VALVE i Building: Drywell- U2 Floor El.: 154'-9" Room: DNV2-27
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eautoment
- a. Identify all the screening gui(stines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand x . Caveats Anchorage ! Seismic Interaction i other i i b. Describe all the reasons for the outlier Demand exceeds Capacity (ABS vs. CRS) 4
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION j a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS. i
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS VECTRA Calculation 0067 o0084-C-014, Rev. 2 resolves Capacity vs. Demand issue. Tlie'reTore, this ,
component has been verified to be seismically adequate. I
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: - M i a Date: /!8/ ([
) g -
M - Date: l'!E/f 6
g PEACH BOTTOM ATOMIC POWER STATION GlP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: RV2-02-071E PIMS ID: RV-242-071E SQUG Class: 7
Description:
E SAFETY RELIEF VALVE Building: Drywell U2 Floor El.: 154'-9" Room: D/w2-27
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eaulomant
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) - - Capacity vs. Demand x Caveats Anchorage Seismic Interaction Other
- b. Describe all the reasons for the outlier Demand exceeds Capacity (ABS vs. CRS)
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS VECTRA Calculation 0067-00084-C-014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been verified to be seismically adequate.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, ' and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: M ' Date: / $
- Date: O!&!f6 fi I
PEACH COTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID: RV2 02471F PIMS ID: RV-2 02-071F SQUG Class: 7
/
Description:
F SAFETY REUEF VALVE Building: Drywen . U2 Floor El.: 154*-9" Room: DW2-27
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equinment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) . Capacity vs. Demand & x Caveats Anchorege Seismic interaction Other
- b. Describe all the reasons for the outlier
- Demand exceeds Capacity (ABS vs. CRS)
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier.
Generate realistic, median-centered, in-structure SSE response spectra by scaling IPEEE RRS.
- b. Provide information needed to implement proposed method (s) for resolving outlier.
N/A
- 4. COMMENTS VECTRA Calculation 0067-00064-C-014, Rev. 2 resolves Capacity vs. Demand issue. Therefore, this component has been venfMH$ to be seismically adequate.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: ' Date: / / 94 Date: LlCl9L 7.. l
- t
y PEACH BOTTOM ATOMIC POWER STATION GIP Rev. 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) 10: RV2-02-071G PIMS ID: RV-2-02471G SQUG Class: 7
,I
Description:
G SAFETY REUEF VALVE Building: DryweX - U2 Floor El.: 154'-9" Room: DW2-27
- 2. OUTLIER ISSUE DEFINITIQN - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) . Capedty vs. Demand x Caveats Anchorage l 2 Seismic Interaction i Other I b. Describe all the reasons for the outlier I - f Demand exceeds Capacity (ABS vs. CRS) i i i i i 3. PROPOSED METHOD OF OUTLIER RESOLUTION
- a. Define proposed method (s) for resolving outlier. l
- Generate realistic, median centered, in-strue.ture SSE response spectra by sca';ng IPEEE RRS.
{ 1 I 1
- b. Provide information needed to implement proposed method (s) for resolving outlier.
I N/A
- 4. COMMENTS
- VECTRA Calculation 0067-50084-C-014, Rev. 2 resolves Capadty vs. Demand issue. Therefore, this a,omponent has been verified to be seismically adequate.
- 5. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, - and satisfies the requirements for this item of equipment to be verified for seismic adequacy: Approved by: a Date: /!!# Y, - Date; <- 9 (.
g PEACH BOTTOM ATOMIC POWEd'STATION GIP Rev. 2, corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) g ID: RV2-02-071H PIMS ID: RV-2-02 071H SQUG Class: 7
.}
Description:
H SAFETY RELIEF VALVE Building: Drywil . U2 Floor El.: 154'-9" Room: D/W2-27
- 2. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Eauloment
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.) -}}