Text

USI A-46 Seismic Evaluation Rept for BVPS Unit 1
	ML20097C837
Person / Time
Site:	Beaver Valley
Issue date:	01/31/1996
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20097C823	List: ML20097C818; ML20097C837; ML20097C843;
References
	REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9602120052
	Download: ML20097C837 (200)
	v • d • e

{{#Wiki_filter:O ATTACHMENT 1 1 USI A-46 SEISMIC EVALUATION REPORT for l O l t Beaver Valley Power Station Unit No.1 ' (BVPS-1) January,1996 gn ( -

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O TABLES Inh!t 4.2 List of Procedures Used for Safe Shutdown Equipment List Review......(page 14) j 5.1 Effective Grade for Plant Structures......(page 26) i { 5.2 Equipment Intent but Not Letter of Caveat Summary....(page 27) 5.3 Equipment Outlier Description and Resolution Summary......(page 28) . 5.3.1.5 Air-operated Valves - Alternatives to Air Supply.......(page 29) l' 6.2 Tank and Heat Exchanger Outlier Description and Resolution Summary.......(page 33) 7.3 Raceway Outlier Description and Resolution Summary......(page 35) pt v iii

s CONTENTS Section g

1. INTRODUCTION 1 l i

1.1 Purpose 1 1.2 Plant Description 1 ! 1.3 Background I l 1.4 Report Organization 2 l

2. SAFE SHUTDOWN EARTHQUAKE 4 l l

2.1 Seismicity 4 l 2.2 Ground Response Spectra 4 2.3 In-Structure Response Spectra 4

3. PROJECT TEAM 7 3.1 Utility Representatives 7 3.2 Seismic Capability Engineers 7 3.3 Third-Party Auditors 7

4. SAFE SHUTDOWN EQUIPMENT LIST (SSEL) 8 4.1 Safe Shutdown Path Selection 8 4.1.1 Safe Shutdown Systems 8 4.1.2 Supporting Systems 11 4.2 Operations Department Review of SSEL 12 4.3 Safe Shutdown Equipment List and Subsets 13 '

5. MECHANICAL AND ELECTRICAL EQUIPMENT REVIEW 16 5.1 Summary of Review 16 1

5.1.1 Seismic Capacity vs. Demand 16 5.1.2 Equipment Class Descriptions 17 5.1.3 Equipment Anchorage 19 5.1.4 Seismic Interaction 20 5.2 Instances ofIntent but Not Letter of Caveat Met 21

 ,                  5.3      Summary of Outliers                                               21 i

6. TANKS AND HEAT EXCHANGER REVIEW 31 6.1 Summary of Review 31 6.2 Summary of Outliers 31

7. CABLE AND CONDUIT RAL.2WAY REVIEW 34 7.1 Summary of Raceway Review 34 7.2 Evaluation of Bounding Samples 34 7.3 Summary of Outlien 34

8. PLAN FOR ADDRESSING UNRESOLVED OUTLIERS 37

9. SIGNIFICANT OR PROGRAMMATIC DEVIATIONS 38 FROM THE GIP

10. THIRD-PARTY AUDIT 39

11. REFERENCES 44 APPENDIX 2.2 BVPS-1 Ground Response Spectra APPENDIX 2.3 BVPS-1 Amplified Response Spectra (ARS/FRS)

APPENDIX 3.2 Resumes for Seismic Capability Engineers APPENDIX 4.3-1 Composite Safe Shutdown Equipment List (SSEL) APPENDIX 4.3-2 Seismic Review Safe Shutdown Equipment List (SSEL) APPENDIX 4.3-3 Alphabetical Listing of SSEL Components by EIN APPENDIX 5.1 Screening Verification Data Sheets (SVDS) APPENDIX 10.0 Third-Party Audit Reports ( > t ii

GLOSSARY OF ACRONYMS \ AFW Auxiliary Feedwater

 . AMSAC ATWS Mitigating System Actuation Circuitry ARS      Amplified Response Spectra ATWS     Anticipated Transient Without Scram BAT      Boric Acid Tank BVPS-1   Beaver Valley Power Station Unit No.1 CVCS     Chemical and Volume Control System DBE      Design Basis Eanhquake DLC      Duquesne Light Company EDG      Emergency Diesel Generator EIN,    Equipment Identification Number EPRI    Electric Power Research Institute FRS     Frequency Response Spectra GERS    Generic Equipment Ruggedness Spectra GIP     Generic Implementation Procedure for the Seismic Verification of Nuclear Plant Equipment GL      Generic Letter GRS     Ground Response Spectmm HAD     Heat Actuated Device HVAC    Heating, Ventilation & Air Conditioning IRS     In-structure Response Spectra (also ARS)

O LAR MCC Limited AnalyticalReview Motor ControlCenter MSIV Main Steam Isolation Valves MWR Maintenance Work Request NRC Nuclear Regulatory Commission OSVS Outlier Seismic Verification Sheet P.E. Professional (Registered) Engineer PRT Pressurizer Relief Tank PSA Peak Spectral Acceleration RCP Reactor Coolant Pump RCS Reactor Coolant System ROB Rule of the Box RPI Rod Position Indication RWST Refueling Water Storage Tank SCE Seismic Capability Engineer SEWS Screening Evaluation Work Sheet SI Safety Injection SLC&RS Supplemental Leak Collection & Recirculation System SQUG Seismic Qualification Utility Group SRT Seismic Review Team SSE- Safe Shutdown Eanhquake SSEL Safe Shutdown Equipment List iv

GLOSSARY OF ACRONYMS (Cont.) SSER Supplemental Safety Evaluation Repon SSI Soil-Structure Interaction SVDS Screening Verification Data Sheet l T. S. Technical Specification Te Cold Leg Temperature Th Hot Leg Temperature

 . USI  Unresolved Safety Issue VCT   Volume Control Tank ZPA   Zero Period Acceleration O

O V

p Section'1 d INTRODUCTION 1.1- PURPOSE The purpose of this repon is to document the seismic evaluations performed to address Unresolved Safety Issue (USI) A-46 at BVPS-1, using the Generic Implementation Procedure (GIP) by the Seismic Quali6 cation Utility Group (SQUG). The relay evaluations are documented in a separate report. 1 1.2 PLANT DESCRIPTION The BVPS-1 is located in Shippingport Borough, Beaver County, Pennsylvania, on the south l bank of the Ohio River. The site is approximately one mile from Midland, Pennsylvania, five miles from East Liverpool, Ohio, and approximately 25 miles from Pittsburgh, Pennsylvania. The coordinates are 40a37' 18" north and 80a26' 2" Lat. The Universal Transverse Mercator coordinates are 547,900 meters east and 4,496,680 meters north. The site comprises j approximately 501 acres including 26 acres of right of way. /spproximately 479.5 acres, with the j exception of approximately 21.5 acres on which BVPS-1 is located, are owned by Duquesne Light Company (DLC). The 21.5 acres on which BVPS-1 is located are owned jointly by the Central Area Power Coordinating Group (CAPCO) members as tenants in common without right ofpanition. J

1.3 BACKGROUND

Because of the extent of the changes in the requirements for seismic qualification of equipment over the years, the U.S. Nuclear Regulatory Commission (NRC) initiated USI A-46, " Seismic Quali6 cation of Equipment in Operating Nuclear Plants," in December 1980. The purpose of USI A-46 is to verify the seismic adequacy of essential equipment in operating plants which had not been qualified in accordance with more recent criteria. In 1982, SQUG was formed to develop a practical approach for seismic qualification of equipment in operating plants. The approach developed by SQUG was to use experience with the performance of power plant and industrial equipment in actual earthquakes as the primary basis for evaluating the seismic ruggedness and functionality of essential equipment in nuclear power plants. In 1983, the NRC issued NUREG 1018 (Reference 6) which includes a general ; endorsement of the use of experience data for veri 5 cation of the seismic adequacy of equipment in nuclear plants. In early 1987, the NRC issued Generic Letter (GL) 87-02 to owners of operating nuclear plants which were licensed prior to development of modern seismic qualification standards. The r recipients of GL 87-02 are referred to as A-46 plants and include BVPS-1. Essentially, all owners ( of A-46 plants, including Duquesne Light Company, are SQUG members. GL 87-02 requires Page 1 - 1

(p) owners to take action to verify the seismic adequacy ofimportant equipment in their plants. The SQUG approach embodied in the GIP is explicitly recognized by the NRC as the preferred method for accomplishing this objective. In 1992, the NRC issued Supplement No. I to GL 87-02 which transmitted Supplemental Safety Evaluation Report No. 2 on SQUG GIP, Revision 2, as corrected on February 14, 1992. References 1 and 2 are the basis for the seismic evaluations described in this report. In Reference 4, Duquesne Light Company described their approach for resolving USI A-46. This approach was accepted by the NRC in Reference 5. 1.4 REPORT ORGANIZATION The remaining sections of this report are organized in accordance with Section IL9.4 of the GIP. These sections include the following:

   . Section 2, " Safe Shutdown Earthquake" - The BVPS-1 Ground Response Spectra (GRS) end In-Structure Response Spectra (IRS) are described. The bases for determining how seismic demand is determined for each ergipment are provided in Section 5, and documented on the SVDS forms in Appendix 5.1 of th.s report.
   . Section 3, " Project Team" - The Duquesne Light Company project team is discussed.

Resumes for SCEs are included in Appendix 3.2 of this report.

   . Section 4, " Safe Shutdown Equipment List (SSEL)" - This section containsm' formation from the SSEL report recommended for submittal to th: NRC, per Section II.9.2 of the GIP.

Descriptions of the safe shutdown path selection, plant operation procedures used, and Duquesne Light Company Operations Department review of the SSEL are discussed. Lists of equipment on the SSEL and Seismic Review SSEL are included in Appendices 4.3-1 and 4.3-2 of this report. The list of equipment included on the Relay Review SSEL is included in the Relay Report, Reference 3.

   . Section 5, " Mechanical and Electrical Equipment Review" - Screening Verification and Walkdown results for mechanical and electrical equipment are discussed, in addition to the SVDS forms provided in Appendix 5.1. Instances in which the intent of a caveat is met without meeting the speci6c wording of the caveat rule are identified. A summary of outliers and their resolution is provided.
    . Section 6, " Tanks and Heat Exchanger Review" - Results of the tanks and heat exchangers review are discussed. A summary of outliers and their resolution is provided.
    . Section 7, " Cable and Conduit Raceway Review" - Results of the raceway review, including bounding samples and outliers, are summarized.

O . Page 2

Section 8,'" Plan for Addressing Unresolved Outliers" - The plan and schedule for addressing 4 O remaining unresolved oudiers are discussed.

                                     -a
          . Section 9, "Signihcant or Programmatic Deviations from the GIP" - A statement is made that no signi6 cant or' programmatic deviations from the GIP were made for the BVPS-1 A-46 Program.
          . Section 10, " Third-Party Audit" - The Third-Party Audit is summarized, including resolution of recommendations made by the Auditor (s) during the initial Audit. The Audit report is included in Appendix 10.

Tables, figures and appendices are numbered according to the report section which references them. O I O Page 3

l Section 2 1 SAFE SHUTDOWN EARTHQUAKE 2.1 SEISMICITY The BVPS-1 area is quiet seismically. Historically, no earthquake of epicentral Intensity V, or greater, Modified Mercalli, has occurred within 80 miles of the site. The nearest canhquake of epicentral Intensity V, or greater, took place on June 27,1906 at Fairport, Ohio (near Cleveland), 80 miles northwest of the site. Only one earthquake having an epicenter within 60 miles of the site has been reponed. This earthquake reportedly took place at Sharon, Pennsylvania, approximately 40 miles north of the site, on August 17, 1873. Details are limited, but it is

     . estimated that it had an epicentral intensity of Modi 6ed Mercalli III and certainly no more than IV.

The site has experienced vibratory ground motion as a result of distant earthquakes, most notably l the 1812 earthquake at New Madrid, Missouri, and the 1886 ennhquake at Charleston, South ) Carolina. It is estimated that the latter canhquake may have caused ground motions in the ; vicinity of the site with an intensity of Modified Mercalli IV in the upland areas and possibly as l high as V along some of the river banks, where the structures were located on alluvial soils of l relatively recent age. Probably the New Madrid, Missouri, canhquakes resulted in much the same i i level of motion at Pittsburgh and Shippingport areas. Data are fragmentary and uncertain Itis known, however, that the nearest significant damage from the New Madrid earthquakes was at Cincinnati, Ohio, approximately 330 miles from the epicenter and about 250 miles closer to the epicenter than the site. The Attica, New York area,180 miles northeast of the site, experienced an earthquake of epicentral Intensity VIII Modified Mercalli on August 12, 1929, and two , earthquakes of epicentralIntensity VI have also occurred in this Attica area. An earthquake of epicentral Intensity VH to VIII occurred near Anna, Ohio, on March 8,1937, and three earthquakes of epicentral Intensity VII have occarred in this same area. Anna, Ohio, is approximately 200 miles west of the site. Eanhquake: which occurred in the Attica, New York, , area and the Anna, Ohio, area apparently were not percoptible at the site. l 2.2 GROUND RESPONSE SPECTRA The BVPS-1 is founded on a soil site. The site Oprational Basis Earthquake (OBE) is based on i 0.06 g maximum ground acceleration at zero paiod, and the site Design Basis Earthquake (DBE)/ Safe Shutdown Earthquake (SSE) is based on 0.125 g maximum ground acceleration at zero period. SSE response spectra for each canhquake used for the analysis of Class I structures are givenin Appendix 2.2. 2.3 IN-STRUCTURE RESPONSE SPECTRA l j A As part of the re-analysis of Seismic Class I piping systems performed in 1979, Amplified Response Spectra (ARS) were developed using Soil Structure Interaction (SSI) methodology. l I l l Page 4

Appendix 2.3 presents the in-structure response spectra for the SSE, which were used in the SQUG evaluations. The methodology used in SSI-ARS is based upon a layered elastic media l model for soil and a iumped mass model for structures. Analysis using these models involves:

1. The calculation of frequency-dependent stiffness at the surface of a layered medium using the program REFUND

2. Modi 6 cation of a speci6ed surface motion to account for embedment of the structure

3. The application of kinematic interaction principles to modify translational input specified at the surface to both a translational and rotational motion at the base of the rigid structure :

foundation using the program KINACT

  ~ 4. Analysis of the structural model sur soned on frequency-dependent springs using the            ,

program FRIDAY. ! The resulting ARS developed from this af.odology were compared with ARS developed using a detailed fmite element representation of the underlying soil medium with a lumped mass representation of the containment structure using the program PLAXLY. The amplified values of , acceleration computed using the REFUND /KINACT/ FRIDAY method are generally 30 to 100 i l percent larger than values computed using the more rigorous PLAXLY approach. ! l Varations m sod properties have generally been accounted for by developing ARS using mean values of soil moduli and damping ratio values adjusted for strain levels associated with canhquakes, and peak spreading the resulting ARS. i i l The soil propenies are developed from subsurface data into a soil pro 61e, in which each stratum ; has its own soil parameters. The required dynamic propenies in each layer are described first by the small strain values of shear modulus, and then site response analysis is used to develop values l i of damping and shear modulus that are compatible with the strains to be expected during an 4 earthquake. ! Subsurface information was obtained from several sources, which include the BVPS-1 FSAR, the , Geotechnical Design Criteria for BVPS-2, and the report on the Soil Densification Program for l BVPS-2. Two seismic cross-hole surveys were performed by Weston Geophysical Laboratory, i the first in 1968 and the second in 1977, in conjunction with the BVPS-2 Soil Densification , ' 1 Program. I The computer program SHAKE developed by Schnabel, Lysmer, and Seed was used to calculate l strain compatible shear moduli, and damping from low strain values was determined from field j testing and empirical formulae based on laboratory test data. j l I The amplified response spectra used in the analysis are based on the methodology described in the 1 report entitled " Soil-Structure Interaction in the Development of Amplified Response Spectra for lO BVPS-L" This report was submitted to the NRC by Duquesne Light Company on June 11,1979, l l Page5

(q) and included USNRC requested revisions (Docket No. 50-334). The USNRC SER, dated 5 92, issued relative to GL 87-02 and GIP-2, categorized BVPS-1 as having " conservative, design" in-structure response spectra. The FRS of Appendix 2.3 are plotted at the 1% damping level associated with the SSE for structural analysis. The coaversion to 5% damping curves (and 3% where needed) for A-46 use, was performed using the GIP section 4.4.3 guidance. O . O Page 6

i i Section 3 PROJECT TEAM 3.1 SEISMIC REVIEW TEAM (SRT) The SRT comprised members of the Duquesne Light Company Nuclear Group's staff and engineers of the consulting firm of EQE International. Safe Shutdown Equipment List (SSEL) , and cabletray/ conduit walkdowns were performed by DLC seismic capability engineers (SCEs), as l were valve evaluations. Cabletray/ conduit and tank / heat exchanger analyses were perfonned by

both DLC and EQE SCEs. Anchorage analysis for SSEL items was performed almost exclusively by EQE. Additionally, EQE performed a preliminary, visual review of cabletrays/ conduits to !

confum the DLC sampling approach, and responded to questions on the SSEL and site ARS. As described below, EQE performed the third party audit, and prior to that, a preliminary audit. The DLC SRT included a representative from the Operations Department, and six (6) SCEs, one ; (1) system engineer and two (2) relay review engineers from the Nuclear Engineering Department (the system engineer also performed relay review, making three (3) relay review engineers : available). A member of the Nuclear Safety Department assisted in communicating with the NRC. All SCEs, system and relay engmeers received SQUG training for their areas of involvement. Additionally, members of the Nuclear Safety Department and Operations Department had individuals trained who are not directly involved in the project currently. Beyond the SRT, Nuclear Engineering Department staff engineers were involved in furnishing analysis to the SCEs for valve weak-link, component materials, and pump performance ! evaluations. j i 3.2 SEISMIC CAPABILITY ENGINEERS The SCEs totaled six (6), as described abcve, and were trained by SQUG. Their resumes are included in Appendix 3.2. - i 3.3 THIRD-PARTY AUDITORS l The third-party audit was performed by EQE International's Mr. Gregory Hardy. His report and j resume can be found in Appendix 10.0. Additionally, EQE's Mr. Ron Cushing performed a preliminary review earlier in 1995. A discussion of their findings and DLC's corrective actions can be found in Section 10. Mr. Cushing's qualifications are included with the SCEs of i Appendix 3.2. O . Page 7

O Section 4 V SAFE SHUTDOWN EQUIPMENT LIST (SSEL) The BVPS-1 Safe Shutdown Equipment List (SSEL) was prepared in accordance with Section II.3 and Appendix A of the GIP. 4.1 SAFE SHUTDOWN PATH SELECTION 4.1.1 Safe Shutdown Systems The following sections describe the safe shutdown systems and main operating procedure steps necessary to meet USI A-46 requirements. The four basic functions of reactivity control, pressure control, inventory control, and decay heat removal are covered. Each section describes the plant systems and main operator actions that are used to accomplish these safe shutdown functions. 4.1.1.1 Reactivity Control Function Initial reactivity control is achieved by control rod insertion initiated by either an automatic or manual reactor. trip. The rods gravity fall into the core if either reactor trip breaker opens g resuhing in an interruption of power to the gripper coils. The operators will be able to verify that Q the reactor is subcritical by checking the power or intermediate range nuclear instruments (NI). The source range nuclear instruments will become available within 30 minutes following the reactor trip / shutdown. Once energized the source range instruments can also be used to monitor subcriticality. The GIP does not require the NI system to be listed on the SSEL. In the unlikely event that the reactor could not be tripped the operators would follow Emergency Operating j Procedure FR-S.1 " Response to an ATWS." The rod position indication (RPI) system was not , chosen because the control rod drive system is nuclear steam supply system (NSSS) supplied and all accident analysis assumes only one rod remains out of the core. Boric acid addition is then used for long term reactivity control to compensate for the positive reactivity added by xenon decay and RCS cooldown (positive reactivity is added due to a cooldown of the fuel - doppler coefficient, and the cooldown of reactor coolant - moderator l temperature coefficient). When the unit is at power, the quantity of boric acid retained in the l RWST and boric acid storage tanks by technical specifications greatly exceeds the quantity required to compensate for xenon decay and concurrent RCS cooldown. For the plant shutdown, charging and boration will be accomplished by operating a minimum of one charging pump. The source of borated water could be from the RWST or the boric acid tanks; which will be used will depend upon whether other non-SQUG equipment is available (primarily the letdown subsystem). Two separate and independent flow paths can be used for RCS makeup and boration: the seal injection lines to the seals of the RCPs and the normal charging line to the loop B cold leg. The boration will probably have to be done without any CVCS letdown because the letdown line is assumed to be isolated due to a loss of containment instmment air. O) w Page 8 .

I Portions of the reactor plant sampling system are included so that the operators will be able to . OP confirm that they are borated to the value required by Operating Surveillance Test OST 1.49.2 prior to blocking the automatic SI signals. The safe shutdown equipment in these flowpaths is itemized on the SSEL (items 1101 through 1248). 4.1.1.2 Pressure Control Function i The RCS is the primary system used to achieve pressure control. Control is achieved by using the I pressurizer heaters and the power-operated relief valves (PORVs)/ Safeties. ! 1 The pressurizer has three PORVs in parallel that provide overpressure protection during normal operations. The PORVs may not be available because the air supply to the valves cannot be guaranteed; instead, the three pressurizer safeties were utilized for overpressure protection. Operation of the ' safeties is the backup for the PORVs which will operate if instrument air is available or accumulator tank GN-TK-1 A or B is used. Pressure reduction (control) is accomplished by natural circulation RCS cooldown or intermittent use of the PORVs. ; l Based on the premise that failure of a pressurizer relief tank (PRT) rupture disk will not negate ! the ability to maintain a safe shutdown, no PRT associated equipment was selected. Wide range RCS pressure instruments were selected to monitor the pressure control function. The equipment used for the pressure control function is itemized on the SSEL (items 2101 through 2230B). 4.1.1.3 Inventory Control Function The charging portion of the CVCS accomplishes RCS inventory control by providing makeup water. Charging flow to compensate for coolant contraction due to the RCS cooldown and any inventory losses due to leakage will be accomplished by operating a minimum of one charging pump. The pump will take its suction from the RWST or the boric acid tanks and inject borated water to the B cold leg via the charging header and/or into the RCS via the reactor coolant pump (RCP) seal injection lines. Charging flow control valve (FCV-CH-122) fails open on a loss of air. If this occurs charging flow could be manually controlled using valves CH-28,29 and 30. Ifit becomes necessary to remove inventory from the RCS due to minimal charging flow with no letdown, two options are available: 1) reestablish RCS letdown and swap the charging pump suction back to the VCT, or 2) cool the RCS to shrink the inventory thus reducing volume. The RCS can be borated to maintain adequate shutdown margin during the cooldown. If it is reestablished, letdown will prevent RCS overfilling. The CVCS letdown lines including the VCT are not on the SSEL and may not be available because there are many air operated valves in the flowpath. . Page 9

i l l l l l The availability of seal retum flow is not required to achieve a safe shutdown and may be locally or remotely isolated. When isolated, RV-CH-382A lifts and diverts RCP seal return flow to the PRT. RWST and pressurizer level indication, and charging and RCP seal injection flow indication will serve to monitor the inventory control function. The equipment used for inventory control is identified on the SSEL (items 3101 A through 3321). 4.1.1.4 Decay Heat Removal Function The decay heat removal function is satisfied by the RCS, main steam and auxiliary feedwater (AFW) systems. Heat is transferred by natural circulation of the reactor coolant from the core to the steam generators (SGs); heat is released from the secondary side of the SGs by releasing steam to the atmosphere via the residual heat release valve and/or an atmospheric steam dump valve (s). The RCS is a Westinghouse three-loop design capable of natural circulation heat transfer. This provides a means of heat removal when the RCPs are unavailable. Adequate SG level is required to maintain natural circulation. Confirmation of flow while in natural circulation is accomplished through the monitoring of the q following instrumentation: SG levels and pressures, RCS pressure and loop temperature b indications, Tcold (Tc) and T hot (Th) or thermocouples. Subcooling within the RCS is maintained by keeping system pressure greater than the saturation pressure which coincides with the hottest RCS temperature and continuous removal of heat from the SGs. l The main steam (MS) system is used to remove decay and sensible heat from the RCS. The secondary system could be isolated by operation of the main steam trip valves if the condenser or i the condenser steam dumps become unavailable. The trip bypass valves are assumed to be closed I at power but could be closed if required. Steam will be released to atmosphere via the Residual Heat Removal (RHR) valve or an atmospheric steam dump. The RHR and atmospheric steam dumps require instrument air for operation. However, they can be manually opened / throttled if the air system is unavailable. The MS components required for a safe shutdown are listed on the SSEL. A non-rugged pressure switch may cause the atmospheric steam dumps to open during the seismic event; if this would occur, the steam released would lessen the demand on the condenser steam dumps; or, if offsite power is lost, the atmospheric steam dumps would already be open. The auxiliary feedwater (AFW) system is required to remove decay heat. SG inventory control is provided by the AFW system. The AFW system consists of one Turbine Driven AFW pump and two motor driven AFW pumps. All AFW pumps receive their water supply from the 140,000 gallon primary demineralized water storage tank (WT-TK-10). WT-TK-10 does not contain enough water to remove decay heat for 72 hours. If needed, the AFW pumps could be supplied with river water by manually repositioning a few valves. It is not expected that river water would Page 10

1 have to be used because there are sufficient quantities of water available in other tanks which could be utilized in the 8-10 hours available before WT-TK-10 is depleted. The AFW pump recirculation flow control valves are air operated and fail closed. In the event that this becomes a problem late in the scenario the pump (s) could be run intermittently to prevent pump damage due ) to low flow. l l The decay heat removal components required for a safe shutdown are included on the SSEL l (Items 4101 A through 4217). 4.1.2 Suonortine Systems The following sections describe the supporting systems necessary to ensure that the basic safe shutdown functions described above will be achieved. These systems do not directly perform a ] safe shutdown function but must operate in order to support the safe shutdown systems. ! 4.1.2.1 River Water The river water system is required to supply cooling water to several components required for a safe shutdown. Included are the emergency diesel generators (EDGs), the charging pumps and items in the control room ventilation system. The river water system has sufficient capability to also supply water to the SGs if needed. Seal water and motor cooling water will be self-supplied from the River Water pump discharge lines. 4.1.2.2 Emernency Power The EDG, station batteries, inverters and emergency electrical distribution systems are required to support all the required shutdown functions. Operability of the EDG also requires the support of the air start tanks, the fuel oil system including the day tanks and the underground tanks, the ; remote excitation cabinet and the load sequencer. Other electrical support includes the 4KV, ) 480VAC,120VAC and 125VDC emergency busses and distribution systems (transformers, l MCCs, inverters and battery chargers). 4.1.2.3 HVAC Several areas of the plant require ventilation during safe shutdown operations to protect electrical equipment from heat damage and allow access for operator actions. These areas are (1) Control Room (2) Emergency Switchgear/ Battery Rooms (3) Charging Pump Cubicles (using SLC & RS) (4) The AFW Pump Room (using SLC & RS) (5) The Diesel Generator Rooms (6) The River Water Pump Cubicles O Page11

i Containment cooling would be lost during the shutdown due to the loss of cooling water. l h Operating experience and calculations show that containment internal temperatures do not exceed 120 degrees during a worst case loss of containment cooling. No operator action in containment is anticipated. If required, operators could still make containment entries using ice vests. 4.1.2.4 Heat Trace Heat Trace required to maintain the RWST flow path is included to assure cold weather availability. Review of BAT piping resulted in a determination that its flowpath will experience ; ambient indoor temperatures only and maintain a 68'F minimum temperature. l 4.1.2.5 Fire Protection Fire protection systems are included where their seismically-induced activation could affect SSEL l component function.' These SSEL components include the AFW Pumps, EDGs and the :harcoal l bed filters. The auxiliary feedwater pumps and charcoal bed filters are protected by heat actuated 7 devices (HADs). The HADs activate a deluge valve upon sensing a fire, releasing water to the ! system. The emergency diesel generators are protected by a carbon dioxide blanket system, ! triggered by HADs. All three systems are automatic in actuation. 4.it.2.6 General e Emergency lighting is provided throughout the plant. If it should fait during a seismic event, ( flashlights or portable lanterns will be used to support operator actions. , Communication is usually done by phone or plant page; should these fail, communication would ! be by walkie-talkie. l Decay heat will need to be removed from the spent fuel pool during the 72 hour period. No fuel pool cooling equipment is on the SSEL because decay heat removal or makeup to the fuel pool could be accomplished using existing procedures utilizing river water as the heat sink. ; Equipment that is required to remain inactive during plant shutdown, including that which could , load the diesel generators, is included for purposes of relay review to assure that no seismic-induced activation occurs. I 4.2 OPERATIONS DEPARTMENT REVIEW OF SSEL The Operations Department SSEL review was performed by Mr. Jeff Shipe, NSS. Mr. Shipe has been a Nuclear Control Operator at Shippingport Atomic Power Station, 1974-1978, an Operating Foreman, 1978-1984, and an Assistant Nuclear Shift Supervisor at BVPS-1,1984-present. His review included both a review of the SSEL to the procedures listed in Table 4.2 and a successful plant shutdown enactment performed on the BVPS-1 Simulator. Only SSEL equipment was used during the simulation, and unavailable (non-SSEL) control board indications were taped-over. Page 12 l l

l The SSEL is endorsed by Mr. Shipe by letter, with computer-dated and reviewer-initialed, individual pages. No procedures unique to SQUG are planned; however, the Operations Department has undertaken to introduce the SQUG shutdown scenario into operator traming sessions. 4.3 SAFE SHUTDOWN EQUIPMENT LIST AND SUBSETS j Printouts of the SSEL database are included in Appendices 4.3-1,4.3-2 and 4.3-3. Appendix 4.3-1 is a printout of the composite SSEL, which includes equipment requirmg seismic reviews and relay reviews. The compositt SSEL includes all equipment for which either a seismic adequacy or j a relay chatter evaluation is required. It is orgamzed by line number series as follows: l e Reactivity Control - 1000 Series: Rod drop - 1100; Boration - 1200.

. )

Pressure Control - 2000 Series: Reduction - 2100; Increase - 2200.
Inventory Control- 3000 Series: CVCS - 3100; Leakoffs - 3200.
Heat Removal- 4000 Series: AFW - 4100; Steam Dump - 4200 l l

D e Support Systems - 5000 Series: River Water - 5100; HVAC - 5200; Electrical (EDG) - 5300.

Electrical Enclosures / Supports - 8000 Series.

This organization by function results in duplicate entries since equipment may serve multiple functions. However, there are 528 individual components on the SSEL. SSEL line numbers as described above were used on forms (SSEL, SEWS, SVDS, OSVS); however, the Equipment Identification Number (EIN) is considered the p;imary tracking number. Forms such as SEWS created at various stages of SSEL evolution, had referenced SSEL line numbers corrected by hne-out/ revision after the SSEL was finahzed Appendix 4.3-2 contains the Seismic Review SSEL; Appendix 4.3-3 is the SSEL sorted alphabetically using EIN. The composite SSEL is the base document for the other lists derived from it and, as noted previously, is approved by the Operations Department representative. It is also approved by the i systems engineer who authored it, Mr. Ronald Ferrie. Mr. Ferrie also acted as lead relay reviewer j and his credentials can be found in the BVPS-1 A-46 Relay Evaluation Report. ! I l O 1 i Page 13

7 l 1 Table 4.2 l List ofProcedure,s Used for I Safe Shutdown Equipment List Review Based on the events observed during a simulation of a DBE at the BVPS Unit 1 Simulator, the i following procedures would be used: 1 l i

1) . Emergency Operating Procedure E-0 Reactor Trip or Safety Injection.

Purpose:

provides l actions to verify response of the automatic protection systems following manual or 1 automatic actuation of a reactor trip or safety injection, to access plant conditions, and to ) identify the appropriate recovery procedures. j

 .       Verify the reactor is shutdown                                                                           ;
 .       Verify the turbine is tripped                                                                            l
 .       Verify steam to the turbine plant is secured                                                             l
 ..      Verify the main unit generator is tripped                                                                i
 .       Verify power is available to the two emergency busses
 .       Verify safety injection is not required

2) Emergency Operating Procedure ES-0.1 Reactor Trip Response.

Purpose:

provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.

 .       Control plant temperature via the steaming rate
 .       Restore parameters to expected ranges
 .       Verify AC poweris aligned
 .       Verify natural circulation of the reactor coolant system

3) Emergency Operating Procedure ES-0.2 Natural Circulation Cooldown. Purpoce:

provides actions to perform a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under reopirements that will preclude any upper head void formation. The following three procedures will provide additional guidance to control the plant in the event systems are disabled by the DBE.

1) Abnormal Operating Procedure 1/2.75.3 Acts of Nature - Earthquake.

Purpose:

provides action in the event of an earthquake.

2) Abnormal Operating Procedure 1.34.1 Loss of Stat *on Instrument Air.

Purpose:

provides instructions necessary for controlling the plant during a loss of station instrument air; provides a list of all air operated valves outside of containment and the positions they fail l to on loss of air. 4 Page 14

l

3) Abnormal Operating Procedure 1.34.2 Loss of Containment Instrument Air.

Purpose:

O provides instructions necessary for controlling the plant during a loss of containment instrument air; provides a list of all air operated valves in containment and the positions

      "$f ail fto onloss of air.

In addition, other procedures may be used as deemed necessary by operations personnel. l P O Page 15 -

_ . _ . .__. _ _ .. _ _ _ ..~_ ._ _ _ _ __ _ _ _ .._ _ . _ _ _ _ _ i h-Section 5 f MECHANICAL AND ELECTRICAL EQUIPMENT REVIEW i ' l i ! 5.1

SUMMARY

OF REVIEW i i The reviews of the seismic adequacy of mechanical and electrical equipment on the BVPS-1 Safe Shutdown Equipment List (SSEL) were performed in accordance with Section II.4 of the Generic i i Implementation Procedure (GIP). The equipment which was reviewed for seismic capacity

(Capacity) versus seismic demand (Demand), can be found in Appendix 4.3-2, the Seismic Review SSEL. The list includes some equipment that is found in or on other SSEL items, and considered seismically adequate thru " Rule-of-the-Box" (ROB) criteria. Such equipment is listed to identify its importance. Each item was inspected for mounting, interaction and any special i i- vulnerability. Separate Seismic Evaluation Walkdown Sheets (SEWSs) were not generated for

, these items, but deficiencies were noted on the host SEWS and Outlier Seismic Verification Sheet (OSVS) as applicable. Equipment characteristics were reviewed using record documents prior to each walkdown. A SEWS for each item was then completed to the extent possible in the field. Unanswered questions were recorded separately as unresolved issues. SEWS considerations that could not be ; answered in the field were completed at a later date, and the item's status held open. If a change on a SEWS was necessary, the initiating SCE initialed the change. Walkdown inspection teams comprised a minimum of two (2) SQUG-trained Seismic Capability Engineers (SCE), occasionally three (3), and always included at least one (1) Professional Engmeer (PE) licensed in the State of Pennsylvania. Initially, separate trains of equipment were ; inspected by separate SRTs to determine if significant differences in judgment existed -- none did. Most walkdowns occurred dtuing BVPS-1 refueling outages 9R and 10R, but some off-outage inspections did occur as well. During the walkdowns, electrical enclosures were inspected for device mountings that were unusual and which could significantly amplify. No unusual features were found. - The lead relay . reviewers joined the SCEs at times to verify essential relay types. Signed Screening Verification Data Sheets (SVDSs) for each SSEL equipment item are contained , in Appendix 5.1. 5.1.1 Seismic Canacity vs. Demand i The BVPS-1 Ground Response Spectrum is enveloped by the GIP Bounding Spectrum; also, the , BVPS-1 Floor Response Spectra (FRS) are bounded by 1.5 times the Bounding Spectrum (BS) - j all at 5% damping. The second criteria (FRS vs.1.5BS) was used exclusively to satisfy the Capacity versus Demand caveat. This negated the need to determine height above grade. The O* grade elevations for various buildings containing SSEL components can be found in Table 5.1. Page 16 l l

                                                                                     ._       _ - _ - - _ _ - _                   __A

_ _ . _ _ _ - _ _ _ _ . . _ ~ _ _ _ _ _ _ _ . - _ _ . . _ _ . _ l I q No use of Generic Equipment Ruggedness Spectra (GERS) was made in establishing equipment y Capacity. No SSEL equipment failed to satisfy the Capacity versus Demand screen, except for two (2) intake stmeture HVAC fans and the River Water Pumps. No record FRS exists for the elevation at which they exist (see outlier discussions).~ 5.L2 Eauipment Class Descriptions The BVPS-1 SSEL equipment is briefly described by equipment class in the following sections. Class 1 - Motor Control Centers (MCCh MCCs manufactured by Allis-Chalmers are found in the auxiliary building (735'), diesel generator building (735'), safeguards building (735'), service building (713') and intake structure (705'). MCCs by Gould can be found in the safeguards building (756'). The MCCs are floor-mounted by way of welds to embedded channels. All have top entry conduit, often times substantial in number. The Allis-Chalmers MCCs were tested for ; response characteristics by WYLE Laboratones, which determined a lowest fundamental frequency of11 Hz. Class 2 - Low Voltage Switchgear (LVSh The equipment supplied by General Electric is located at elevation 713 of the service building. They are anchored by concrete expansion anchors. The equipment supplied by Westinghouse Electric Corp. is located at elevation 713 of the service building. They are anchored by concrete expansion anchors. l Class 3 - Medium Voltage Switchgear (MVSh This equipment is simplied by ITE and General Electric. All are located at elevation 713 of the service building. '

                                                                                     , ,s anchored by welds to embedded channels.

Class 4 - Transformers: Six (6) transformers are on the SSEL. Four (4) transformers are

   . supplied by General Electric, and located at elevation 713 of the service building. The internal core and coils were subsequently replaced by ITE Gould cores and coils and the supporting base was revised to accommodate the change. Two of these transformers are attached with welds to embedded steel and two are anchored with concrete expansian anchors. Two (2) transformers are supplied by Westinghouse Electric Corp. and are located in the safeguards building at elevation 722. These are mounted on a Unistmt frame.

Class 5 - Horizontal Pumos: The horizontal pumps include three (3) CH charging pumps in the aux. building at elevation 722, two (2) boric acid transfer pumps in the aux. building at elevation 752, four (4) diesel generator fuel oil transfer pumps in the diesel generator building at elevation 735, and two (2) motor driven auxiliary feedwater pumps in the safeguards building at elevation 735. The pumps are supplied by Pacific Pump Dresser, Goulds Pumps Inc., Sier-Bath Pump, and IR/ Cameron. Class 6 - Vertical Pumps: The vertical pumps include three (3) river water pumps. They are located in the intake structure at elevation 705. They are supplied by Byron Jackson. O Page 17

l Class 7 - Fluid-ooerated Valves: Fluid-operated valves are located in the auxiliary building at elevation 722, in the safeguards building at elevations 735, 752 & 768, in the reactor containment building at elevations 707,718,752 & 767, in the intake structure at elevation 705 and the diesel generator building at elevation 735. Various manufacturers supplied the air- operated valves. 13cluded in this class are relief valves and pressure regulators. Class 8A - Motor-ooerated & Solenoid-ooerated Valves: Motor-operated valves are located in I the auxiliary building at elevation 722, in the safeguards building at elevations 722 & 735, in the reactor contamment building at elevations 718, & 767, in the intake structure at elevation 705, in the service building at elevation 713, in the PG pump room at elevation 722 and the diesel generator building at elevation 735. Various manufacturers supplied the motor-operated valves. Cla::s 8B - Solenoid-ooerated Valves: Solenoid-operated valves are located in the auxiliary building at elevation 722, in the safeguards building at elevations 722, 735 & 751 andinthe reactor containment building at elevations 722,735 & 751. Various manufacturers supplied the solenoid- operated valves. These valves are associated with the charging system, main steam system, reactor coolant system, and the reactor coolant samH t em. Class 9 - Fans: Fans not included with air handling units (Class w) are associated with the emergency switch gear supply .and exhaust in the service building at elevation 725, diesel generator building exhaust at elevation 756, control room return air in the service building at elevation 713, leak collection exhaust in the auxiliary building at elevation 768 and the intake structure supply at elevation 725. American Warming and Vent, supplied the fans in the intake O structure and Buffalo Forge Co. supplied the remaining fans. Class 10 - Air Handlers: The air handlers include the control room air conditioning unit in the service building at elevation 713, the containment air compressor receiver tank air dryers in the service building at elevation 713 and the river water cooling coils associated with the control room air conditioning system in the service building at elevation 713. American Air Filter Co, supplied the cooling coils, Hankinson Corp. supplied the air drier tank and Trane supplied all the other equipment in this class. Class 11 - Chillers: No chillers are included on the SSEL j Class 12 - Air Compressors: The air compressors on the SSEL are associated with the control room air conditioning system. They are supplied by Honeywell Inc. and are located in the service building at elevation 713. Class 13 - Motor-Generators: No motor-generators are on the SSEL j Class 14 - Distribution Panels: The distribution panels are as follows: DC bus and vital bus distribution panels in the service building at elevation 713 and 735, 120 volt AC power distribution panels in the service building at elevation 713, 125 volt DC power distribution panels in the service building at elevation 735 and pressurizer heaters power distribution panels in the Page 18

1 I safeguards building at elevation 735. This equipment was supplied by Reliance Electric Co., Static O Products inc. and Harlo/ Westinghouse. Class 15 - Batteries on Racks: These are located in the service building at elevation 713. There are four (4) battery sets - two (2) each by Exide and by Gould. Class 16 - Batterv Chargers & Inverters: Battery chargers are supplied by LA Marche Mfg. Co. and are located in the service building at elevation 713. Inverters are supplied by Solidstate Controls Inc. and are located in the service building at elevation 713. Class 17 - Engine-Generators: There are two (2) engine-generator sets on the SSEL. Both are supplied by Electro Motive. Class 18 - Instruments on Racks: Instruments on racks are located in the auxiliary building at elevation 722, in the safeguards building at elevations 722, 735, 751 & 768, in the reactor containment building at elevations 701 & 718, in the yard area at elevation 735 and in the service building-at elevation 713. Various manufacturers supplied these instruments. Class 19 - Temocrature Sensors: The RCS RTDs are located in the reactor containment building at elevation 718. They were supplied by RDF Corp. Class 20 - Instmmentation & Control Panels and Cabinets: Instrumentation and control panels and cabinets include the control room consoles, vertical boards and panels located in the serece O building. Panels and cabinets are located in other service building areas at eievations 713 & 735, in the diesel generator building at elevation 735, in the safeguards building at elevation 735, in the service building at elevations 713 & 735 and the auxiliary building at elevation 768. Various manufacturers supplied the panels and cabinets. Class 21 - Tanks and Heat Exchanners: This equipment is located in the auxiliary building at elevations 735, 722 & 752, in the diesel generator building at elevation 735, in the reactor containment building at elevation 767 and in the yard areas at elevations 724 & 735. Various manufacturers supplied the tanks and heat exchangers. Class 0 - Other: This class includes the dampers in the ventilation and air conditioning systems for the control room air conditioning system, the emergency switchgear exhaust, the diesel generator building supply and exhaust, quench spray pump room outside air intake isolation, auxiliary feedwater pump room exhaust, leak collection and filtration system exhaust and the intake structure outside and recirculation air system. 5.1.3 Eauipment Anchorare Evaluation ofloadpath was performed by the SCEs during walkdowns. On several occasions washers were replaced with larger types to improve anchor effectiveness. In general, all electrical enclosures were judged to be of adequate or superior structural design and fabrication. O Page 19

Anchorage types found to be used on the SSEL equipment include embedded bolts, concrete O expansion anchors, thru-bolts, nelson studs, welds and embedded channels and angles. Sizes and locations of anchorage were recorded during walkdowns for use later in performing anchorage capacity analysis. NDE was used on two (2) occasions - in determining the length of the bolts threaded into the shell anchors for the building service panel due to gaps under the base; in confirming the lengths of unknown expansion anchors on the PORV air / nitrogen accumulator tanks. Concrete pads are tied to the floor slab thru reinforcing as detailed on BVPS-1 design drawings. No confirmation was attempted and such pads were considered to be adequate to transfer equipment loads to the floor slab. Concrete expansion anchor types include Hilti Kwik-bolt & Drop-In, and Phillips Red-Head Self-Drilling & Drop-In. The length of all Hilti Kwik-bolts is known by virtue of controlled procurement, while shell types are standardized by their manufacturer. One instance of mismatched anchor components was discovered. These were replaced, and other anchors of the same size, timeframe and plant location extracted to prove that the problem was limited to the subject equipment. l Expansion-type anchorage checks were made during the walkdowns and were predominantly hand-wrench tightness checks during 9R; whereas, calibrated torque wrenches were used during 10R. Craft help was used for these checks during outages, while SCEs performed the checks O non-outage. All accessible anchorage was checked for tightness. Inaccessible anchors were few and considered adequate based upon their use - e.g., shear loads only, or gravity loads "self weight." Numerous shell anchors were inspected for proper recess after the attachment bolt had l been removed. Several anchors that appeared to be in contact with an equipment base had the bolt hole enlarged slightly, and the anchor torque-tested to check for movement - none occmred. Walkdown inspection also included the observation of cracks and construction joints near expansion anchors. Anchor analysis was performed by EQE using the GIP guidelines and reduction factors. Anchorage that failed either walkdown inspection or analytical review was classified as an outlier. Walkdown anchorage outliers that involved instalht ion errors or deficiencies were corrected as they were found. See the outlier descriptions of Section 53 for examples. 5.1.4 Seismic Interaction The SRTs assessed interaction risk w-hile performing the walkdowns using the GIP guidelines of Section II.4.5 and Appendix D. Credibility, soft targets and consequences each are considered. l Several situations in the control room necessitated the removal of unanchored storage cabinets. l The control room ceiling panels will also be secured as described later in the outlier discussion section. O Page 20

As noted above, the Allis-Chalmer MCCs were determined by WYLE Laboratories to have a O lowest fundamental frequency of 11 Hz. This was used with the highest FRS PSA for any MCC location (intake structure, El. ~03) in the deflection formula: displacement 6 = PSA/ [ 2xf ]2; where PSA is the peak spectral acceleration and f is the enclosure's overall fundamental frequency of response. The resulting maximum deflection is 0.10 inch. This determination along with the conduit entry was considered in evaluating interaction where these types of MCCs were near a wall. If the object interacting with the MCC was itself flexible, then combined, worst case deflection was . considered, or the possibility of interaction eliminated thm modification. The Gould MCCs had no potential interaction concerns because of the space around them. Nu ,erous instances of potential impact were identified. Where simple modifications were possible, maintenance work requests (MWRs) were generated and corrections made. Other potential impact situations were recorded for analytical evaluation of likelihood, consequence, and/or modification. See Section 5.3 for examples ofinteraction outliers. 5.2 INSTANCES OF INTENT BUT NOT LETTER OF CAVEAT MET Instances in which the intent of a caveat is met without meeting the specific wording of the caveat rule are identified in Table 5.2. 5.3

SUMMARY

OF OUTLIERS A total of 230 outliers were identified for BVPS-1 SSEL equipment items. Short descriptions of each equipment outlier and its resolution are provided in Table 5.3. The following sections provide additional detail regarding selected outliers. 5.3.1 Open (Unresolved) Outliers 5.3.1.1 As required by the GIP, interaction concerns were addressed by the SRT dunng walkdown inspections while viewing individual equipment items. Questions of impact credibility l and risk of damage were answered by individual SCEs as they viewed each component's , l surroundings. Generally, fluorescent light fixtures and their tubes were not judged to be threats, I nor were wall-mounted emergency lights with batteries. However, as a result of third-party audit comments and additional inspection, these two interaction items have been determined to require further attention. All emergency lights and batteries in seismic areas will be inspected to assure that attachment hardware (e.g., screws) are in-place. Florescent light fixtures hung from chains will have their attachment hooks closed, and florescent tubes in fixtures near essential relay enclosures will have retention clips installed. 5.3.1.2 The control room (CR) ceiling is a continuous, suspended, wall-to-wall system oflight-weight, formed-metal, open-lattice panels. Initial inspection proved that the panels resist removal from their individual support frames due to interference with certain features of the support members However, further review disclosed some panels that would lift easily, which would allow them to fall. With some panels falling, the integrity of the remaining grid cannot be assured. Since failures of suspended ceilings are common in seismic events, the CR ceilint will have , l Page 21

l l l positive restraint added to it in the form of tie-wraps at panel corners, or panel retention clips. l C. Overall support of the entire ceiling is judged to be adequate. ! 5.3.1.3 The reactor coolant system temperature detectors (RTDs) were added to the SSEL prior to the last refueling outage, but were erroneously considered to be passive devices. They were given full support system and relay review, but were not walked down. Therefore, the SRT ! did not view the installation for interaction (anchorage review does not apply). Since these ! devices were installed in 1990 by way of a QA-controlled plant modification (DCP-698), both l they and their installation are qualified to IEEE-344-75. Therefore, all SQUG concerns other than interaction are satisfied. DCP installation criteria included recommended wiring slack, and two-over-one situations are generally not concerns in the reactor containment. However, the RTDs , will be considered outliers until the SRT views the installation during the next refueling outage. I 5.3.1.4 The HVAC dampers and control systems on the SSEL which are not directly attached to an air-handler were originally qualified by.way of various levels of test and analysis by the , architect / engineer (Stone & Webster) and suppliers (Honeywell, American Warming & < Ventilating). None of the existing documentation can be considered as equivalent to current I requirements. Since SQUG does not speci6cally consider dampers located apart from air-handlers, these dampers are considered outliers (Class 0). Furthermore, since SQUG is developing criteria with which to evaluate such dampers, they will continue as outliers until SQUG criteria is j available. All were given support system and relay review as appropriate, and walked down. Any additional interaction concerns have been identi6ed as separate issues for resolution. 5.3.1.5 The BVPS-1 air supply system is not seismically qualified for functionality. Consequently, seven air-operated valves (AOVs) on the SSEL are not assured air supply for shutdown function as required (See Table 5.3.1.5). Three (3) of these, the power-operated relief valves (PORVs), have accumulator tanks available. The tanks are normally used with nitrogen during refueling, but are pressurized to normal air system pressure during power operation. Because of check valves, they would retain sufficient air to actuate the PORVs in the event of air system loss. The tanks and valving system are on the SSEL and have been judged to be adequate to operate the PORVs. The remaining four (4) valves require operator action for use in the SQUG shutdown scenario. 5.3.1.6 Transformers 1-8N,1-8N1,1-9P and 1-9P1 are outliers due to a lack of SQUG-required top bracing on the coils and because no analysis of the coil support arrangement is provided. The original quahfication was based upon testing for the U.S. Navy and proper operation during the Sylmar earthquake. While the existing base-mounted coil support appears to be substantial, detailed vendor information for it is limited. Structural analysis of the base supporting the coils demonstrated that weak-way bending is not a problem. The basis for the SQUG coil brace caveat is not well-documented; consequently, it is not clear 1 whether it represents actual damage observed or vendor testing. The SQUG database contains ! two (2) " failures" of this type (coil contact with enclosure), but the transformers continued to l function in both cases. Top bracing of the coils would appear to be very difficult to achieve while I O maintaining electrical integrity, The presence of shipping braces appears to be unrealistic. The Page 22 -

s transformers will remain cutliers until the coil support concern can be evaluated as to capacity, the coils braced, or the SQUG concern rationalized. 5.3.1.7 Three (3) control board strip chart recorders (LR-QS-100, TR-RC-410, TR-RC-413) are on the SSEL. They are cantilevered and meet the general acceptance criteria of Equipment Class 20. However, the separate review suggested by the Class 20 caveats identified the fact that these Westinghouse devices are required to have an independent rear support. Such a support is lacking for these recorders, making them outliers. Problem Report No. 1-95-605 and Basis for Continued Operation 1-95-012 have been written for this deficiency, and the recorders will either be supported properly or r@ laced with types not requiring support. Three (3) strip chart recorders (FR-MS-478,488,498) of the same type are attached directly to the top of the benchboard. Their actual support conditions differ from the front and rear support arrangement which was their test configuration. The difference and its effect on their performance requires further review. 5.3.1.8 Switchboard Panel DC-SWBD-2 has two (2) ofits four (4) anchors located less than the minimum distance from a construction joint (1.5" vs. 2.0"). The 2" minimum represents a 60% reduction of capacity, below which the SQUG reduction is 100% (full capacity requires 5" clear). The 100% reduction effectively eliminates the anchorage on one side of the panel, analytically leaves the panel without resistance to overturning, and makes the panel an outlier. The SQUG 100% reduction for a free edge nearby was based upon test results, and is perhaps due to the lateral forces created by expansion type anchors (Note: TRW Nelson stud testing - although substantially different in anchor mechanics - indicates approximately a 33% reduction in capacity for a comparably located " free" edge). However, while the construction joint will undoubtedly affect the anchors' capacity, it is not a free edge. The construction joint, to the contrary, was formed when one concrete section was poured against another. The construction joint is, therefore, a tight concrete-on-concrete planar surface that intersects an anchor's cone ofinfluence. Such failure mechanisms as side-bursting and concrete splitting at a free surface, which are known to reduce anchor capacity, would not be present with a confined concrete surface such as this. The affected anchor.will clearly have some capacity. SQUG anchorage analysis of the DC-SWBD-1, 3 and 4 panels resulted in anchor bolt tensile loads of 54% of allowables. Since shear capacity would be unaffected (13% of capacity), the interaction limit of 100% would allow a 33% reduction in allowable to be taken for the nearness ofthejoint. ! In summation, the subject panel will be identified as an outlier until the anchors can be either adequately tension tested in-situ, or additional anchorage provided thru design modification. While in-situ testing does not establish capacity margins (safety-factors) as normally assumed, the need for such margins - wide-ranging installation uncertainty regarding concrete strength, hole size, angularity and setting method - is absent with an existing anchor. Only concern over i dynamic effects would make a margin prudent. For in-situ testing, a factor of three (3) for test load to calculated demand load would satisfy SQUG margins . Page 23

                                                                                           . _ - - _   ~ - . - . .

1 1 l l l 5.3.1.9 Inverter INV-VITBUS-4 also has anchorage that is too close to a floor constmetion ( joint. Its anchors, 3/4" diameter Hilti Kwik-bolts, are one (1) inch distant versus an acceptable 4" min, for 40% capacity; 7.5" for 100% capacity. The subject anchors were installed during a design l modification (DCP-204) and were torque and tension tested as part of the QC controls in-place at l that time. As discussed above, the applied testing proves that the anchor will resist a certain level and type ofloading, with the exception of dynamic effects. The inverter is, therefore, considered an outlier under SQUG, to be resolved by testing or design modification. l 5.3.1.10 Four (4) motor-operated valves, MOV-CH-ll5C & E, MOV-CH-350, and MOV-MS-105 are outliers. Th three (3) CH valves have MOV operator restraint, while the MS valve is j outside of the SQUG ewpment class. They each possess weak-link analysis that requires further , review to confirm seismic adequacy. Initial indications are that all will be found acceptable. ; l 5.3.1.11 Control room HVAC VS-AC-1 A is an outlier due to missing anchorage on one side of the unit, where it attaches to the supporting platform. A problem report and MWR are being generated to document and repair the attachment deficiency. 5.3.1.12 The River Water Pumps WR-P-1 A, B & C are outliers because of Capacity / Demand and ' a discharge column overall length that exceeds that of the SQUG database pumps. There exists a record calculation, however, that considers the effect of anticipated seismic loads on the pumps. It concludes that the pumps will perform properly. The pump will be considered an outlier until the record analysis can be reviewed in greater depth for confirmation ofits conclusions. 5.3.1.13 The AMSAC Panel contains programmable controllers for which no SQUG database ! guidance exists. Record qualification documentation exists, however, that will be reviewed for purposes of resolving the outlier. Additionally, SQUG is developing criteria for such devices which may also be used to confirm the AMSAC equipment's Capacity. l 5.3.1.14 VS-F-57A, B & C are located at elevation 725 of the intake structure in the pump cubicles. FRS are available at the cubicle floor elevation, but not at the fan elevation. The cubicles are rigid, missile-protection, concrete structures with minimal resonance. The fans, however, will be considered outliers until a FRS is formulated for their location and compared to 1.5BS. 5.3.2 Significant Closed Outliers 5.3.2.1 Disconnect Switches SW-1-8N1 and SW-1-9P1 both had several anchors that failed the tightness test. It was determined that a mismatch of shell anchor plug and shell had produced the ) problem. The anchors were replaced with Hilti Kwik-bolts. Additionally, two (2) shell anchors of I the same size and plant area were extracted to determine whether a particular crew performing installation may have repeated the mistake. The shells withdrawn were a Hilti Drop-in and a ! Phillips Red Head, both properly assembled and installed (withdrawal was extremely difficult). Hilti Kwik-bolts set deeper were installed as replacements. It was concluded that the mismatch installation was an isolated occurrence. Page 24 L ____. _

5.3.2.2 BAT-CHG-2 had three (3) of four (4) expansion anchors on one side fail the tightness O check. Analysis showed that the single remaining bolt would have been sufficient to prevent overturning. Since the unit could not be removed to reset or replace the problem anchors, a steel angle and Hilti Kwik-bolts were installed on that side of the charger to assure proper anchorage. 5.3.2.3 MCC-lE-7 serving the EDG was found to have no weld connecting its rear base channel (inverted) to a channel embedded in its concrete support pad. This MCCs base channel was unlike all the other MCC base channels in that it and the embedded channel were the same size, providing no location for the standard fillet weld to be placed. A butt weld should have existed at the intersection of the channel's flanges, but none was found. The deficiency was resolved by instMling flat bar tie-backs anchored to the wall along the tops of the MCCs sides. A problem report and LER were issued. . l 5.3.2.4 RK-AUX-REL A & B were missing tie-plate connections to adjacent cabinets and several base-to-support-channel bolts. These were installed, although the overall structural integrity was considered to be adequate in the as-found condition. 5.3.2.5 MOV-FW-160 is on the SSEL as a backup isolation valve requiring relay review. It was added even though several check valves exist between it and the primary system isolation valve. Check valves are rugged devices and the addition of the second isolation valve is very conservative - unless the primary valve and the multiple check valves fail, its function is totally redundant. Furthermore, the valve's supporting MCC is non-safety powered and located in the - e turbine building. The MCC cannot be qualified due to interaction concerns The MOV-FW-160 j valve is, therefore, considered an outlier; but because of the system's multiple isolation features, it j is an outlier for which no further corrective action is required. , i l l Page 25

l Table 5.1 Effective Grade for BVPS-1 Structures ! l The effective grade for the structures which contain equipment on the SSEL are listed below. l This elevation shall be used to determine if a piece of equipment is greater than or less than 40 feet above grade for the purpose of the SQUG review. The actual elevation of the equipment shall be used for comparison to the effective grade. l Blda Abr Building Effective Grade l SRVB Service Building 713'- 6" AXLB Auxiliary Building 722'- 6" : RCBX(1) Reactor Containment 690'- 11" i DGBX Diesel Generator Building 735'- 0" PG-Pump PG Water Pump Building 721'- 6" INTS Intake Structure 643'- 0" SFGB Safeguards (This designation 732'- 6" Safeguards includes the Safeguards Bldg, 722' - 6" Safeguards the Cable Vaults, Main Steam 722'- 6" MSCV Valve House, Cable Tunnel) 725'- 6" Cable Tunnel YARD Yard (South of Turbine Bldg) 735'- 0"

1) Applicable for equipment supported by the internal containment structure.

l I O

Page 26

. . . - . . . . . - . ~ . . . _ - . _ . - - . - . - . - . - . - - - . . . . O Table 5.2 Intent but Not Letter of Caveat Summary ( 8 pages) O -

l l O Page 27

Tabk, 2 !

;                                                                         Notes for Screening Verification Data Sheets i '

Eauipment ID No. Reason the Intent of the Caveat was met Without Meeting the Specific Wordina of the Caveat Rule 52-RTA 1. This component is mounted in the Reac-Tr-Swgr cabinet and is covered with the " rule of the box". The breaker is evaluated in the [' relay report 52-RTB 1. This component is mounted in the Reac-Tr-Swgr cabinet and is covered with the " rule of the box". The breaker is evaluated in the relay report BAT-BKR-1 1. Cabinet exceeds the height for the equipment class (91 1/2" vs 90"). Additional height is sheet metal only andjudged s_ -p " . BAT-BKR-2 1. Cabinet exceeds the height for the equipment class (91 1/2" vs 90"). Additional height is sheet metal only andjudged wpt.J-:c ,

2. Conduits attached to top of cabinet, by engineering judgment, have sumcient slack to allow for movement t BAT-BKR-3 1. Cabinet exceeds the height for the equipment class (91 1/2" vs 90"). Additional height is sheet metal only andjudged wr i.4,:c j

2. Conduit attached to top of cabinet, by engineering judgment, have sufficient slack to allow for movement. l BAT-BKR-4 1. Cabinet exceeds the height for the equipment class (91 1/2" vs 90"). Addit,ional height is sheet metal only and judged acceptable.

2. Conduits attached to top of cabinet, by engineering judgment, have sumcient slack to allow for movement.

I BAT-CHG-1 1. Conduits attached to top of cabinet, by engineeringjudgment, have sumcient slack to allow for movement. BAT-CHG-2 1. Conduits attached to top of cabinet, by engineering judgment, have sumcient slack to allow for movement. BAT-CHG-3 1. Conduits attached to top of cabinet, by engineeringjudgment, have sufficient slack to allow for movement. BAT-CHG-4 1. Conduits attached to top of cabinet, by engineering judgment, have sufficient slack to allow for movement. BNCHBD 1. Bottom of benchboard filled with fire foam that cannot be removed. Records indicate weh!s to embedded steel. Analysis indicated very low loading on welds and therefore judged to be acceptable. CC-E-1 A 1. A temporary lifting plate is welded to the fixed and free end supports. By engineeringjudgment this isjudged inconsequential to ! the supports seismic capability. f CC-E-1B 1. A temporary lifting plate is welded to the fixed and free end supports. By engineering judgment this is inconsequential to the supports seismic capability. t CC-E-lC 1. A temporary lifting plate is welded to the fixed and free end supports. By engineeringjudgment this is inconsequential to the i supports seismic capability. EE-TK-1 A 1. Buried tank cannot be visibly inspacted. No interaction concerns exist for the tank. , EE-TK-lB 1. Buried tank cannot be visibly inspected. No interaction concerns exist for the tank.- FCV-CH-122 1. A 3/4" conduit located above this valve is not adequately supported. By engineeringjudgment the collapse of the conduit will not ; adversely affect the function of the valve. l FCV-RC-455Cl I. This valve has a spring loaded disc that allows free flow in one direction and metered (controlled) flow in the other. It functions somewhat like a check valve and check valves are inherently rugged. FCV-RC-455C2 1. This valve has a spring loaded disc that allows free flow in one direction and metered (controlled) flow in the other. It functions somewhat like a check valve and check valves are inherently rugged. r

SVDS Notes Table 5.2 Page 1

                    . - _ . __ . _ _ . - , . . ~ - , - . _ _ . - . . .                -.-,.m...,  . . , , , m   ., . - -n.  ..       - , m._.- - . . .. m_. .._.--~    .. -     -- .f

q p p Table Notes for Screening Verification Data Sheets Eauioment ID No. Reason the Intent of the Caveat was met Without Meetina the Specific Wording of the Caveat Rule FCV-RC-455DI 1. This valve has a spring loaded disc that allows free flow in one direction and metered (controlled) flow in the other. It functions somewhat like a check valve and check valves are inherently rugged. FCV-RC-455D2 1. This valve has a spring loaded disc that allows free flow in one direction and metered (controlled) flow in the other. It functions somewhat like a check valve and check valves are inherently rugged. FE-CDL-IA 1. The anchorage calculation is not yet complete. 'Ihe four 3/8" anchors arejudged adequate for the panel.

2. The steel break glass rod on the panel (PCC-FE-I A) above isjudged to be an unlikely interaction concern based on a tug test.

All devices are mounted internally and free from impact of the steel rod. FE-CDL-1B 1. The anchorage calculation is not yet complete. The four 3/8" anchors are judged adequate for the panel.

2. The steel break glass rod on the panel (PCC-FE-1B) abcys is judged to be an unlikely interaction concern based on a tug test.

All devices are mounted internally and free from impact of the steel rod. FI-CH-122A 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. l FI-CH-124 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. FI-CH-127 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. FI-CH-130 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. FI-CH-150 1. This component is mounted on the bench board and is covered with the " rule of the box" by the vertical board. F1-FW-100A/B/C 1. These components are mounted on the vartical board and is covered with the " rule of the box" by the vertical board. FR-MS-478 1. This component is mounted on the benchboard and is covered with the " rule of the box" by the benchboard. FR-MS-488 1. This component is mounted on the benchboard and is covered with the " rule of the box" by the benchboard. FR-MS-498 1. This component is mounted on the benchboard a id ievered with the " rule of the box" by the benchboard. FT-CH-122 1. By engineeringjudgment the collapse of a lighting fixture located above this equipment will not adversely affect its function. F'l CH-150 1. Due to configuration a 1/4" clearance to an adjace.nt teach sed is allowable, no interaction is expected. HCV-CH-186 1. Differential movement between tbe valve and pipe is emimal since both are supported by the same adjacent wall. INV-VITBUS-3 1 Cabinet exceeds the height for the equipment class (84" vs 80"). This is acceptable since the cabinet is constructed of heavy gauge material and no items of significant mass are mounted in the upper 1/4 of the cabinet, cabinet meets all other G.I.P. criteria. INV-VITBUS-4 1. Cabinet exceeds the height for the equipment class (84" vs 80"). This is acceptable since the cabinet is constructed of heavy gauge material and no items of significant mass are mounted in the upper 1/4 of the cabinet, cabinet meets all other G.I.P. criteria. LI-FW-474 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. L1-FW-475 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. L1-FW-476 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. LI-FW-484 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. o.i-Wy-485 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. LI-FW-486 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. SVDS Notes Table 5.2 Page 2

( ) Tableh) Notes for Screening Verification Data Sheets Eauipment ID No. Reason the Intent of the Caveat was met Without Meeting the Specific Wording of the Caveat Rule i LI-FW-494 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. LI-FW-495 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. I LI-FW-4% 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. t LI-QS-100A/B/C 1. These components are mounted on the vertical board and is covered with the " rule of the box" by the vertical board. LI-RC-459A 1. This component is mounted on the bench board and is covered with the " rule of the box" by the vertical board.

LI-RC-460 1. This component is mounted on the bench board and is covered with the " rule of the box" by the vertical board. LI-RC-461 1. This component is mounted on the bench board and is covered with the " rule of the box" by the vertical board. LI-WF-104Al 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. , LI-WT-104A2 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. LR-QS-100 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. MCC-1-E13 1. An in-basket is bolted to the side of the cabinet. This basket is light weight and will have no adverse affect on the cabinet. ; MCC-1-E2 1. Flex conduit not used for top entry conduit. The length to support and bends in conduit are adequate to allow sufficient flexibility.

1. Flex conduit not used for top entry conduit. The length to support and bends in conduit are adequate to allow sufficient flexibility. ;

MCC-I-E4 MCC-1-E6 1. Flex conduit not used for top entry conduit. The length to support and bends in conduit are adequate to allow sufficient flexibility.- MOV-RW-102Al 1. Actuator to yoke bolts are recessed by about I thread. For 3/4" plate with 1/2" diameter bolt the factor of safety = 8 (Allis Chalmers calculation VER-0027). Therefore the recessed bolts arejudged to be acceptable.

2. The overhead lights are mounted on flexible rods. Falling lights / parts unlikely and no soft targets exist. [

MOV-RW-102A2 1. Actuator to yoke bolts are recessed by about I thread. For 3/4" plate with 1/2" diameter holt the factor of safety =8 (Allis Chalmers , i calculation VER-0027). Therefore the recessed bolts arejudged to be acceptabic. :

2. The overhead lights are mounted on flexible rods. Falling lights / parts unlikely and no soft targets exist. >

4 MOV-RW-102B1 1. Actuator to yoke bolts are recessed by about I thread. For 3/4" plate with 1/2" diameter bolt the factor of:afety=8 (Allis Chalmers ! calculation VER-0027). Therefore the recessed bolts arejudged to be acceptable. ;

2. The overhead lights are mounted on flexible rods. Falling lights / parts unlikely and no soft targets exist.

MOV-RW-102B2 1. Actuator to yoke bolts are recessed by about I thread. For 3/4" piate with 1/2" diameter bolt the factor of safety =8 (Allis Chalmers calculation VER-0027). Therefore the recessed bolts arejudged to be acceptable.

2. The overhead lights are mounted on flexible rods. Falling lights / parts unlikely and no soft targets exist.

MOV-RW-102Cl 1. Actuator to yoke bolts are recessed by about I thread. Fbr 3/4" plate with 1/2" diameter bolt the factor of safety =8 (Allis Chalmers calculation VER-0027). Therefore the recessed bolts are judged to be acceptable.

2. The overhead lights are mounted on flexible rods. Falling lights / parts unlikely and no soft targets exist.

MOV-RW-102C2 1. Actuator to yoke bolts are recessed by about I thread. For 3/4" plate with 1/2" diameter bolt the factor of safety =8 (Allis Chalmers calculation VER-0027). Therefore the recessed bolts arejudged to be acceptable.

2. The overhead lights are mounted on flexible rods. Falling lights / parts unlikely and no soft targets exist.

SVDS Notes Tabie 5.2 Page 3

1 O Table ,.2 1 O Notes for Screening Verification Data Sheets Eauipment ID No. Reason the Intent of the Caveat was met Without Meeting the Specific Wordina of the Caveat Rule 't t MOV-RW-106A 1. Actuator to yoke bolt is recessed by about I thread on I bolt. This is considered acceptable by engineeringjudgment.

2. An overhead I" stainless steel pipe is questionably supported for seismic loads. Ilowever, failure of this pipe isjudged not to ;

damage the valve. MOV-RW-114A 1. Actuator to yoke _ bolt is recessed by about I thread on I bolt. This is considered acyiable by engineeringjudgment.

2. An overhead I" stainless steel pipe is questionably supported for seismic loads. However, failure of this pipe isjudged not to ;

damage the valve. j PCC-FE-1 A 1. The anchorage calculation is not yet complete. The four 3/8" anchors are judged adequate for the panel.

2. The glass front is designed to be broken to access the manual CO2 dump control. Since the controls work aller the glass is broken f i

any breakage caused by a seismic event would not affect operation ofinternal devices.

3. The steel break glass rod on the panel isjudged to be an unlikely interaction concern based on a tug test of the rod. ,
PCC-FE-1B 1. The anchorage calculation is not yet complete. The four 3/8" anchors are judged adequate for the panel.: 2. The glass front is designed to be broken to access the manual CO2 dump control. Since the controls work after the glass is broken i any breakage caused by a seismic event would not affect operation ofinternal desices. ;; 3. The steel break glass rod on the panel isjudged to be an unlikely interaction concern based on a tug test of the rod.

PCV-GN-108 1. Missing nut on support adjacent valve isjudged not to have an adverse affect on the seismic a&quxy of this valve. R. paired per , MWR 038659 (Problem Report 1-95-39).. PCV-MS-101 A 1. Based on a review of the stress report (11700.34-NP(B)-6590-X-001-0) the ARS used in analyzing the piping is for the , containment building, since the pipe support structures are attached to the containment exterior. The Containment External j (El. 792) 5% damping curve is enveloped by 1.5 x (Bounding Spectrum).' Therefore, capacity exceeds the demand for these valves. 7 PCV-MS-101B 1. Based on a review of the stress report (11700.34-NP(B)-6590-X-001-0) the ARS used in analyzing the piping is for the i containment building, since the pipe support structures are attached to the containment exterior. The Containment External i (El. 792) 5% damping curve is emeloped by 1.5 x (Bounding Spectrum). Therefore, capacity exceeds the demand for these vah>cs. . PCV-MS-101C 1. Based on a review of the stress report (11700.34-NP(B)-6590-X-001-0) the ARS used in analyzing the piping is for the containment building, since the pipe support structures are attached to the containment exterior. The Containment External i l (El. 792) 5% damping curve is enveloped by 15 x (Bounding Spectrum). Therefore, capacity exceeds the demand for these vahes. l I l PCV-RW-130A 1. Compact pressure regulator in pipeline adjacent to a pipe support will not overstress pipe. l 2. Pressure regulator valve is similar to pressure relief valves. Subject matter expert G. l{ardy indicates regulator valves are in the ; experience database and considered appropriate in equipment class 7, PCV-RW-130B i. Compact pressure regulator in pipeline adjacent to a pipe support will not overstress pipe. j

1. Pressure regulator valve is similar to pressure relief valves. Subject matter expert G. Hardy indicates regulator valves are in the [

experience database and considered appropriate in equipment class 7. ; I SVDS Notes Table 5.2 Page 4 i i __ _ _ _ . _ ___ ___ _ , _ - _ . . _ ~ __ __ . _ ___ ._ - ___ _ _ _ _ _ ___ _ _ _ _ _ __ _ _ _ ____ _ _ _ _ _.__ __ _ _ ___ -

                                                                                                                  %                                                                                            )

(G Table ,.2 . Notes for Screening Verification Data Sheets [ Reason the Intent of the Caveat was met Without Meeting the Specific Wording of the Caveat Rule EauiDment ID No. PCV-RW-130C 1. Compact pressure regulator in pipeline adjacent to a pipe support will not overstress pipe.

2. Pressure regulator valve is similar to pressure relief valves. Subject matter expert G. Hardy indicates regulator valves are in the experience database and considered appropriate in equipment class 7.

PI-RC-402A 1. This companent is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. PI-RC-403 1. This u-ig-:- -:nt is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. PNL-AMSAC 1. Construction inspection per DCP 693 controls adequate to verify anchorage installed per the design outputs. PNL-DIGEN-2 1. An overhead fluorescent light will not adversely affect the cabinet (i.e. rugged).

2. Several loose and missing screws in the back panel (cover) of cabinet. However, there are sufficient screws to secure the panel.

PNL-PR-HTR-A 1. Anchors not accessible due to panel covering or interfering with tools. Anchorage installation adequate per GIP paragraph 4.4.1, 1 pg. 4-36, based upon existence of deadioad. PNL-PR-HTR-B 1. Anchors not accessible due to panel covering or interfering with tools. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadioad. PNL-PR-HTR-D 1. Anchors not accessible due to panel covering or interfering with tools. Anchorage installation adequate per GIP paragraph 4.4.1, I pg. 4-36, based upon existence of deadioad. PNL-PR-HTR-E 1. Anchors not accessible due to panel covering or interfering with tools. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadioad. PNL-REL-41 1. Rigid conduits at top of the panel have sufficient length and bends for adequate flexibility. RK-VS-AC-1 A 1. Anchors not accessible due to panel covering or interfering with tools. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadioad. RK-VS-AC-1B 1. Anchors not accessible due to panel covering or interfering with tools. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadicad. RK-VS-E-567 1. Laace bolt supporting auxiliary panel repeired per MWR 043338. SOV-MS-101A 1. The SOV is in the " rule of the box" with PNL-MS-101 A. SOV-MS-101 A4 1. The SOV is in the " rule of the box" with PNL-MS-101 A. SOV-MS-101B 1. The SOV is in the " rule of the box" with PNL-MS-101B. SOV-MS-101B4 1. The SOV is in the " rule of the box" with PNL-MS-101B. SOV-MS-10lC 1. The SOV is in the " rule of the box" with PNL-MS-10lC. SOV-MS-101C4 1. The SOV is in the " rule of the box" with PNL-MS-101C. ! SOV-RC-455CI 1. The SOV is mounted on a 1/2" line which is below the figure B.8-1 limits. However, SOV is independently supported and thereforejudged to be acceptabic.

2. The clearance from SOV housing is approximately 1/16" to adjacent PCV-RC-455C valve actuator. They will move in-phase and not interact therefore judged to be acceptable SVDS Notes Table 5.2 Page 5

O O Table .2 Notes for Screening Verification Data Sheets Ea.ui_pment ID No. Reason the Intent of the Caveat was met Without Meetina the Specific Wordina of the Caveat Rule j

1. The SOV is mounted on a 1/2" line which is below the figure B.8-1 limits. However, SOV is i. '-;- ndently supported and SOV-RC-455C2 thereforejudged to be acceptable. .

2. The clearance from SOV housing is approximately 1/16" to adjacent PCV-RC-455C valve actuator. They will move in-phase and ,

not interact thereforejudged to be auspuaAc t i SOV-RC-455DI 1. The SOV is mounted on a 1/2" line which is below the figure B.8-1 limits. However, SOV is independently supparted and thereforejudged to be W "-1

2. The clearance from SOV housing is approximately 1/16" to adjacent PCV-RC-455C valve actuator. They will move in-phase and not interact thereforejtaad to be auspuaAc SOV-RC-455D2 1. The SOV is mounted on a 1/2" line which is below the figure B.8-1 limits. However, SOV is independently supported and thereforejudged to be auspid,le.

2. The clearance from SOV housing is approximately 1/16" to adjacent PCV-RC-455C valve actuator. -They will move in-phase and not interact thereforejudged to be acceptable SOV-RC-456-1 1. The SOV is attached to a 1/2" tube and mounted on a support plate attached to PCV-RC-456.

SOV-RC-456-2 1. The SOV is attached to a 1/2" tube and mounted on a support plate attached to PCV-RC-456. TR-RC-410 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. TR-RC-413 1. This component is mounted on the vertical board and is covered with the " rule of the box" by the vertical board. TRF-SI-02 1. Transformer box solidly filled with epoxy. Coil attachment location is not a concern. TRF-SI-06 1. Transformer box solidly filled with epoxy. Coil attachment location is not a concern. TV-MS-101 A 1. The east face of the operator is I" clear of the platform steel. Impact is unlikely to prevent valve ciosing. TV-MS-101C 1. The east face of the operator may interact with structural steel. Impact is unlikely to prevent valve closing. TV-MS-111 A 1. Diaphragm operated valve with cast iron yoke. Caveat applies to piston or spring operated relief valves not diaphragm valves. TV-MS-IllB 1. Diaphragm operated valve with cast iron yoke. Caveat applies to piston or spring operated relief valves not diaphragm valves. TV-MS-IllC 1. Diaphragm operated valve with cast iron yoke. Caveat applies to piston or spring operated relief valves not dia$ragm valves. TV-SS-105Al 1. Unistrut tube clamp adjacent to valve is missing. Tube clamp replaced by MWR 039274. Valve supported independently of tubing. TV-SS-105A2 1. Unistrut tube clamps adjacent to valve and valve support u-bolt are missing. Tube clamp and u-bolt replaced by MWRs 032116 and 032117. Valve and tubing supported off rack. VS-C-1 Al 1. The equipment weight is small relative to the tension and shear capacity of a 3/8" redhead (4). Therefore, the anchorage is acceptable by engineeringjudgment. (Ref Calc. 8700-DSC-6534-Rev. 0) VS-C-1B1 1. The equipment weight is small relative to the tension and shear capacity of a 3/8" redhead (4). Therefore, the anchorage is acceptable by engineeringjudgment. (Ref Calc 8700-DSC-6534-Rev. 0) SVDS Notes Table 5.2 Page 6

s w Tabic 2 Notes for Screening Verification Data Sheets Eauipment ID No. Reason the Intent of the Caveat was met Without Meeting the Specific Wording of the Caveat Rule ! VS-D-40-IC 1. A missing screw on the adjacent SOV cover (MWR 33422) will not prcvent this component from operating. SOV andjunction ! box have since been replaced per TER-9768. l VS-D-40-ID 1. Missing bolts on the associated SOV andjunction box are judged to not have an adverse effect on the operation of the MOV (i.e. Prevent it from opening / closing). SOV and junction box have since been replaced per TER-9768. t VS-D-40-IF l. Poor weld quality isjudged to be structurally acceptable. VS-D-57Al 1. Damper is mounted in concrete opening with a sheet metal plenum below it. Although not physically accessible nothing is present in the plenum or concrete intake hood to be a seismic interaction concern with the damper. VS-D-57BI 1. Damper is mounted in concrete opening with a sheet metal plenum below it. Although not physically accessible nothing is present ; in the plenum or concrete intake hood to be a seismic interaction concern with the damper. VS-D-57C1 1. Damper is motmted in concrete opening with a sheet metal plenum below it. Although not physically accessible nothing is present ; in the plenum or concrete intake hood to be a seismic interaction concern with the damper. , VS-F-40A 1. The 1/8" gap between anchor bolt head and the base of the vibration isolator is only on one side of the bolt head. The bolt head was tightness checked with a wrench and found to be tight. VS-F-40B 1. The 1/8" gap between anchor bolt head and the base of the vibration isolator is only on one side of the bolt head. The bolt head I was tightness checkcd with a wrench and found to be tight.

2. The > l/4" gap was remeasured and found to be less than 1/4" on one side (dimension from bottom of bolt head to top of base for [

vibration isolator). Therefore, the intent of the caveat is judged to be met (i.e. gap <l/4"). VS-F-57A 1. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadioad. - 2 Access from floor level. Embedment OK for shell anchors. Spacing is greater than fans VS-F-57B & C and no free edges exist. Concrete condition / strength is the same as adjacent cubicles. No essential relays in the fan assembly and no visible gaps. VS-F-57B 1. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadioad. ; VS-F-57C 1. Anchorage installation adequate per GIP paragraph 4.4.1, pg. 4-36, based upon existence of deadioad. WR-P-I A 1. Overhead light fixtures on flexible support. Falling lights / parts unlikely and no soft targets exist.

2. Pump column support submerged in bay and is not accessible. Support is inspected by the ISI program. ,

3. Conduit against motor housing judged to not have an adverse effect on the operation of the pump or the wires in the conduit.

WR-P-1B 1. Overhead light fixtures on flexible support. Falling lights / parts unlikely and no soft targets exist.

2. Pump column support submerged in bay and is not accessible. Support is inspected by the ISI program.

3. Conduit against motor housing judged to not have an adverse effect on the operation of the pump or the wires in the conduit.

SVDS Notes Table 5.2 Page 7

Table

                                                                              ' Notes for Screening Verification Data Sheets                                                                                                           ;

Eauipment ID No. Reason the Intent of the Caveat was met Without Meeting the Specific Wordina of the Caveat Rule I WR-P-lC 1. Overhead light fixtures on flexible support. Falling lights / pans unlikely and no soft targets exist. !

2. Pump column support submerged in bay and is not accessible. Support is inspected by the ISI program. ,

3. Conduit against motor housingjudged to not have an adverse effect on the operation of the pump or the wires in the conduit. j

)-

i t t f i L SVDS Notes Table 5.2 Page 8

4 I l a j i i i i i. 4 Table 5.3 i Equipment Outlier Description and Resolution Summary ( 23 pages) ) 4 i i 4 J i f Page 28

Ta i Mechanical and Electrical Equipment Outlier Description and Resolution Summary i Equipment ID Type Location Outlier Description Outlier Resolution l Status i ( 480VUS-1-8-N1 Anchorage SRVB El. 713 Broken bolt in shcIl anchor in front portion of Shell anchor replaced with Hilti Kwik-Bolt by ? MWR 019483. Performed analysis of as-found I I CLOSED cabinet (1 of 3). anchorage. i 480VUS-1-9-P Caveats (12) SRVB El. 713 Missing mounting screw on P2 Control DC Screw replaced by MWR 01%31. CLOSED switch. BAT-1 Caveats (3) SRVB El. 713 Battery exceeds the weight for the equipment Review DCP 673 for seismic analysis of batteries class. 600 lbs vs 450 lbs. and racks (2). Also locate seismic qualification of , battery (cells). BAT-2 Caveats (3) SRVB El. 713 Battery exceeds the weight foi the equipment Review DCP 673 for seismic analysis of batteries class. 600 lbs vs 4',0 the. and racks (2). Also locate seismic qualification of battery (cells). BAT-BKR-4 Interaction (5) SRVB El. 713 Overhead condoit support may impact top . Determine deflections for components end compare ; to actual. Trim conduit support if required. - 4 corner of cabinet. BAT-CHG-2 Anchorage (4) SRVB El. 713 Various anchors will not tighten. Repair concrete anchorage CLOSED Repaired on TER 9294 and MWR 38133. Funher analysis of existing anchorage required r Calc # 8700-DSC-6545. I BNCHBD Caveats (9) SRVB El. 735 Some board mounted devices have missing Re-install missing hardware - completed prior to CLOSED attachment hardware (Problem Report 1 10R restad. 024). Caveats (3) SRVB El. 735 Recorders FR-MS-478,488, & 498 mounted Review qualification test report for recorder l directly on top of bench board have different capacity. support conditioris than qualification test. i Interaction (4) SRVB El. 735 Suspended ceiling paned unrestrained. Add panel clips or tic-wraps to positively secure s ceiling sections. l DC-SWBD-1 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review seismic qualification documentation. , equipment class. Height 98" vs 90". Followed by analysis and/or testing. DC-SWBD-2 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review seismic qualification documentation. equipment class. Height 98" vs 90". Followed by analysis and/or testing. Outliers by EIN Table 5.3 Page I

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      - Equipment ID ..            ~M                         ja:g                                         @-

Status .

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gy ~ DC-SWBD-3.1 , Clwenes(1); g SRWBIIL 713? f, r'=hamat egggeds the dimensions foi tb5 >.

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ympyy . yg g, DC-SWBD-4 Cavents(1)' 4 . SRWBEl 7134 gn Oshiestenseedstheh ser thei V Resicwscissacquaie , -

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                                                                                            ,1                             ;                    pg a9
        ~EE-EG-1 J         ._

Anchorage W - DGBX Et,7351 64 Asuiker tot disip is uniqueten shmilst to cast $ Anchorage analysis required.for EDO.

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WW .g ' g{y Q? cmammansana'S2233-C-018 analyzed EDG anchorage a, , ' Osp ender pestiam erBDO ddd in gseeger dies f Land _9susulttents' W ' i

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EE-EG-2 Anchorage DGBX El. 735 " Anchor bolt design is unique but eunger to cost-; Aashenageausgelsseguised Apr EDGc in-place bolisi t> _7 Calculallen $2233 C SIS ~amelyzed EDG anchorage Gap under portion of EDG skid is smeter then l^ and Esmed k er be acceptable , '

                                                                                                                                                                                     '        ~

1/4". Only the ends of the EDG sidd arei - g; grouted. EE-P-I A Anchorage DGBX El. 735 Cracks in concrete pad require evaluation.' Per RC-30A AB the anchor embedment depth is 18"

CLOSED with a 7" sleeve.' The cracks in the concrete pad will not effect the adequacy of the cast-in place anchors. Caveats (1) DGBX El. 735 Pump motor is (1) hp, which is outside the The I hp pump weighs less than the 5 hp pump in CLOSED experience equipment class of motors Shp to experience equipment class. By engineering . 2300hp. judgment, the smaller pump is adequate for the applied seismic forces. EE-P-1B Anchorage DGBX El. 735 Cracks in concrete pad require evaluation. Per RC-30A &B the anchor embedment depth is 18" CLOSED with a 7" sleeve. The cracks in the concrete pad will ' not effect the adequacy of the cast-in place anchors. Caveats (1) DGBX El. 735 Pump motor is (1) hp, which is outside the The I hp pump weighs less than the 5 hp pump in CLOSED experience equipment class of motors %p to experience equipment class. By engineering 2300hp. judgment, the smaller pump is adequate for the applied seismic forces. i Outliers by EIN Table 5.3 Page 2

O O Table .,.3 O

                             . Mechanical and Electrical Equipment Outlier Description and Resolution Summary Eauipment ID Type                    Location                Outlier Description -                                  Outlier Resolution Status DC-SWBD-2    Anchorage (5)           SRVB El. 713            Anchorage does not meet GIP criteria due to              Perform additional analysis after verification of construction joint in floor near one row of              continuous rebar through the constructionjoint anchors.

DC-SWBD-3 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review seismic qualification documentation. equipment class. Height 98" vs 90". Followed by analysis and/or testing. DC-SWBD-4 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review seismic qualification documentation. equipment class. Height 98" vs 90" Followed by analysis and/or testing. EE-EG-I Anchorage DGBX El. 735 Anchor bolt design is unique but similar to cast- Anchorage analysis required for EDG. in-place bolts. Calculation 52233-C-018 analyzed EDG anchorage Gap under portion of EDG skid is greater than and found it to be acceptabic. 1/4". Only the ends of the EDG skid are grouted. EE-EG-2 Anchorage DGBX El. 735 Anchor bolt design is unique but similar to cast- Anchorage analysis required for EDG. in-place bolts. . Calculation 52233-C-018 analyzed EDG anchorage Gap under portion of EDG skid is greater than and found it to be acceptable. 1/4". Only the ends of the EDG skid are grouted. i EE-P-1 A Anchorage DGBX El. 735 Cracks in concrete pad require evaluation. Per RC-30A AB the anchor embedment depth is 18" CLOSED with a 7" siceve. The cracks in the concrete pad will not effect the adequacy of the cast-in place anchors. l Caveats (1) DGBX El. 735 Pump motor is (1) hp, which is outside the The I hp pump weighs less than the 5 hp pump in l CLOSED experience equipment class of motors Shp to experience equipment class. By engineering 2300hp. Judgment, the smaller pump is adequate for the applied seismic forces. l L EE-P-1B Anchorage DGBX El 735 Cracks in concrete pad require evaluation. Per RC-30A AB the anchor embedment depth is 18" CLOSED with a 7" sleeve. The cracks in the concrete pad will not effect the adequacy of the cast-in place anchors. , Caveats (1) DGBX El. 735 Pump motor is (1) hp, which is outside the The I hp pump weighs less than the 5 hp pump in

CLOSED experience equipment class of motors Shp to experience equipment class. By engineering 2300hp. judgment, the smaller pump is adequate for the applied seismic forces.

Outliers by EIN Table 5.3 Page 2

m py . ~ Tab J i Mechanical and Electrical Equipment Outlier Description and Resolution Summary Eauipment ID Tvoe Location Outlier Description Outlier Rewlution Status EE-P-IC Caveats (1) DGBX El. 735 Pump motor is (1) hp, which is outside the The I hp pump weighs less than the 5 hp pump in CLOSED experience equipment class of motors Shp to experience equipment class. By engineering 2300hp. judgment, the smaller pump is adequate for the applied seismic forces. EE-P-ID Caveats (1) DGBX El. 735 Pump motor is (1) hp, which is outside the The I hp pump weighs less than the 5 hp pump in CLOSED experience equipment class of motors Shp to experience equipment class. By engineering 2300hp. judgment, the smaller pump is adequate for the applied seismic forces. FCV-RC-455Cl Caveats (4) RCBX El. 767 Equipment mounted on 1/2" diameter copper Further analysis required. tube which is less than 1" diameter pipe. FCV-RC-455C2 Caveats (4) RCBX El. 767 Equipment mounted on 1/2" diameter copper ' Further analysis required. tube which is less than 1" diameter pipe. FCV-RC-455DI Caveats (4) RCBX El. 767 Equipment mounted on 1/2" diameter copper Further analysis required. tube which is less than 1" diameter pipe. FCV-RC-455D2 Caveats (4) RCBX El. 767 Equipment mounted on 1/2" diameter tube Further analysis required. which is less than l' diameter pipe. FE-CDL-I A Caveats (10) DGBX El. 735 Review of relays in panel not complete / lack of Complete review of relays in panel. Obtain documentation. documentation for panel and relays or perform qualification testing. FE-CDL-1B Caveats (10) DGBX El. 735 Review of relays in panel not complete / lack of Complete review of relays in panel. Obtain documentation.- documentation for panel and relays or perform qualification testing. FR-MS-478 Caveats SRVB El. 735 Actual support condition for strip chart recorder Further review of the mounting differences is mounted on top of the benchboard difTers from required. their tested configuration. FR-MS-488 Caveats SRVB El. 735 Actual support condition for strip chart recorder Further review of the moimting differences is mounted on top of the benchboard differs from required. their tested configuration. FR-MS-498 Caveats SRVB EL. 735 Actual support condition for strip chart recorder Further review of the mounting differences is mounted on top of the benchboard difTers from required. their tested configuration. Outliers by EIN Table 5.3 Page 3

O O Table ,.3 O Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution ' Status FT-CH-124 Anchorage SFGB El. 722 Transmitter is mounted to block wall with Anchorage analysis for support shows anchorage to , CLOSED expansion (shell) anchors. be acceptable (Calc. #52233-C-019). Required capacities for expansion anchors in concrete block walls were determined. , FT-CH-127 Anchorage SFGB El. 722 Transmitter is mounted to block wall with Anchorage analysis for support shows anchorage to CLOSED expansion (shell) anchors. be acceptable (Calc. #52233-C-019). r Required capacities for expansion anchors in concrete block walls were determined. FT-CH-130 Anchorage SFGB El. 722 Transmitter is mounted to block wall with Anchorage analysis for support shows anchorage to CLOSED expansion (shell) anchors. be acceptable (Calc. #52233-C-019). ; Required capacities for expansion anchors in ; concrete block walls were determined. l FW-P-3A Anchorage SFGB El. 735 Concrete pad requires evaluation. Further evaluation required. FW-P-3B Anchorage SFGB El. 735 Concrete pad requires evaluation. Further evaluation required.

HCV-CH-389 Caveats (4,5) RCBX El. 707 Caveat 4 - Limits valves to piping I" and larger. Locate existing qualification reports or create ,

This valve is three-way 3/4" AOV. qualification analysis. Caveat 5 - Figure B.7-1 restrictions preclude , this valve and the 3g static load yoke stresses are unknown. HCV-MS-104 Caveats (5) SFGB El. 752 Valve is outside of GIP Figure B.7-1 Perform 3G or weak-link check analysis on valve. ,

dimensions for centerline of pipe to top of vahe. Air supply to valve is not assured. Operator action required if no air available. INV-VITBUS-1 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review DCP 1531 seismic qualification and analysis t equipment class. Width 551/2" vs 40". ofinverter cabinet included in DCP 153 I i documentation. INV-VITBUS-2 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review DCP 1531 seismic qualification and analysis equipment class. Width 551/2" vs 40" ofimerter cabinet included in DCP 1531 documentation. 1 INV-VITBUS-4 Anchorage (5) SRVB El. 713 Anchorage does not meet GIP criteria due to Ferform additional analysis after verification of construction joint in floor near one row of continuous rebar through the construction joint. anchors. ; Outliers by EIN Table 5.3 Page 4

                                                     -.         .       .       -         . , . _ .      _ _ = _ . -                _ _ _ _ _ _ _ -            _ _ - _--

O O Table s.3

Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status FT-CH-124 Anchorage SFGB El. 722 Transmitter is moimted to block wall with Anchorage analysis for support shows anchorage to l CLOSED expansion (shell) anchors. be @ (Calc. #52233-C-019).'

_ Required capacities for expansion anchors in l concrete block walls were determined.

! FT-CH-127 Anchorage SFGB El. 722 Transmitter is mounted to block wall with Anchorage analysis for support shows anchorage to

;                            CLOSED                                            expansion (shell) anchors.                         be acceptable (Calc. #52233-C-019).

Required capacities for expansion anchors in concrete block walls were determined. . FT-CH-130 Anchorage SFGB El. 722 Transmitter is mounted to block wall with Anchorage analysis for support shows anchorage to - CLOSED expansion (shell) anchors. be acceptable (Calc. #52233-C-019). Required capacitics for expansion anchors in concrete block walls were determined. i FW-P-3A Anchorage SFG3 El. 735 Concrete pad requires evaluation. Further evaluation required. l FW-P-3B - Anchorage SFGB El. 735 Concrete pad requires evaluation. Further evaluation required. l HCV-CH-389 Caveats (4,5) RCBX El. 707 Caveat 4 - Limits valves to piping 1" and larger. Locate existing qualification reports or create This valve is three-way 3/4" AOV. qualification analysis. Caveat 5 - Figure B.7-1 restrictions preclude this valve and the 3g static load yoke stresses are unknown. HCV-MS-104 Caveats (5) SFGB El. 752 Valve is outside of GIP Figure B.7-1 Perform 3G or weak-link check analysis on valve. dimensions for centerline of pipe to top of valve. Air supply to valve is not assured. Operator action required if no air available. INV-VITBUS-1 Caveats (1) SRVB El. 713 Cabinet exceeds the dimensions for the Review DCP 1531 seismic qualification and analysis equipment class. Width 551/2" vs 40".' ofinverter cabinet included in DCP 1531 documentation. INV-VITBUS-2 Caveats (1) SRVB El. 713 Cabinet exceeds the (iimensions for the - Review DCP 1531 seisnde qualification and ans'ysis equipment class. Width 551/2" vs 40". ofinverter cabinet included in DCP 1531 documentation. j INV-VITBUS-4 Anchorage (5) SRVB El. 713 Anchorage does not meet GIP criteria due to Perform additional analysis after verifk:ation of constructionjoint in floor near one row of continuous rebar through the constructionjoint. enchors. l Outliers by EIN Table 5.3 Page 4

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                                                                            - Tab Mechanical and Electrical Equipment Outlier Description and Resolution Summaty Equipment ID Type                 Location                Outlier Description                                Outlier Resolution                                           ,

Status LCV-CH-460A Interaction (1) RCBX El. 718 15/8" clearance between valve and concrete Further analysis is required to check deflection of wall. valve. LCV-CH-460B Interaction (1) RCBX El. 718 15/8" clearance between valve and concrete Further analysis is required to check deflection of wall. valve. LR-QS-100 Caveats SRVB El.735 Cantilevered strip chart recorder lacks rear Provide rear support as detailed by the vendor's support required by the vendors seismic requirements or replace recorder with a type not ; qualificatioit. Problem Report No. 1-95-605 requiring rear support. LT-FW-494 Anchorage (2) RCBX El. 718 Anchorage not covered by GIP. The base of the Performed calculation for the connection to i CLOSED instrument rack is bolted to the steel beams of structural steci (Calc #52233-C-020). platform. ; LT-QS-100A Interaction (1,4) YARD El. 735 Scaffolding too close to equipment. Remove scaffolding. LT-QS-100B Interaction (1,4) YARD El. 735 ScalTolding too close to equipment. Remove scaffolding. j LT-QS-100C Interaction (1,4) YARD El. 735 Scaffolding too close to equipment. Remove scaffolding. LT-QS-100D Interaction (1,4) YARD El. 735 Wooden structure over transmitter could Evaluate or replace wood st ncture. Evaluate. Caveats (5) collapse. Natural frequency not evaluated. natural f%wwy. LT-RC-459 Caveats (2) RCBX El. 718 Rack base is bolted to structural steel. This ' Adequacy of anchorage determined by analysis configuration is not covered in the GIP. I CLOSED (Calc #52233-C-020). LT-RC-460 Caveats (2) RCBX El. 718 Rack base is bolted to structural steel. This Adequacy of anchorage determined by analysis ; l configuration is not covered in the GIP. CLOSED (Calc #52233-C-020). ,

LT-RC-461 Caveats (2) RCBX El. 718 Rack base is bolted to structural steel. This Adequacy of anchorage determined by analysis !

CLOSED configuration is not covered in the GIP. (Calc #52233-C-020). MCC-1-E5 Caveats (12) W C VAULT El. 735 Cubicles AR and AD have contactor mounting Replaced broken screws per MWR 019711. ! CLOSED screws with missing heads. _ MCC-1-E7 Anchorage DGBX El. 735 Embedded channel & welds not as specified on Support top of MCC to prevent overturning. CLOSED design drawing, therefore insufficient support Support installed per TER 9344 & MWR 38903. provided for MCC. Prob Rpt I-95-44 ; MCC-1-E9 Interaction SRVB El. 713 Raceway brace could impact top rear corner of Renxwe raceway brace where impact will occur. j MCC. Clearanceis 1/4" l MOV-CH-115C Caveats (5,6) AXLB El. 722 Support attached to yoke. Yoke subject to Further piping analysis is required to investigate l piping loads. Weak link analysis checks yoke rennwal of the seismic restraint on the valve. as ifit was not braced. Review 8700-DMC-2957 and SCE-047-2. t i i Outliers by EIN Tabic 5.3 Page 5 [ t k 1

                  . , .                s...               -     r   , . - . - . . - . - - - _ . , , ,       ,                                  - - . - . .   -

g J Tabk~.3 Mechanical Equipment ID Type as ifit was not braced. MOV-CH-350 Caveats (6) Actuator is restrained piping is supported Interaction (1) AXLB El. 722 MOV-CH-378 Caveats (5) check is not completed. MOV-CH-381 Caveats (5) check is not completed. Interaction (4) SFGB El. 722 MOV-FW-160 Caveats CLOSED power supply to the would be required to l MOV-MS-105 Caveats (5) I MOV-RC-537 Interaction (1) ! PCC-FE-IA Caveats (10) Outliers by EIN Table 5.3 Page 6 l and Electrical Equipment Outlier Description and Resolution Summary _ Location Outlier Description - Outlier Resolution Status MOV-CH-115E Caveats (5,6) AXLB El. 722 Support attached to yoke. Yoke subject to Further piping analysis is required to investigate piping loads.~ Weak link analysis checks yoke removal of the seismic restraint on the valve. Review 8700-DMC-2957 and SCE-047-2. AXLB El.-722 Actuator and yoke are braced ir44ntly. Further analysis required of the seismic restraint. to the concrete floor and Review of weak link and pipe stress calculation. off the stmetural steel. Various clearance violations. Further analysis is required. RCBX El. 718 Centerline pipe to top of operator of Figure B.8- Based on engineering review of weak link analysis CLOSED 1 restrictions preclude this valve and the 3g the valve is adequate for lg seismic plus operating - loads. SFGB El. 722 Centerline pipe to top of operator of Figure B.8- Based on engineering review of weak link analysis CLOSED 1 restrictions preclude this valve and the 3g the valve is adequate for Ig seismic plus operating - loads. 3 1/4" clearance between MOV and adjacent Based on engineering review of pipe stress CLOSED TV-CH-204. calculations the MOV will not interact with the adjacent valve. TRBB El. 693 Valve is a backup isolation valve requiring relay The valve is a backup isolation valve. Several check - review. The valve is a non-safety related valves exist between the valve and the primary component located in the turbine building. The isolation valve. Check valves are rugged devices. valve is non-safety and MOV-FW-160 is toally redundant since the primary cannot be assured. isolation valve and all the intervening check valves c fail along with it. SFGB El. 735 Existing vendor calculation checks yoke to "G" Further review and possible analysis required to values that are less than those found in the pipe determine yoke acceptability. stress calculation. RCBX El. 767 Motor operator is 1/2" clear of copper air Determine component deflection for comparison to f tubing. 1/2" actual. DGBX El. 735 Review of relays in panel not complete / lack of Complete review of relays in panel. Obtain documentation for panel. documentation for panel and relays or perform qualification testing. - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ -

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Tabc 3 Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier u Resolution Status PCC-FE-1B Caveats (10) DGBX El. 735 Review of relays in panel not complete / lack of Complete review of relays in panel. Obtain documentation for panel. documentation for panel and relays or perform qualification testing. PCV-IA-108 Caveats (4) RCBX El. 767 Valve is mounted on a 3/4" threaded pipe. Further analysis required PCV-IA-109 Caveats (4) RCBX El. 767 Valve is mounted on a 3/4" threaded pipe. Further analysis required PCV-MS-101 A Other SFGB El. 752 Air supply to operate valve is not as3nred. Operator action to operate valve. PCV-MS-101B Other SFGB El. 752 Air supply to operate valve is not assured. Operator action to operate valve PCV-MS-101C Other SFGB El. 752 Air supply to operate valve is not assured. Operator action to operate valve. PCV-RC-455C Caveat (5) RCBX El. 767 Valve does not comply with dimension Perform 3G or weak-link check analysis on vahe. requirements of GIP Figure B.7-1. PCV-RC-455D Caveats (5) RCBX El. 767 Valve does not comply with dimension Perform 3G or weak-link check analysis on vahe. requirements of GIP Figure B.7-1. PCV-RC-456 Caveats (5) RCBX El. 767 Vahe does not comply with dimension Perform 3G or weak-link check analysis en vah c. requirements of GIP Figure B.7-1. PNL-AC-El Caveats (1) SRVB El. 713 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Height 50" vs 40" and Depth 16" vs 12" PNL-AC-E2 Caveats (1) SRVB El. 713 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Height 50" vs 40" and Depth 16" vs 12". PNL-AC-E3 Caveats (1) SRVB El. 713 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Height 50" vs 40" and Depth 16" vs 12". PNL-AC-E4 Caveats (1) SRVB El. 713 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Height 50" vs 40" and Depth 16" vs 12" PNL-AMSAC Caveats (2) SRVB El. 713 Panel contains programmable controllers. Determine effect of controllers on circuit (s). Determine whether controllers have been seismically qualified. PNL-BLDG-SER-A Anchorage SRVB El. 735 Gap under cabinet varies 3/16" to 3/4". Shims Anchorage calulation (#52233-C-025) by EQE exist around anchor locations. shows the anchorage to be acceptable.

Interaction SRVB El. 735 Suspended ceiling panels lack restraint and can Secure the ceiling panels so as to prevent their j impact cabinet. falling down. ._

t PNL-BLDG-SER-B Anchorage SRVB El. 735 Gap under cabinet varies 3/16" to 3/4". Shims Anchorage calulation (#52233-C-025) by EQE exist around anchor locations, shows the anchorage to be acceptable. l Outliers by EIN Table 5.3 Page 7 I

Table s.3 Mechanical and Electrical Equipment Outlier Description and Resolution Summary Eauipment ID Type Location Outlier Description Outlier Resolution Status PNL-BLDG-SER-B Interaction SRVB El. 735 Suspended ceiling panels lack restraint and can Secure the ceiling panels so as to prevent their impact cabinet. falling down. PNL-PR-HTR-A Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review seismic qualification documentation.- class Height 64" vs 40" and width 441/2" vs Compare seismic demand to SQUG database levels. 40". PNL-PR-HTR-B Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Height 641/4" vs 40" and width 44" vs Compare seismic demand to SQUG database levels. 40". PNL-PR-HTR-D Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review scismic qualification documentation. class. Height 64" vs 40" and width 441/2" vs Compare seismic demand to SQUG database levels. 40". 4 PNL-PR-HTR-E Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. cla s. licight 641/4" vs 40" and width 44" vs Compare seismic demand to SQUG database levels. 40". PNL-REL-21 Anchorage (6) SRVB El 713 Depressed section of floor (3" deep) beneath one Fill area beneath cabinet or shim under cabinet corner of cabinet. frame. PNL-REL-22 Anchorage (6) SRVB El. 713 Depressed section of floor (3" deep) beneath one Fill area beneath cabinet or shim under cabinet

corner of cabinet. frame.

PNL-SI-02 Caveats (7) SFGB El. 722 Anchorage analysis not completed for rack on Complete anchorage analysis for the rack. which the panelis mounted. PNL-SI-06 Caveats (7) SFGB El. 722 Anchorage analysis not completed for rack on Complete anchorage analysis for the rack, which the panelis mounted. PNL-VITBUS-1 Caveats (1) SRVB El. 735 Panel exceeds the dimensians for the equipment Review scismic qualification documentation. class. Length 72" vs 40". PNL-VITBUS-2 Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Length 72" vs 40". PNL-VITBUS-3 Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review seismic qualification documentation.

class. Length 72" vs 40".

PNL-VITBUS-4 Caveats (1) SRVB El. 735 Panel exceeds the dimensions for the equipment Review seismic qualification documentation. class. Length 72" vs 40". Outliers by EIN Table 5.3 Page 8 i 1

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l O O Table .,.3 O Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status FT-RC-402 Anchorage RCBX El. 717 Anchorage not covered by GIP. The base of the Performed calculation for the connection to CLOSED instmment rack is bolted to the steel beams of structural steel (Calc #52233-C-020). platform. QS-RACK-2 Caveat (6) YARD El. 735 Construction in area prevents complete access Final review to be donc during walk-down for to attached lines. acceptance of DCP-2163. QS-RACK-3 Interaction (4) YARD El. 735 Wood roof on adjacent utaiher shelter could Install a seismic restraint to the roof. fall on instrument lines. (Ref. EM 107301)

 , RK-AUX-RELA     Cawats (5,11)        SRVB El. 713           Tie plates at top of cabinet which connect       Install tie plates between top of panel and RK-CLOSED                                      adjacent panel are absent.                       REAC-TEST-A.

Missing bolts that connect cabinet to base Replaced missing 3/8" bolts per MWR 019461. channel. Relay D4 is missing mounting screw. Replaced missing screw by MWR-019461. RK-AUX-RELB Caveats (5,11; SRVB El. 713 Tie plates a.i top of cabinet which connect Install tic plates betuten top of panel and RK-CLOSED adjacent panel are absent. REAC-TEST-B. Relay 36 is missing mounting screw in upper Replaced missing screw by MWR-019464. l len corner. ! RK-PRI-PROC-10 Caveats (11) SRVB El. 713 Mounting screw missing for TM-422-N, F, H3. Replaced missing screws per MWR 019469. CLOSED i RK-PRI-PROC-14 Caveats (11) SRVB El. 713 Mounting screw missing for TM-432-lit,112, Replaced missing screws per MWR 019471. CLOSED H3. RK-PRI-PROC-15 Anchorage SRVB El. 713 Panel base to base channel 3/8" bolts loose Tightened loose bolts and replaced missing bolt per CLOSED (3 total). MWR 019479. RK-PRI-PROC-17 Anchorage SRVB El. 713 Base channel connection bolt (1 of 4) to WF Replaced missing nut and washer for base channel CLOSED missing nut and washer. bolt. (MWR 019474) RK-PRI-PROC-25 Caveats (11) SRVB El. 713 Mounting screw missing on front panel for FC- Replaced missing screw per MWR 019472. CLOSED 498D. RK-PRI-PROC-26 Caveats (11) SRVB El. 713 Mounting screw missing for unmarked device Replaced missing screws per MWR 019473. CLOSED and two blank plates. Outliers by EIN Table 5.3 Page 9

Tabh . 3 Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status RK-RAD-MON-7 Caveats (3,5) SRVB El. 735 Two strip chart recorders are mounted in the Strip chart recorders will be resiewed separately for cabine. (RR-RM-700 and RR-RM-800).The rear scismic qualification and proper support.. of the recorders are not supported in the manner recommended by the vendor. l Interaction SRVB El. 735 Cabinet touches adjacent cabinet (RK-RAD- Attach adjacent cabincts together and either stiffen MON-1)in the midfe. At outside edges of the side panels or shim between cabinets to prewnt cabincts there is 3/8" clearance. Sheet metal interaction of the cabinet sides. sides bulge outward to touch. RK-VS-E567 Caveats (8) SRVB El. 713 Two rigid conduits attach to an adjacent panel Install flex conduits between the panels. (RK-VS-E8-12), differential panel movement MWR 046347/TER 984I written to perform the can cause a problem. work. Interaction (3,5) SRVB El. 713 Insufficient clearance to adjacent pipe support Modify pipe support to gain sufficient clearance. 5/8" copper tube on panel moves freely causing Add clamp / anchor to copper tube on panel face. stress on tubing joints internal to panel. TERs to be developed RK-VS-E8-12 Caveats (8) SRVB El. 713 Two rigid conduits attach to an adjacent panel Install flex conduits between the panels. (RK-VS-E567), differential panel movement MWR 046347/TER 9841 written to perform the can cause a problem. work. RV-EE-201 A Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical resiew required or perform tug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded. RV-EE-201B Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and vahc test on pipe connection during next outage. are threaded. RV-EE-201C Caveats (4,9) DGBX El. 735 Vahr is mounted on 1/2" diameter pipe. Further analytical review required or perform lug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded. RV-EE-202A Caveats (4,9) DGBX El. 735 Vahe is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and vahr test on pipe connection during next outage. are threaded. Outliers by EIN Table 5.3 Page 10

Tab .3 Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location - Outlier Description Outlier Resolution Status RV-EE-202B Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded RV-EE-202C Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perfor:n tug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded RV-EE-203A Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and valve test on pipe connection during next outage, are threaded RV-EE-203B Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug - Connections between tank and pipe and valve test on pipe connection during next outage. are threaded i RV-EE-203C Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and vahc test on pipe connection during next outage. are threaded RV-EE-204A Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded RV-EE-204B Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded. RV-EE-204C Caveats (4,9) DGBX El. 735 Valve is mounted on 1/2" diameter pipe. Further analytical review required or perform tug Connections between tank and pipe and valve test on pipe connection during next outage. are threaded RV-RC-551 A Caveats (1) RCBX El. 767 Valve is not in SQUG database Seismic qualification per Target Rock, VT1 #8700-CLOSED 06.039-0164 A. RV-RC-551B Caveats (1) RCBX El. 767 Valve is not in SQUG database. Seismic qualification per Target Rock, VT1 #8700 . CLOSED 06.039-0164A. RV-RC-551C Caveats (1) RCBX El. 767 Valve is not in SQUG database. Seismic qualification per Target Rock, VTi #8700-CLOSED 06.039-0164 A. Outliers by EIN Table 5.3 Page 11

O 1~ Mechanical and Electrical Equipment Outlier Description and Resolution Summary Fauipment ID Tvoe Location Outlier Description ~ Outlier Resolution Status Anchorage SRVB El. 713 Loose shell type expansion anchors (3 of 6). Replace anchors with Hilti Kwik bolts. SW-1-8NI CLOSED Anchors found to be improperly installed. Perform anchorage analysis for the cabinet. Problem Report 1-93-61 Anchorage analysis 8700-DSC-6550. Replaced anchor bolts per MWR 019484 & 01%$0. SW-1-9PI Anchorage SRVB El. 713 Shell anchors removed for inspection were Replac: 3 of 4 anchors with Hitti Kwik bolts. CLOSED found to be, improperly installed. Perform anchorage analysis for the cabinet. Problem Report 1-93-6l Anchorage analysis 8700-DSC-6550. Replaced anchor bolts per MWR 01%I6. TR-RC-410 Caveats SRVB El. 735 Cantilevered strip chart recorder lacks rear Provide rear support as detailed by the vs.d fs support required by the vendors scismic requirements or replace recorder with a type not qualification. Problem Report No. 1-95-605 requiring rear support Caveats SRVB El. 735 Cantilevered strip chart recorder lacks rear Provide rear support as detailed by the vs.dwrs TR-RC-413 ' support required by the vendors seismic requirements or replace recorder with a type not qualification. Problem Report No. 1-95-605 requiring rear support TRANS-I-8-Ni SRVB El. 713 Transformer coils are not top braced. Perform analysis to determine existing m.yroit Caveats (4) adequacy or add top support to transformer TRANS-1-8N SRVB El. 713 Transformer coils are not top braced. Perform analysis to determine existing support Caveats (4) adequacy or add top support to transformer TRANS-I-9-Pl SRVB El. 713 Transformer coils are not top braced. Perform analysis to determine existing m.pymi Caveats (4) adequacy or add top support to transformer TRANS-I-9P SRVB El. 713 Transformer coils are not top braced. Perform analysis to determine existing support Caveats (4) adequacy or add top support to transformer TRB-RC-410 InteNion RCBX El. 718 RTD's not walked down. A walkdown of the RTD's is planned during next refueling outage for interaction. TRB-RLE.3 Interaction RCBX El. 718 RTD's not walked down. A walkdown of the RTD's is planned during next refueling outage for interaction. TRB-RC-420 Interaction RCBX El. 718 RTD's not walked down. A walkdown of the RE's is planned during next refueling outage for interaction. TRB-RC-423 Interaction RCBX El. 718 RTD's not walked down. A walkdown of the RE's is planned during next refueling outage for interaction. Outliers by EIN Table 5.3 Page 12

Ta Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status TRB-RC-430 Interaction RCBX El. 718 RTD's not walked down. A walkdown of the RTD's is planned during next refueling outage for interaction. TRB-RC-433 Interaction RCBX El. 718 RTD's not walked down. A walkdown of the RTD's is planned during next refueling outage for interaction. TRF-SI-02 Caveats (11) SFGB El 722 Anchorage analysis not completed for rack that Complete anchorage analysis for the rack. the transformer is mounted. TRF-SI-06 Caveats (11) SFGB El 722 Anchorage analysis not completed for rack that Complete anchorage analysis for the rack. the transformer is mounted. TV-CH-200A Caveats (5,6,7) RCBX El. 718 Exceeds limits of Figures B.7-1 & B.7-2 Perform 3G yoke analysis. Operator and pipe are mounted to same wall 7' Review pipe stress analysis for effect ofirAgrAnt to one pipe support. operator support. TV-CH-200B Caveats (5, o,7) RCBX El. 718 Exceeds limits of Figures B.7-1 & B.7-2 Perform 3G yoke analysis. Operator and pipe are mounted to same wall 7' Review pipe stress analysis for effect of i.AgiAnt to one pipe support. operator support. TV-CH-200C Caveats (5,6,7) RCBX El. 718 Exceeds limits of Figures B.7-1 & B.7-2 Perform 3G yoke analysis. Operator and pipe are mounted to same wall 7' Review pipe stress analysis for effect ofirAyAnt to one pipe support. operator support TV-MS-101 A Caveats (1) SFGB El. 752 Power assisted check valve is not in the Review scismic qualification documentation or experience database. perform analysis. TV-MS-101B Caveats (1) SFGB El. 752 Power assisted check valve is not in the Review seismic qualification documentation or experience database. perform analysis. TV-MS-101C Caveats (1) SFGB El. 752 Power assisted check valve is not in the Review seismic qualification documentation or experience database. perform analysis. VERTBD Caveats (11) SRVB El. 735 Strip chart recorders 7R-RC-410 & 413 and Replace recorders with qualified devices. LR-QS-100 are not seismically qualified or mounted. Problem report 1-95-605. Cetats (9) SRVB El.735 Some devices lacked retention clips (Problem Replace clips - Completed prior to 10R startup. CLOSED Report 1-95-024). Other SRVB El. 735 Ceiling panels could fall and strike board. Add clips or tie-wrap to ceiling panels. VS-AC-1A Caveats SRVB El. 713 Anchorage ofinternal components could not be Further review and inspection required. verified (accessed) at time of inspection. Outliers by EIN Table 5.3 Page 13

Tabl 3 Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status VS-AC-1A Anchorage SRVB El. 713 Two hold down bolts were found to be missing. Hold down bolts to be installed by MWR. Interaction SRVB El. 713 Cooling water lines are hard piped into the Further engineering review is required. cooling coils. VS-AC-1B Caveats SRVB El. 713 Anchorage ofinternal components could not be Further review and inspection required. verified (accessed) at time of inspection. Interaction SRVB El. 713 Cooling water lines are hard piped into the Further engineering review is required. cooling coils. Anchorage SRVB El. 713 One of four shell type anchors improperly Calculation 52733-C-011 confirmed the anchorage installed. The anchor is ineffective. to be adequate with only 3 of 4 anchors. Subject anchor to be replaced. VS-AD-10 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic Capacity VS-AD-3 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-AD-4 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity. VS-AD-5 Ancinrage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic in-duct mounting. VS-AD-5 CapvilOn SRVP El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity. VS-AD-6 Anchorage SRVE El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets I Equipment Class Seismic Capacity I l Outliers by EIN Table 5.3 Page 14

Tab ' t Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution j Status t VS-AD-7 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's : Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-AD-8 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic Capacity VS-AD-9 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Eqaipment Class Seismic in-duct mounting. ; VS-AD-9 Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity Perform Engineering Analysis to Evaluate Damper's VS AFD-1 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience s Equipment Class Seismic in-duct mounting. i Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-AFD-10 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic in-duct mounting. > Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-AFD-11 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's - Equipment Class Seismic in-duct mounting. , Cap vs Dem SRVB El. 713 Damper is not in SQUG Eadhquake Experience Perform Engineering Analysis to Evaluate Dampets , Equipment Class Seismic Capacity VS-AFD-12 Anchorage SRVB El. 713 Damper is not in SQUG Ea'thquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic in-duct mounting. Perform Engineering Analysis to Evaluate Damper's ! Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Equipment Class Seismic Capacity ; l l VS-AFD-13 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's ! E=_siW Class Seismic in-duct mounting l r i I l Outliers by EIN Table 5.3 Page 15

--_-------_-----,m                 r    -                  -           +               -<mn -- . .m-< .-   e w-    - _ ---  ----_______.-----.___-----_--._..---,1.--_.w-              ..- . __.-

O , Tabl .3 O Mechanical and Electrical Equipment Outlier Description and Resolution Summary

   ~ Eauipment ID           Type             Location               Outlier Description                            Outlier Resolution Status VS-AFD-13               Cap vs Dem       SRVB El. 713           Damper is not in SQUG Earthquake Experience     Perform Engineering Analysis to Evaluate Dampets Equipment Class                                 Seismic Capacity VS-AFD-14               Anchorage        SRVB El. 713           Damper is not in SQUG Earthquake Experience     Perform Engineering Analysis to Evaluate Dampers Equipment Class                                 Seismic in-duct mounting.

Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-AFD-15 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity , VS-AFD-2 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evahmte Dampers Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic Capacity VS-AFD-3 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic Capacity VS-AFD-4 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers , Equipment Class Seismic Capacity VS-AFD-5 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class. Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class. Seismic Capacity. Interaction SRVB El. 713 Conduit support rod in contact with operator. Modiry rod and/or conduit to clear. Conduit in contact with damper drive rod. VS-AFD-6 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Expenence Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. i l l Outliers by EIN Table 5.3 Page 16 l

O 0

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i Mechanical and Electrical Equipment Outlier Description and Resolution Summary [ Eauipment ID Type Location Outlier Description Outlier Resolution ; Status ! VS-AFD-6 Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's , Equipment Class Seismic Capacity VS-AFD-7 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets , Equipment Class Seismic Capacity VS-AFD-8 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's ; Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-AFD-9 Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Scismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's ; Equipment Class Seismic Capacity ' VS-C-l Al Anchorage SRVB El. 713 Load path from C.G. to wall bracket not Attach cm,4 wnt to existing wall bracket by adding CLOSED adequate. connection bolts per *mR 9047 and MWR 036772 Calculation 8700-DSC-6534 VS-C-1B 1 Anchorage SRVB El 713 Load path from C.G. to wall bracket not Attach component to existing wall bracket by adding , CLOSED adequate. connection bolts per 7ER 9047 and MWR 034492 { Calculation 8700-DSC-6534 VS-D-16A Anchorage SRVB El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's [ Equipment Class Seismic in-duct mounting i Cap vs Dem SRVB El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's ! Equipment Class Seismic Capacity i VS-D-16B Anchorage SRVB El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets l Equipment Class Seismic in-duct mounting. l Cap vs Dem SRVB El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic Capacity VS-D-22-1 A Anchorage DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper Equipment Class. Anchorage not accessible at Seismic mounting. Obtam access to anchorage next ! time ofinspection. outage. Outliers by EIN Tabic 5.3 Page 17 l I , I

_ _ _ _ ~ - _ _ _ _ - _ . -- . _ - -_ .__. o , A o Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status VS-D-22-1 A Cap vs Dem DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Mounting. VS-D-22-1B Anchorage DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper Equipment Class. Anchorage not accessible at Seismic mounting. Obtain access to anchorage next ; time ofinspection. outage. Cap vs Dem DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity. VS-D-22-2A Anchorage DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic mounting. Cap vs Dem DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engince-ing Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-22-2B Anchorage DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic mounting. Cap vs Dem DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-D-22-2C Anchorage DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class. Missing anchor bolts Seismic mounting. MWR 04339 to replace bolts Cap vs Dem DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-D-22-2D Anchorage DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class. missing Anchor bolts. Seismic mounting. MWR 04339 to replace bolts Cap vs Dem DGBX El. 756 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic Capacity VS-D-4-12A Anchorage SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-D-4-12B Anchorage SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic in-duct mounting. Cap vs Dem SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity Outliers by EIN Table 5.3 Page 18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __. _~ __ _ -_ . . .._._ - .,-_._, __ . . _.._ _ __ _____________.._,.

Tab Mechanical and Electrical Equipment Outlier Description and Resolution Summary Eauipment ID Type Location Outlier Description Outlier Resolution Status VS-D4-15A Anchorage SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D4-15B Anchorage SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class Seismic in-duct mounting. VS-D4-15B Cap vs Dem SFGB El. 735 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D4-7A Anchorage AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets . Equipment Class Seismic in-duct mounting. Cap vs Dem AXLB El. 768 Damper is not in SQUG Earthquake Experience Puform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D4-7B Anchorage AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets l Equipment Class 'Scismic Capacity VS-D4-8A Anchorage AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class. Seismic in-duct mounting. Cap vs Dem AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampets Equipment Class. Adjacent Rod Hung Pipe May Seismic Capacity. Impact Damper. Analyze Pipe Deflection for Interaction with Damper. Interaction AXLB El. 768 Adjacent Rod Hung Pipe May Impact Damper. Analyze Pipe Deflection for Interaction with Damper. VS-D4-8B Anchorage AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class. Companion flange missing Seismic in<!uct mounting. MWR 039971 to replace bolts. missing bolts. Cap vs Dem AXLB El. 768 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class. Seismic Capacity Outliers by EIN Table 5.3 Page 19

v U Ta n Mechanical and Electrical Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolutiori Status VS-D-40-1 A Caveats (7) SRVB El. 713 Two rigid conduits - one attached to SOV and One conduit clip (for SOV) removed to allow Interaction (2) one attached to Limitorque motor. flexibility and bolting corrected per MWR 044843 Bolt missing from SOV mounting plate. Conduit clip to be removed from conduit for motor. ' VS-D-40-IF Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-40-lG Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engitreering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-40-lH Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-40-lK Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-40-lM Anchorage SRVB El. 713 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic in-duct mounting. Cap vs Dem SRVB El. 713 Damper is not in SQUG Earthquake Expc:ience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-57Al Anchorage INTS El. 725 Damper is not in SQUG Earthquake Experiace Perfor'n Engineering Analysis to Evaluate Damper Equipment Class Seismic mounting. Cap vs Dem INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-57A2 Anchorage INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper Equipment Class Seismic mounting. Cap vs Dem INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Fquipment Class Seismic Capacity Outliers by EIN Table 5.3 Page 20

o , a o Mechanical and Electrical Equipment Outlier Description and Resolution Sumanry Equipment ID Type - Location Outlier Description Outlier Resolution Status VS-D-57BI Anchorage INTS El. 725 Damper is not in SQUG Earthquake Experience Perfctm Engineering Analysis to Evaluate Damper Equipment Class Seismic mounting.' Cap vs Dem INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic Capacity VS-D-57B2 Anchorage INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic mounting.' VS-D-57B2 Cap vs Dem INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-D-57Cl Anchorage INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Damper's Equipment Class Seismic mounting Cap vs Dem INTS El. 725 Damper is not in SQUG Earthquake Experience. Perform Engineering Analysis to Evaluate Dampers Equipment Class - Scismic Capacity VS-D-57C2 Anchorage INTS El. 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic mounting. Cap vs Dem INTS El 725 Damper is not in SQUG Earthquake Experience Perform Engineering Analysis to Evaluate Dampers Equipment Class Seismic Capacity VS-E-14A Caveats (2,6,7) SRVB El. 713 Anchorage details are not accessible. Further field inspection required when equipment is taken out of semcc VS-E-14B Caveats (2,6,7) SRVB El. 713 Anchorage details are not accessible. Further field inspection required when equipment is taken out of semce VS-F-40A Caveats (1) SRVB El. 713 Fan exceeds the weights for the equipment class Anchorage evaluation by EQE documented by Calc. CLOSED - 1000 lbs vs 2650 lbs. 52233-C-009 shows anchorage to be OK. SSRAP Report does not limit fan weight. VS-F-40B Caveats (1) SRVB El. 713 Fan exceeds the weight for the equipment class Anchorage evaluation by EQE documented by Calc. CLOSED - 1000 lbs vs 2650 lbs. 52233-C-009 shows anchorage to be OK. SSRAP Report does not limit fan weight. VS-F-4A Caveats (1) AXLB El. 768 Fan exceeds the weight for the equipment class The fan was seismically qualified by analysis by the CLOSED - 1000 lbs vs 5000 lbs. vendor in 1972. Analysis located on reel BV-34 / frame 1497. SSRAP Report does not limit fan weight. Outliers by E;N Table 5.3 Page 21 i _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . . . - - ~ _ - , . . . - . - - - - .

4 p ' Tabi 3 f Mechanical and Electrical Equipment Outlier Description and Resolution Summary Eauipment ID Type Location Outlier Description Outlier Resolution Status , VS-F-4A Caveats (1) AXLB El. 768 Fan exceeds the pressure (12" H2 0.vs 15") for The fan was seismically qualified by analysis by the CLOSED the equipment class. vendor in 1972. Analysis located on reet BV-34 / frame 1497. Interaction AXLB El.768 An overhead unit heater and piping is supported The piping and heater are passive equipment on rod l CLOSED by rod hangers and its failure could cause water hangers which resist seismic acceleration due to i spray on the fans electric motor. damping via the rods. VS-F-4B Caveats (1) AXLB El. 768 Fan exceeds the weight for the equipment class The fan was seismically qualined by analysis by the l CLOSED - 1000 lbs vs 5000 lbs. vendor in 1972. Analysis located on reel BV-34 / frame 1497. SSRAP Report does not limit fan weight. j Caveats (1) AXLB El. 768 Fan exceeds the pressure (12" H2 O vs 15") for The fan was seismically qualified by analysis by the . ; vendor in 1972. Analysis located on rect BV-34 / t CLOSED the equipment class. frame 1497. Interaction AXLB El. 768 An overhead unit heater and piping is supported The piping and heater are passive equipment on rod _ CLOSED by rod hangers and its failure could cause water hangers which resist seismic acceleration due to spray on the fans electric motor. damping via the rods. VS-F-57A Cap vs Dem INTS El. 733 Building response spectrum not available for Develop IRS for fan seismic demand to compare to ; this elevation. 1.5 Bounding Spectrum. VS-F-57B Cap vs Dem INTS El. 733 Building response spectmm not available for Develop IRS for fan seismic demand to compare to this elevation. 1.5 Bounding Spectrum.- ' VS-F-57C Cap vs Dem INTS El. 733 Building response spectrum not available for Develop IRS for fan seismic demand to compare to this elevation. 1.5 Bounding Spectrum. WR-P-1 A Caveats (2) INTS El. 705 Overall shaR length exceeds length in database. Perform engineering review of existing pump .

                                                                                                                                                  ' qualification analysis and review ISI inspection data.                                                          j Cap vs Dem        INTS El. 705                        1RS 3% damping curves are above the                         Perform engineering review of existing pump Bounding Curves.                                            qualification analysis.                                        .

WR-P-1B Caveats (2) INTS El. 705 Overall shaft length exceeds length in database. Perform engineering review of existing pump , qualification analysis and review ISI inspection data. , i Outliers by EIN Table 5.3 Page 22 __.__._m -_____.__a__ ___

                                               -     s     =    ..+*...... . - - - . .          . , . -  -.m.w-~..,....%.e4   =r s .w..,+o.e  w + w , r - re rm,9..=7---meL  m-.   -- --- .  ++-_________.____m

TatiM.'3 Mechanical and Electrical Equipment Outlier Description and Resolution Summary Eauipment ID

Tvoe Location Outlier Description Outlier Resolutiori , Status ! WR-P-1 B Cap vs Dem INTS El. 705 IRS 3% damping curves are above the Perform engineering review of existing pump Bounding Curves. qualification analysis. WR-P-IC Caveats (2) INTS El. 705 Overall shaft length exceeds length in database. Perform engineering review of existing pump qualification analysis and review ISI inspection data. Cap vs Dem INTS El. 705 1RS 3% damping curves are atxwe the Perform engineering review of existing pump ; Bounding Curves. qualification analysis. Outliers by EIN Table 5.3 Page 23

  - - - - . . .-     .. .    -      . - . _ . - . - . .     . - .-._. - . ~ . . . - _ _ . - .

i 1 1 1 I i i i a i 4 .i e i 1 i Table 5.3.1.5 j Air-operated Valves - Alternatives to Air Supply 1I 2 ( 1 page) i i e 'O \ l Page 29 i

O O O Table 5.3.1.5 Air-operated Valves - Alternatives to Air Supply AIR FOR AIR TO VALVE EIN NSA SSE NSA TO REMAIN @ ALTERNATIVE RESOLUTION SSE7 SSE? FCV-CII-122 0"LU CLOSED YES YES NONE OPERATOR ACTION,* _ FCV-FW-103 A CLOSED OPEN YES YES NONE OPERATOR ACTION'* FCV-FW-103B CLOSED OPEN YES YES NONE OPERATOR ACTION ** _ HCV-MS-104 CLOSED OPEN YES * *

YES * *
IIAND-WIIEEL OPERATOR ACTION PCV-MS-101 A CLOSED OPEN YES* *
YES * *
IIAND-WIIEEL OPERATOR ACTION PCV-MS-101 B CLOSED OPEN YES* *
YES * *
HAND-WIIEEL OPERATOR ACTION PCV-MS-101C CLOSED OPEN YES* *
YES * *
IIAND-WHEEL OPERATOR ACTION PCV-RC-455C CLOSED OPEN YES YES ACCUMULATOR N/A PCV-RC-455D CLOSED OPEN YES YES ACCUMULATOR N/A

PCV-RC-456 CLOSED OPEN YES YES ACCUMULATOR N/A NOTES

See Section 4.1.1.3

 ** See Section 4.1.1.4
 **

Valve is throttling.

SSE = Safe Shutdown Equipment position NSA = Normal System Arrangement Page 30

l l q Section 6 ; V TANKS AND HEAT EXCHANGER REVIEW 1 6.1

SUMMARY

OF REVIEW The tanks and heat exchangers on the BVPS-1 SSEL were evaluated in accordance with Section II.7 of the GIP, except for the buried EDG fuel oil tanks and Air Accumulator Tanks GN-TK-1 A

     & IB. The buried tanks were reviewed using existing criteria and recent analysis appropriate to their physical environment. The accumulators were reviewed using SQUG criteria applied to a l     recent analysis performed for operability. Thirty-one (31) tanks and heat exchangers were

. reviewed. All tanks except one (1) were reviewed by DLC SCEs and reviewed by EQE j engineers; the one exception being the Seal Water Hx (CH-E-1), which EQE reviewed in total. 6.2

SUMMARY

OF OUTLIERS Table 6.2 summarizes the tank and heat exchanger outliers. Additional discussion follows: ' OS-TK-1 (Refueling Water Storage Tank) - The RWST is a 52' x 38' Dia., flat-bottom, cylindrical, stainless steel tank containing 2000 ppm borated water. The tank is on a slab at grade, 4 and was designed by Stone & Webster Engineering Corporation. It is encircled for approximately 2/3 ofits height by an 18" thick reinforced concrete shell. The shell is separated from the tank by foam and a small interstitial space. The tank was evaluated to determine that no interaction between the tank and shell occurs, but its stand-alone GIP evaluation determined that its base s overturning moment Demand exceeds Capacity. However, the tank's anchor chairs are embedded in the concrete shell, which was ignored for the GIP evaluation. Consideration of this fact should resolve the outlier issue. An interaction concern regarding Dmporary scaffolding will be resolved with its near-term removal (it is seismically evaluated and tied-back). WT-TK-10 (Demineralized Water) - This tank is a 30' X 30' Dia., flat-bottom, cylindrical, carbon steel tank containing demineralized water. The tank is on a slab at grade, and was designed by Stone & Webster Engineering Corporation. The outlier determination resulted from base overturning moment Demand exceeding Capacity. A more refmed analysis should resolve the outlier. CH-TK-1 A & IB (7700 ppm Boron) - These boric acid storage tanks are 12' Dia. X 10' high, curved-bottom, cylindrical, stainless steel tanks, supported on four (4) 52" high W8x31 columns. They are located at elevation 752 of the auxiliary building, and were furnished by Westinghouse Electric Corporation. The outlier determination resulted in-part from overstress in the leg to tank l attachment, or in the legs' anchorage - depending on column end-restraint assumptions. Additional analysis by EQE has shown the tanks to be seismically qualified. A remaining issue is interaction with several duct and conduit suppons. These will require tank deflection determinations to resolve. It appears that the interaction would do no more than affect the insulation layer on the tank, which is several inches thick. b o Page 31

_. _ .._._ _ .__ ._._ _. _. _ . ._ _ _ _ _ . _ _ _ _ _ _._ . ~ . _ GN-TK-1 A & IB (PORV Nitrogen Accumulators) - These accumulators were installed primarily for PORV operation for over pressure protection during refueling. They are then charged with nitrogen, but are open to the containment air system during operation, and are valved to provide air to the PORVs as necessary. The tanks are vertically mounted on the exterior of the crane wall in containment using tubular frames and four (4) wall plates each. Their outlier status resulted from inspection of the expansion anchors used to attach the plates to the wall - four (4) bolts were loose - one in cach bottom wall plate. Analysis show that the plates are in constant compression (no tension on bolts), and the remaining bolts have low lo:.5ng. The tanks were concluded to be seismically acceptable as-found. EE-E-1B (EDG Heat Exchanger) - This heat exchanger has cast iron end-bells, which violates Footnote 1 of GIP Table 7-6, regarding parameters for acceptance criteria. The loads on the end-bells were evaluated and found to result in stresses less than 20% of the material's tensile strength. The EE-E-1 A heat exchanger has previously had its end-bells changed to steel. EE-TK-3A/B/C/D/E/F and 4A/B/C/D/E/F - These EDG air start tanks are supported on steel frames. Concrete expansion anchors at the base of the support legs attach base plates to the floor. l The anchors are spaced too near one another to assign full GIP capacities to them, resulting in a calculated overstress. However, it is believed that a refined analysis of the support / plate system will resolve the outlier. , CC-E-1 A/B/C - These heat exchangers have nelson stud spacing violations. The anchorage is more than adequate, and additional analysis is expected to resolve the outlier. O I: O . Page 32

i i i 4

O l

i , i l i l l 1 l 4 i ? : l ! Table 6.2 1

Tank and Heat Exchanger Outlier Description and Resolution Summary 1

( 3 Pages) i

O I

1 1 4 i j i

1 4 O Page 33

O O Tabiu.2 O Tank and Heat Exchanger Equipment Outlier Description and Resolution Summary Equipment ID Type Location ' Outlier Description Outlier Resolution . Status CC-E-1 A Anchorage AXLB El. 735 Headed studs (CIP anchor) fail GIP anchor More detailed analysis required.- criteria CC-E-1B Anchorage AXLB El. 735 Headed studs (CIP anchor) fail GIP anchor More detailed analysis required. criteria CC-E-IC Anchorage AXLB EL 735 Headed studs (CIP anchor) fail GIP anchor More detailed analysis required. criteria CH-TK-1A Other (Cap vs Dem) AXLB El. 752 Tank does not pass GIP analysis criteria. More detailed analysis performed by EQE (Calc. CLOSED #52233-C-03I) qualified the tank. Other (Interaction) AXLB El. 752 Ductwork stiffeners 1/4" from insulation. Analysis of tank and support interaction to Conduit support approx.1" clear. determine deflections and possible interaction. Abandoned vertical strut near tank. l Strut touching tank on neith side. CH-TK-1B - Other (Cap vs Dem AXLB El. 752 Tank does not pass GIP analysis criteria. More detailed analysis gifmi.G by EQE (Calc. CLOSED #52233-C-031) qualified the tank. , Other (Interaction) AXLB El. 752 Possible interaction with unistrut ductwork Analysis of tank and support interaction to support (s). determine deflections and possible interaction. EE-E-1B Caveats DGBX El. 735 Heat exchanger has cast iron end bell. Heat exchanger end bell evaluated for loading and CLOSED stresses to determine i./L.qug.y by calculation 8700-DMC-2978. Stresses determined to be low ! and the end bells adequate. EE-TK-1 A Other YARD El. 724 Tank is buried and not accessible for visual Existing seismic analysis and qualification CLOSED inspection. documentation (8700-DMC-2494,2795 & 27%) qualify the tank. EE-TK-1B Other YARD El. 724 Tank is buried arid not accessibic for visual Existing seismic analysis and qualification CLOSED inspection. documentation (8700-DMC-2494,2795 & 27%) qualify the tank. EE-TK-2A Interaction DGBX El. 735 Cover for emergency light batteries is missing Replace missing screw on cover. a restraint screw. Cover could fall and impact j level switches on the tank. EE-TK-3A Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. I i l Tank & Heat Exchanger Outliers Table 6.2 Page 1

O O Tabic o.2 O Tank and Heat Exchanger Equipment Outlier Description and Resolution Summary Equipment ID Type Location Outlier Description Outlier Resolution Status EE-TK-3B Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-3C Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evahiation required. criteria. EE-TK-3D Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-3E Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-3F Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-4A Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-4B Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-4C Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-4D Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-4E Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. EE-TK-4F Anchorage DGBX El. 735 Floor anchor bolts do not meet GIP acceptance Further engineering evaluation required. criteria. GN-TK-I A Anchorage RCBX El. 767 Two concrete anchors didn't pass SQUG hand Check and repair of anchors as required performed CLOSED tightness test performed for walkdown. by MWR 038887. Problem Report 1-95-045 Performed engineering analysis of as found condition for operability. Comparison of analysis of record (8700-DSC-0133-1) to SQUG anchorage criteria found anchorage acceptable.. Tank & Heat Exchanger Outliers Table 6.2 Page 2

p - 7- - G s Tab c o.2 G Tank and Heat Exchanger Equipment Outlier Description and Resolution Summary Equioment ID T_ype Location Outlier Description Outlier Resolution , Status GN-TK-1B Anchorage RCBX El. 767 Two concrete anchors didn't pass SQUG hand Check and repair of anchers as required performed CLOSED tightness test performed for walkdown. by MWR 038888. Problem Report 1-95-045 Performed engineering analysis of as found > condition for operability. Comparison of analysis of record (8700-DSC-0133-1) to SQUG anchorage criteria found anchorage acceptabic. QS-TK-1 Anchorage YARD El. 735 Base overturning moment demand exceeds Further engineering evaluation required. capacity. Vertical anchorage plates do not meet GIP criteria. ' WT-TK-10 Anchorage YARD El. 735 Base overturning moment exceeds the Further engineering evaluation required. anchorage capacity for the tank per GIP criteria. i i t Tank & Heat Exchanger Outliers Table 6.2 Page 3

i Section 7 j CABLE AND CONDUIT RACEWAY REVIEW ! 7.1

SUMMARY

OF RACEWAY REVIEW t i j The reviews of cable tray and conduit systems at BVPS-1 were performed per the guidelines of i Section II.8 of the Generic Implementation Procedure (GIP). All safety-related cabletray & raceway was inspected as part of the A-46 review. Three (3) SRTs initially reviewed the reactor j containment's cable & conduit raceways. A single SRT comprising two (2) SCEs, one of whom j was a P.E., reviewed the remainder of the plant's raceway. For purposes of continuity, this same i- team reviewed the contamment raceways a second time. Complete records were kept of all plant ! area inspections.

The BVPS-1 raceway encompass most standard types and configurations. They range from
lightly loaded to substantially loaded. Trays are typically 30" ladder type (T. J. Cope) and are: supported in all of the SQUG-de6ned fashions -- single to multi-ti:r, stmt-hung, cantilever j bracket, frame, and floor-to-ceiling. Conduit vary in diameter up to 6", and are of both aluminum j (majority) and steel. All raceway was generally well-supported. Unistmt is a common structural j support, with ridge-face nuts used. Concrete inserts, welds to embedded steel, and expansion i anchors were all found as attachment means. No rigid boots were found. No cast iron inserts l were found and none are known to have been used at BVPS-1. Tug tests were used to check lightly loaded 6xtures. Tie-wraps were regularly checked and were found to be sound.

Prior to SQUG walkdowns, the Color-separation Resolution Program resulted in the inspection of j all safety-related conduit and raceway. Over 18,000 separate items were inspected and 4 catalogued. Identi6ed de6ciencies (eg., missing bolts, clearances) are being systematically corrected. 4 7.2 EVALUATION OF BOUNDING SAMPLES As part of the in-plant review, worst-case bounding samples of raceway supports were selected l for further analytical reviews. Bounding samples were selected by EQE to encompass the C diversity and extreme of the plant's existing raceway support systems. Thirteen (13) were subjected to GIP analysis by a team of EQE and Duquesne Light SCEs. All but one (1) analysis has produced satisfactory results (i.e., samples acceptable). 7.3

SUMMARY

OF OUTLIERS Seven (7) outliers were identified during the plant walk-downs and one (1) thru analysis. Table : 7.3 summarizes the nature of the outliers and their resolution. Maintenance Work Requests (MWRs) are being issued where indicated. O Page 34

1 l l l O Table 7.3 Cable & Conduit Raceway Outliers and Resolutions ( l page) O . l O Page 35

O O O Table 7.3 Cable & Conduit Raceway Outliers and Resolutions 1CL7150C2 AXLB. El. 722 Conduit bank of 11 conduits are attached to a Static analysis using "g" acceleration value based Inclusion Rules support which is not attached to a wall, on actual frequency of conduit span. An as-built of causing an overspan between adjacent the conduit bank to be fumished by drafting. supports 1CK91201 SRVB. El. 713. An overspan condition, possibly due to two Static analysis ofconduit. Inclusion Rules missing clamps, was identified on conduit Re-install supports (clamps) - MWR . ICK9120L-1" Tag number 28820 is in place to repair. These missing clamps result in a span between supports greater than the GIP guidelines allow. ICC9300E SRVB. El. 713. An overspan condition, possible due to a Re-install supports - MWR . Inclusion Rules missing clamp, was identified on conduit ICC9300E-1". The conduit is connected on both sides to equipment by flex conduit. (The conduit is restmg on several conduits which run perperwhcular to this run). N/A SRVB. El. 725. Rod hung piping is routed through this area. Perform static analysis of pipe / supports or formal Other seismic its collapse could potentially damage raceway. hazards review. performance concerns (Drain line, doesn't always flow full). As-builds to be provided later. RC-P-I A, IB, IC RCBX El. 738. Support has questionable anchorage at base Add attachment at the base of the support. Other seismic (Not attached) MWR performance concerns Cable Tray Assembly RCBX El 767-10 Floor-mounted cable tray failed SQUG check. STRUDL analysis 8700-DSC-6530 was to Reactor Head Rod performed which qualified the subject raceway. Drive Assembly Various YARD El. 735. A non-ferrous (wood) shed is built in this area Remove wood structure or analyze. Other seismic for weather protection and could collapse. performance concerns. l l Page 36 I u_______________. _ - - . . _ . . . . .

 . _ -  _  _    . . -           .               . _ - . --        _ _ _   . ~ _ _ . _ . - . _ . _                         . . ~

l l i Section 8 ; O PLAN FOR ADDRESSING UNRESOLVED OUTLIERS The resolution of USI A-46 outliers for BVPS-1 progressed in parallel with the inspection and assessment process. Consequently, numerous outliers have already been resolved by corrective maintenance action, review of existing qualification documentation and/or additional analysis. The outliers which remain unresolved will be prioritized according to their safety significance and scope. If any modifications are required for these outliers, it is planned to schedule them for implementation during one of the next three BVPS-1 refueling outages. 1 O l O Page 37 ,

i l 1 i

i. Section 9 SIGNIFICANT OR PROGRAMMATIC DEVIATIONS FROM THE GIP

! No significant or programmatic deviations from the GIP have been made in the BVPS-1 A-46 Program. 4 ie i i i t i 1 l l 1 1 1

O i 1 l l i l l l l O Page 38

O sec1te io THIRD-PARTY AUDITS As required by Section I.2.2.7 of the GIP, a third-party audit was performed by an individual who isr.: part of the Seismic Review Team. The third-party audit report is included in Appendix 10.1 of ( . , report. Earlier, a preliminary, informal review was also conducted. Due to personnel availability and DLC's submittal commitment, the third-party audit was conducted prior to completion of the program, and consequently includes issues that would have normally been resolved prior to a fmal audit. It is expected that a return visit by the auditor will confirm proper resolution of all issues prior to submittal of DLC's completion letter. Responses to both the preliminary review and third-party audit follow. 10.1 Mr. Ron Cushing's preliminary review observations and DLC responses: Control Room Ceiline was not soecifically addressed in the SEWS - Initial inspection of the ceiling indicated well-fitting sections with little apparent room for movement. Latter hands-on effort proved that most of the ceiling panels are difficult to raise out of their framing tees due to a lip on the tees. However, due to Mr. Cushing's comment and the fact that positive retention does not exist, the ceiling was made an interaction issue, and is addressed in this report. Uncomoleted SEWS - The SEWS are considered to be working documents in accordance with O GIP guidance. SEWS were signed and dated at the time of equipment inspection to record SCEs and time of walkdown. Checklist questions that cannot be answered, such as anchorage analysis which depend upon field-measured bolt and/or weld size and location, were left blank or marked '

    " unknown." Either was acceptable since they are equivalent in meaning, and either prevents the overall checklist question of seismic adequacy from being answered "yes." Upon reaching a final detemtination of a "yes" or "no" for a checklist question, the entry was initialed and dated. All       l SEWS will be complete prior to SVDS sign-off. The SVDS, which constitutes a conclusive, final and submitted record, to the contrary, was always to be complete prior to signature.                    i l

SEWS Capacity versus Demand not completed - This determination was to be made in the cufice l following determination of natural frequency and actual location of the SSEL component at which I the seismic demand level is derived. Mr. Cushing suggested that 1.5 Bounding Spectrum versus FRS be used since the 8 Hz and 40 ft. height limits do not apply. This criteria was applied as specified by the GIP, Section 4.2. I Damners as outliers - Mr. Cushing noted the number of Class 0 dampers and suggested that they be reviewed under new guidelines being developed by SQUG. DLC had participated in initiating this effort and chose this option as described elsewhere in this report. Rule-of-the-box (ROB) and use of SEWS for subcomr>onents - Mr. Cushing suggested that where SEWS exist for subcomponents that are found on ROB items, that they be used. DLC practice is that such concerns are included under the "any other concerns" consideration for the ROB item, Page 39

and since the SCEs are trained in the equipment class requirements applicable to certain subcomponents, no individual subcomponent SEWS are needed. Additionally, the GIP (3.3.3) specifically addresses ROB individual components as not requiring separate evaluation (since the experience base already includes them). 10.2 Mr. Hardy's audit observations and DLC's responses: l 10.2.1 Audit Item 5.2 Twelve SEWS were generated for these tanks - one (1) per tank - by two (2) SRTs. The SRTs each produced six (6) of the SEWS. One SRT identified friction as the only available means of l restraint, whereas, the second SRT noted the need to evaluate the tank' for longitudinal restraint. One (1) of the second SRT's SEWS (EE-TK-3B) did not contain this statement - apparently in error. The existence of eleven (11) SEWS that addressed lateral restraint, five (5) of which called for evaluation, would appear to offset the one SEWS lacking a note, and assures that further review would occur. The potential for lateral movement has since been evaluated as noted on the five (5) SEWS, and friction is, in fact, sufIicient to prevent movement. 10.2.2 Audit Item 5.3

                                                    .                            The Diesel Air-Start Compressor (EE-C-1 A) interaction was not thought to be a threat by the SRT at the time ofinitial walkdown. (See 10.2.3).
                                                    .                            The " grout pad" is actually the compressor's base frame partially filled with grout. Itis believed that the bolt in question is a structural, thru-bolt (steel-on-steel), which connects the pump to the upper flange of the support frame's channel member. The bolt's nut is on the underside of the support frame's flange, and therefore, embedded in grout used to fill a portion of the frame to increase mass and reduce vibration. The crack, therefore, has no effect on the bolt. The nature of this bolt was decided by the SRT in the field, but was not noted on the SEWS. Further review could identify no additional detail on the vendor's drawing. However, the compressor is clearly skid-mounted, and an expansion anchor used to make the compressor-to-base connection would be both unlikely and difficult to install. The thru-bolt assumption, therefore, remains in effect.

10.2.3 Audit Item 5.4 The diesel generator tank level indicator has an emergency light / battery above and nearby. The SRT discounted it as a threat. A return visit will be made to confirm the presence of the attachment screw and further assess the likelihood of interaction (distance, height, etc). Additionally, all such emergency lights in seismic areas will be inspected for installation of attachment hardware. O Page 40

10.2.4 Audit Item 5.5 O As noted in the audit comment, the cabinet's load path and attachment welds had been inspected by the SRT during a previous walkdown, and no problem existed. 10.2.5 Audit Item 5.6

   . Mr. Hardy apparently reviewed the fis1d sketch of the fan, which does not identify the anchorage type. The SEWS Hic sketch does call out 1/2" Phillips Red Heads (an expansion anchor). It was drawn in the office using the field sketch and the design drawing - the source of the anchor type information. Additional information on the anchors for the vibration isolators had been sent to EQE prior to the audit, and it appears in the EQE anchorage calculation.
   . The SEWS for VS-F-40A does note that " light fixtures have 16" clearance above the fan",         ,

which the SRT considered sufficient. l

   . The issue of excessive fan weight was considered based strictly on the GIP equipment class description and SQUG training. Both sources give weight limits - the GIP as typical, the training as a numerical limit. This is true for the equipment classes of fans, air handlers, and chillers. The fan is, therefore, considered an outlier. The outlier resolution will be based in-part upon the fact that the Senior Seismic Review and Advisory Panel (SSRAP) report does not specify a weight limit.

10.2.5 Audit Item 5.7 The crack referred to was not identified on the SEWS because it is not near the original concrete 1 anchors inspected during the SQUG walkdowns. The anchor involved was a 3/8" Hilti Kwik-bolt installed as part of supplemental anchorage required because all but one of the original anchors on that side failed the tightness check. The subject anchor was designed and installed to existing plant procedures since it was part of a corrective action. It was QC-inspected and tension-tested to 120% of the anticipated load, an indication that the crack is not detrimental. 10.2.6 Audit Item 5.9 ( l The determination of an Allis-Chalmers MCC (type involved) mati num seismic deflection was ! noted earlier in this report as having been established at 0.10". This fact was identified to the l SCEs early in the initial walkdowns. Distance to walls for interaction risk was judged l accordingly. It was also understood that this determination was enveloping and on file, and did not require repeating. One (1) exception was MCC-E9 where a raceway strut was involved, and l removal was the preferred resolution because both items can deflect. I l 1 Page 41

l l 10.2.7 Audit Item 5.10 Bars acting as spacers are now so noted on the SEWS for the two (2) Exide battery sets with this arrangement. 10.2.8 Audit Item 5.11 The Cavea #4 could have been a "No", since it asks if either coil top bracing or an evaluation exists. A top brace does not; the SRT evaluated the existing coil support frame to be adequate l based on judgment. .A formal analysis was nct performed, nor was one found in the records. ; Although the form and extent of evaluation required by the GIP and SSRAP is unclear, all four l transformers will be considered outliers. Further discussion can be found in Section 5.3, j

    " Summary of Outliers.".

Caveat #10 should have been identified as Yes or Unknown. All pads on this floor elevation are ; tied to the base mat using typical bent bar ties as shown on reinforced concrete drawings. This is i l well known to the SCEs who considered the pad to be sufficiently robust to be juiged adequate without the need for analysis. However, this determination should yield a Yt.s. not N/A; ) therefore, the transformer's support pads will again be reviewed. 10.2.9 Audit Item 5.12 O The EDG Cardox Fire Protection system has been added as an interaction concern It was already one of three (3) fire protection concerns under review as a generic BVPS-1 SQUG issue - l EDG, auxiliary feedwater pumps, and charcoal bed filters. The discussion of each can be found in the BVPS-1 A-46 Relay Evaluation Report. 10.2.10 Audit Item 5.13 Concrete Block Walls (CBWs) were reviewed extensively under IEB 80-11 and IN 87-67, with some modification to upgrade seismic walls that did not meet review criteria under IED 80-11. ; All IEB 80-11 results were submitted to the NRC, and the CBWs were subsequently (and selectively) inspected by the NRC during the 1992 BVPS-1 Structural Audit. The CBWs are : controlled for purposes ofinspection and modification. The walls mentioned by Mr. Hardy were fully analyzed and modified under IEB 80-11, " Masonry Wall Design, dated May 8,1980." In general, CBWs were not evaluated again for SQUG, but the I record review analyses for the subject walls will be reviewed again to resolve Mr. Hardy's concern j 10.2.11 Audit Item 5.14 The bad actor relays are discussed in the Relay Report. The basis for acceptance is the SQUG p Program EPRI GERS capacity data for the subject relay configured as BVPS-1 uses it. There are

 \    no data being used outside of t,he relay GERS database.

Page 42

                                           -         -           .__ ~     _. ___________

l

< l 10.3 General j Comments made by the auditors were very helpful, and were incorporated into the BVPS-1 i SQUG implementation wherever possible. Where confusion appeared to exist as to what the SEWS information conveyed, clarifying changes were made. 1 1 I l O , t l 1 i I I O 1

'                                                                             Page 43

3 W Section 11

O REFERENCES i

1. Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant ;

l Equipment, dated February 1992, copyright Seismic Qualification Utility Group (SQUG), Revision 2, corrected February 14,1992.

2. USNRC, " Supplement No. I to Generic Letter (GL) 87-02 that Transmits Supplemental Safety Evaluation Report No. 2 (SSER No. 2) on SQUG Generic Implementation Procedure, Revision 2, as corrected on February 14,1992 (GIP-2)," dated May 22,1992.

3. "USI A-46 Relay Evaluation Summary Report for Beaver Valley Power Station Unit No.1 (BVPS-1)," dated December,1995.

4. Duquesne Light Company letters to USNRC, dated September 22,1992, and February 19, 1993, committing to SQUG resolution ofUSI A-46.

5. USNRC letter dated November 20, 1992 accepting Duquesne Light the Company Commitment to SQUG of September 22,1992.

6. NUREG-1018, " Seismic Qualification of Equipment in Operating Plants - Status Report Unresolved Safety Issue A-46," U.S. Nuclear Regulatory Commission, September 1983.

Page 44 .

O APPENDIX 2.2 BVPS-1 Ground Response Spectra O O

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2. FINAL SVPS 1 RESPONSE SPECTRA (SWEC.1979).

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1 I !O 1 1 i i s APPENDIX 2.3 BVPS-1 Amplified Response Spectra (ARS/ IRS) O

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O O O SQUG Review INTAKE STRUCTURE (INTS) ELEV. 705 ' Horizontal SSE Envelope vs.1.5BS 1 10 100 77_. r g-- -- - r- 4

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O O O SQUG Review MAIN STEAM / CABLE VAULT (MSCV) ELEV. 753.5 Horizontal SSE Envelope vs.1.5BS 1 10 100 7 i' .

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O O O SQUG Review MAIN STEAM / CABLE VAULT (MSCV) EL. 768 Horizontal SSE Envelope vs.1.5BS 1 10 100

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O O O i SQUG Review REACTOR CONTAINMENT (RCBX) ELEV. 738 : Horizontal SSE Enveiope vs.1.5BS ; 1 . 10 100 l 3 .. ; 3

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SQUG Review EXTERIOR REACTOR CONTAINMENT LRCBX) EL.792. Horizontal Envelope vs.1.5BS (FRS are drawn to envelope broadened ARS? 1 10 100 _ . , 4 i i !

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4 I. i . i I O i 1 i j ? l l APPENDIX 3.2 Resumes for Seismic Capability Engineers O O .

i PAUL V. DAVIS EDUCATION: Associate in Science - Civil Engincedng Technology, Youngstown State University,1978 Bachelor in Science - Civil Engineering Technology, Youngstown State University,1988 : PROFESSIONAL HISTORY: l Duquesne Light Co., Senior Engineer,1990 - present Stone & Webster Engineering Corp., Senior Field Designer, 1979 - 1990 L. K. Comstock & Company, Inc., Field Engmeer, 1972 - 1976, 1978 - 1979 Kaiser Engineers, Inc., Junior Engineer,1978 PROFESSIONAL EXPERIENCE: Mr. Davis joined Duquesne Light Company in Jauary of 1990 as an Engineer in the General and Plant Engineering section. He is presently a Senior Engineer involved in structural and mechanical analyses regarding the continuous operation and upgrade ofBeaver Valley Nuclear Power Station's systems, components, and parts. He has been responsible for the detailed seismic analysis and qualification of structural, mechanical and electrical components, including anchorage and supporting structure evaluations. Toward the resolution of BV-1 A46 concerns, he has been O performing duties as a Seismic Capability Engineer. V Prior to joining Duquesne Light Company Mr. Davis came to the Beaver Valley Power Station in the employ of Stone & Webster Engineenng Corp. in September 1980 as a Senior Field Designer. The gist of his work was makmg installation modifications to duct and piping systems during the BV-2 construction phase. Upon completion of construction he underwent a transition into plant modifications and upgrades. From December of 1972 to his coming to Beaver Valley Power Station Mr. Davis worked as a Field Designer / Engineer at several nuclear power plants - Three , Mile Island 1 & 2, North Perry 1 & 2, Washington Public Power System No. 2, and North Anna 1 l

 & 2. During this time his tasks included construction and modifications of piping / duct systems and mechanical components and analysis of existing piping / duct systems and mechanical components. Throughout this time Mr. Davis gained considerable knowledge related to the installation details and modifications of Nuclear Power Plant components. Seismic considerations were a key factor in the determination of how these niodifications were to be made and also in the analysis of those modifications.

TRAINING: SQUG Generic Implementation Procedure, walkdown screening seismic evaluation training - August,1993. O

WILLIAM HWANG EDUCATION: B. S. - Civil Engineering - Taiwan Cheng Kung University,1960 M. S. - Applied Mechanics - Kansas State University,1%5. REGISTRATION: Registered Engineer-in-Training in Pa. Registered Professional Engineer in Pa. Registered Professional Land Surveyor in Pa. PROFESSIONAL HISTORY:

1. Duquesne Light Company, Pittsburgh, Pa. Nuclear Engineering Department Senior Engineer 1969 - Present.

2. Peter F. Loftus Corporation, Pittsburgh, Pa. Civil & Stmetural Engineering Department Stmetural Engineer 1965 - 1968.

PROFESSIONAL EXPERIENCE: O As senior engineer with Nuclear Engineering Department of Duquesne Light Company, has been responsible for the development of seismic qualification specifications of class IE safety-related electrical components, detailed seismic design of various category I structures and anchorage analysis for SQUG USI A-46 SSEL components. ; 1 Served as stmetural engmeer with Peter F. Loftus Corp., I was involved with the structural and i foundation design of electrical substation structures and transmission towers. Also performed the detail design of the generator support and oil storage facility of combustion turbine unit. TRAINING: SQUG Generic Implementation Procedure, walkdown screening seismic evaluation tra' ming - November,1992. EPRI Add-On seismic IPE traming - December,1992. CYGNA Energy Services Pipe Support Design Seminar - November,1983. Stmetural Dynamics - Februanj through May,1981. I O

l l l CARMEN V. MANCUSO O EDUCATION: B. S. - Civil Engineering - University of Pittsburgh 1979 REGISTRATION: Registered Professional Engineer, State ofPennsylvania PROFESSIONAL HISTORY: Duquesne Light Company, Nuclear Group, Shippingport, Pa., Senior Engineer,1982-present. Schneider Consulting Engineers, Bridgeville, Pa., Stress Analyst, 1979-1982 PROFESSIONAL EXPERIENCE: Mr. Mancuso currently serves as a Project Engineer / Project Manager for Design Change Modifications performed to the Beaver Valley Power Station. Beaver Valley Power Power Station is a two Unit Pressurized water reactor plant located in Shippingport, Pennsylvania. His duties include the management of construction and modification projects through the detailed design, procurement, and installation phases Included in these responsibilities is ensuring that site ! licensing requirements are complied with for individual projects. ) Mr. Mancuso has served as a design engineer and stress analyst for a variety of projects at the Beaver Valley Power Station, including design of new support systems as well as analyzing existing i 4-found conditions to determine system operability. Specific areas of responsibility includes: a) pipe stress analyr.is and pipe support analysis (considering normal loads, thermal loads and seismic loads), b) structural analysis of structural steel and concrete structures, c) Anchor bolt and base plate design for component supports (including seismic loads), e) development of seismic qualification requirements and review of seismic quali6 cation' reports for compliance with IEEE 344, " Seismic Qualification of Class lE Equipment for Nuclear Power Generating Stations", f) design of seismic conduit and raceway systems. TRAINING: Pipe Support Design Seminar, Cygna Engineering, Instructor Thomas Ward Fundamentals of Seismic Engineering, Vantage Training Services, Instructor Dr. Charles Farwell Piping Design, Analysis and Fabrication, The Center, Instructor Walter Sperko Pipe Support and Hanger Design. The Center, Instmetor Jacques L. Boulay PWR Specialty Training, Westinghouse Nuclear Training Services, Instructor Phil McHale. SQUG Generic Implementation Procedure, walkdown screening seismic evaluation traimng - August,1993. O V .

PATRICK G. PAUVLINCH EDUCATION: B. S. - Civil Engineering, Penn State University,1984 REGISTRATION: Registered Engineer-in-Training: Pennsylvania l PROFESSIONAL HISTORY: Duquesne Light Company - Beaver Valley Power Station, Shippingport, i Pennsylvania: Senior Engineer,1993 to Present ' l Engineer I,1990 to 1993 ! i Stone & Webster Engineering Corp. - Beaver Valley Power Station Shippingport, Pennsylvania: Engineer 1984 to 1990 PROFESSIONAL EXPERIENCE: ( Mr. Pauvlinch prese.!y serves as a Senior Engineer for the General and Plant Engineering Section of the Nuclear Engineering Department at Beaver Valley Power Station. His Responsibilit'es include interpretation and utilization of computer analysis (STRUDL, NUPIPE, Finite Element etc.) to solve complex plant system and component problems. He interprets and effectively uses industry codes and standards (ANSI, ASME, AWS, AISC, etc.) while adhering to plant licensing procedures (UFSAR, Tech. Specs.) and overali design basis. l Mr. Pauvlinch is actively involved in the walkdown and seismic qualification (per the General Implementation Procedure, GIP) of components on the Beaver Valley Powwer Station's Safe l Shutdown Equipment List for USAI A-46 Project completion. Mr. Pauvlinch performs detailed design analysis and verification on piping, piping supports, equipment, equipment supports, structural supports, and electrical equipment using various computer code (STRUDL, NUPIPE, Finite Element) and manual calculation methods. He is responsible for solving urgent day to day problems associated with the continued operability and reliability of the plant while dealing with long term goals set forth by management. TRAINING: SQUG Generic Implementation Procedure, walkdown screening seismic evaluation training - February,1993. EPRI Add-On seismic IPE training March,1993.

rm- GLENN S. RITZ b EDUCATION: 1986 - MS-IE, University of Pittsburgh 1970 - 1971 - Candidate for MS-CE, University of Pittsburgh 1969 - BS-CE, University of Pittsburgh 1965 - 1966 - Candidate for BS Mathematics, Alderson-Broaddus College REGISTRATION: Registered Professional Engineer, State of Pennsylvania, No. PE-024749-E PROFESSIONAL HISTORY: 1970 - Present; Employee of Duquesne Light Co., Pittsburgh, PA PROFESSIONAL EXPERIENCE: Mr. Ritz is currendy a Principal Engineer with the Nuclear Engineering Department, Corporate Nuclear Services Unit, Nuclear Group, at Beaver Valley Nuclear Power Station. He is the Project Manager for the Beaver Valley Unii No.1 USI A-46 Project. He concurrently acts as a civil / structural staff engineer, seismic engineer, and internal consultant to associate engineers. Duties include design and analysis of structural systems (e.g., buildings, equipment supports), specifying and evaluating seismic equipment qualification, and advising associate engineers on issues such as bolting, analytical techniques, and failure assessments. He has held this position since 1984, when he was reassigned from the former Engineering & Construction Division due to Corporate reorganization. Prior to 1984, Mr. Ritz worked in the former Structural Engineering Department, where he held the positions of Engineer, Project Engineer and Senior Project Engineer. His work assignments included review of Architect / Engineer design documents for both Units of the Beaver Valley Power Station. Additionally, he worked on civil / structural projects involving the Utility's fossil fuel generating stations, power transmission system, waste disposal / compliance issues, and , subsidiary steam heating system for the city of Pittsburgh. TRAINING: Severe Loading Symposium, Dr. John D. Stevenson, Case Western Reserve,1973. PWR Specialty Training, Westinghouse Nuclear Training Services. Structural Dynamics Lecture Series, February thru May,1981. Advanced Frame and Finite Element Analysis, Georgia Institute of Technology,1988. Seismic Seminar, WYLE Laboratories,1989. SQUG SSEL, Relay Review, IPEEE Add-on and Seismic Capability Engineer (walkdown) O training, September / October,1992. P

l l G. THOMAS WESTBROOK EDUCATION: B. S. Civil Engineering - West Virginia University,1979 Masters Program Studies - West Virginia University, 1979 - 1981 REGISTRATION: Professional Engineer, PA License Number PE-037526-E,1988 Engineer-in-Training, WV 1979 PROFESSIONAL HISTORY: Duquesne Light Co.; Senior Engineer 1990 - Present Engineer I, 1987 - 1990 Engineer II, 1981 - 1987 Triad Engineering, Field / Lab Technician / Draftsman / Analyst - Summers 1978,1979,1980 PROFESSIONAL EXPERIENCE: Mr. Westbrook currently serves as a Senior Engineer in the General and Plant Engineering Section of the Nuclear Engineering Department at Beaver Valley Power Station. Responsibilities include the preparation of specifications for seismic qualification of equipment / components, evaluation of seismic test reports for components, preparation of stmetural site design / installation standards and specifications, and analysis / design of anchorage for equipment and supports. Mr. Westbrook is the in-house specialist on concrete anchor bolts and protective coatings. Other responsibilities include design and analysis of structures, equipment, pipe supports, HVAC duct supports, conduit and cable tray supports, and coordination of field modifications. Mr. Westbrook successfully completed the SQUG Walkdown Screening and Seismic Valuation Training Course, Nov. 9 thru 13,1992 and the Seismic IPE Add-on Training Course, Nov. 30 thru Dec. 3,1992. He has been involved in the equipment walkdowns ofitems on the SSEL for Unit 1 of the Beaver Valley Power Station. Performed analysis and evaluations of equipment on the walkdown list. Also, developed resolution for deficiencies discovered during walkdowns. TRAINING: Structural Repair of Concrete and Masonry, ASCE 1989 GT-Strudl Course, Georgia Institute of Technology 1988 O Protective Coatings Course, KTA-TATOR, Inc 1983

I CYNA Energy Services Pipe Support Design Seminar,1983 PWR Specialty Training,1982. SQUG Generic Implementation Procedure, walkdown screening training, November 1992. 0 O l l l l l O

RICHARD D. AUGUSTINE i PROFESSIONAL HISTORY EQElnternational, Stratham, New Hampshire, Principal Engineer,1987-present Impell Corporation, New York, New York, Project Engineer,1986-1987 Cygna Energy Services. Boston, Massachusetts, Structural Engineer,1985-1986 Butler Service Group, Charlotte, North Carolina, Structural Engineer, 1984-1985 Pullman-Higgins, Seabrook, New Hampshire, Field Engineer,1983-1984 Butler Service Group, Braintree, Massachusetts, Design Engineer, 1981-1982 Bechtel Power Corporation, San Francisco, California, Design Engineer, 1980-1981 i PROFESSIONAL EXPERIENCE Since joining EQE, Mr. Augustine has been involved in various projects relating to the EQE seismic experience data base. In the field he has used the data base to seismically qualify electrical and mechanical equipment and various piping systems in nuclear power plants. Similar evaluation work has been j performed on nuclear-plant cranes. He has used his extensive knowledge of nuclear piping in conjunction j with data base experience to perform piping qualification tasks and develop performance criteria, in j addition he has been involved in organizing and updating the seismic experience data base. l l Mr. Augustine was assigned as USI A-46 Task Leader at Indian Point Unit 2. He has completed the SQUG !

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Seismic Capability Training required for USI A-46 evaluations. In addition to work at Indian Point, he has performed IPEEE/A-46 walkdowns as an SCE at the TMI, Savannah River, Oyster Creek, Calvert Cliffs 1 ' and 2, and Keonee facilities. His work has included seismic screening of equipment, tanks and heat exchangers; conduit and cable tray screening and analytical reviews; and outlier resolutions. Mr. Augustine has participated in various piping and equipment evaluation projects for DOE facilities including work at the Savannah River Plant and Princeton Plasma Physics Laboratory. At Savannah River, Mr. Augustine was a member of seismic review teams who reviewed relays, raceways, control panels, piping, and equipment in the K, L, and P reactors. At Princeton, he was project engineer for the seismic evaluation of Tritium handling systems. Other assignments have included acting as project lead for the seismic verification of the diesel air start system at the Ginna Nuclear Plant, cable tray verification at TMI Unit 1, seismic 11/1 interaction review at Browns Ferry Unit 2 and Salem Unit 1, equipment seismic verification at Surry and North Anna, and seismic verification of HVAC duct and isolation dampers at Oyster Creek. Mr. Augustine has also participated as a seismic capability engineer on seismic review teams for seismic verification of equipment l at several nuclear power plants. O resumenh/augustnl/Jan-95/ I

RICHARD D. AUGUSTINE PROFESSIONAL EXPERIENCE (Continued) Before joining EQE, Mr. Augustine was involved in the evaluation of anchorage for safety-related rotating equipment at the Comanche Peak Nuclear Station. Mr. Augustine has also panicipated in a number of conduit projects. At the Fitzpatrick Nuclear Station in upstate New York, he provided engineering ) solutions to conduit routing and support problems. At the Pilgrim Nuclear station he contributed to the ! design of a conduit suppon framework in the cable spreading room. , Also at Pilgrim, Mr. Augustine was involved in the seismic requalification of the main fuel pool hoist and i trolley, in another project at this facility, he panicipated in the design of a reinforced concrete shield-wall ! to be placed on the operating floor of the turbine building. .j At the Seabrook Nuclear Station, he was involved in reconciliation of ASME Class 1,2, and 3 piping and , pipe supports. This effort required determining from design change documents for each support the ; capacity of these components to withstand deadweight, thermal, seismic, and transient loads imposed by l the piping systems. j in a prior assignment at Seabrook, Mr. Augustine was responsible for overseeing the installation of piping and suppons in the diesel generator building. Work involved checking the layout and structural j configurations of piping and restraints, instructing staff on both drawing interpretation and procedural ' l requirements, and resolving interferences encountered during construction. He also supervised completion j of as-built drawings. ; At the Brunswick Steam Elec ric Plant, Mr. Augustine worked in the engineering support group during refueling and plant modification outages. He participated in the design of new pipe suppons and the i redesign of existing ones. Following design, he supervised installation of supports and resolved interference problems. Non-outage work consisted primarily of routing and supporting Class IE conduit. ; Mr. Augustine designed the supponing structure framework for the mainsteam, feedwater, and pressurizer piping systems at the McGuire Nuclear Station. The design included seismic analysis, field measurement and layout, and base plate analysis. ! I While with Bechtel, Mr. Augustine supervised the piping simplified stress analysis group for the Susquehanna Nuclear project. In this capacity he managed the stress review and new design of piping , systems and supports. He also performed seismic and gravity stress calculations. During this period, he ; also designed both large and small bore supports, including snubbers, struts, anchors, and springs. I EDUCATION COLORADO STATE UNIVERsim B.S. Civil Engineering,1979 REGISTRATIONS Civil Engineer: New Hampshire Structural Engineer: New Hampshire l I resumenhlaugustnl/Jan-95/ 2

i 1 JEAN-PAUL CONOSCENTE PROFESSIONAL HISTORY EQE International, San Francisco, California. Principal Engineer, January 1988 - present URS/Blume Engineers, San Francisco, Califomia, Lead Engineer,1987; Engineering Intem,1985 l Borie-SAE, Paris, France, Engineering Intem,1986 . j PROFESSIONAL EXPERIENCE ) v Mr. Conoscente has a wide range of practical and research experience in structural engineering, earthquake ! engineering, equipment qualification, lifeline analysis, and structural mechanics. ! As a principal engineer for EQE's Engineering Consultants division, Mr. Conoscente's structural l engineering experience includes the seismic and tomado analysis of major steel and concrete structures for ; industrial plants, including the analysis of the Oak Ridge National Laboratory High Flux isotope Reactor [ for seismic and extreme wind load; the evaluation of twin high-rise buildings in Oakland for seismically induced building pounding; the seismic fragility analysis of the N-Reactor Core at the Depamnent of l Energy (DOE) Hanford Facility. Mr. Conoscente also has extensive experience in developing design as well as probabilistic in structure : floor response spectra, including constructing building models and soil-structure models, and performing l O the SSI analysis. Past experience includes the development of design and probabilistic floor response spectra for various buildings at the Three Mile Island, North Anna, Surry, Brunswick, and Washington Power nuclear plants. Mr. Conoscente has conducted seismic fragility evaluations of several buildings at the Three Mile Island, Oyster Creek, and Washington Power facilities for resolution of the Individual Plant l Examination for External Events (IPEEE). l Mr. Conoscente also has significant equipment qualification experience. He was Project Manager in charge of the seismic qualification efforts of the Airbome Activity Confmement System (AACS) at the

Savannah River Site (SRS) reactors, using the Seismic Qualification Utility Group (SQUG) Generic ! Implemet. tion Procedure (GIP) methodology. At SRS, Mr. Conoscente also performed SQUG GIP evaluations of critical safety systems in support of the reactor restart program. Mr. Conoscente has i completed the SQUG certified walkdown screening and seismic evaluation training course. He also J participated as a seismic capability engineer for resolution of A 46 issues at the Three Mile Island Nuclear i Plant. Mr. Conoscente perfortned the seismic margins assessment walkdown of Comanche Peak Steam l Electric Station to address the Individual Plant Examination for External Events. He also conducted ; seismic fragility evaluations for structures ano equipment at the Hope Creek Nuclear Generating Station for resolution of the IPEEE. l Mr. Conoscente also participated in Risk Manegement and Prevention Program (RMPP) evaluations and l seismic studies for the TOSCO Chemical Plant in Martinez and the PGAE Power Plant in Pittsburg, Califomia. k p:\res-sfconsent5/ Mar 09-95 1

I JEAN PAUL CONOSCENTE . PROFESSIONAL EXPERIENCE (Continued) He also has extensive experience in the seismic risk assessment of lifeline facilities. He was Project Manager in charge of the resolution of safety issues related to the safe operation and shutdown of the Trans-Alaska pipeline facilities. Additional projects include a reliability study to assess the impact of an earthquake on the electrical distribution system of British Columbia, Canada; and the vulnerability evaluation of key substations for the City of Seattle, Washington. Mr. Conoscente is also an active

member of the French Association for Earthquake Engineering Lifelines Committee, which is currently rewriting the French Seismic Code Provisions for buried pipelines. Past research projects while at EQE include the United States Nuclear Regulatory Commission (USNRC) Structural Damping Research Program; and the development of a state-of-the-art computer code to analyze impacting structural systems. Mr. Conoscente developed seismic evaluation criteria for HVAC duct and electrical cable tray and conduit systems based on past seismic experience data. This method has been adopted by the Seismic Qualification Utility Group for the seismic evaluation of cable trays and conduit in older nuclear power plants. Mr. Conoscente also participated in earthquake reconnaissance studies following the 1988 Saguenay, Quebec, the 1989 Loma Prieta, and the 1994 Northridge earthquakes. At URS/Blume, Mr. Conoscente performed the seismic evaluation oflarge industrial steel-frame buildings, including models representing the beam-column connections by nonlinear elements. He also used 1 analytical models to develop state-of-the-art methods for the seismic evaluation of tanks for the Electric ; Power Research Institute (EPRI). Additional project experience inchie a EPRI generic study of the l importance of soil-structure interaction on the dynamic response of nuclear power plant structures based on l actual recordings. l /N j b As an engineering intern with Borie-SAE, Mr. Conoscente developed a computer program for the analysis of a prestressed concrete bridge during an incremental launching construction. As an engineering intem j with URS/Blume he prepared designs for the dredging of a creek and participated in the structural design 1 of the Portman Hotel in San Francisco. l EDUCATION UNIVERSITY OF CALIFORNIA, BERKELEY, California: M.S. Structural Engineering and Mechanics,1987 ECOLE SPECIALE DES TRAVAUX PUBLICS, Paris, France. Diplome d'Ingenieur des Travaux Publics,1986 REGISTRATIONS Professional Engineer: Califomia PROFESSIONAL AFFILIATIONS Structural Engineers Association of Northern California Earthquake Engineering Research Institute French Association for Earthquake Engineering O V p:\res-sf\ consents / Mar 09-95 2 .

1 JEAN-PAUL CONOSCENTE l PUBLICATIONS O V With J. Betbeder-Matibet, D. Amir-Mazaheri, et al. "The January 17, 1994 Northridge Earthquake." Reconnaissance repon from the French Association of Eanhquake Engineering, March 1994. With T. R. Roche, C. Abou-Jaoude, and J. R. Diser. " Comparison Between Analytical and Test Results for Transformer Base Details." ASME Pressure Vessels and Piping Conference, Denver, Colorado,1993.

     ~ Methods Used for the Treatment of Non-Proportionally Damped Structural Systems." NUREG/CR-6013, 1993.
     " Dynamic Analysis of impacting Structural Systems".            Tenth World Conference on Earthquake Engineering, Madrid, Spain, July 1992.

With A.P. Asfura. "A Simplified Analytical Method to Evaluate Pipe-to-Pipe Impact Loads". ASME Pressure Vessels and Piping Conference, New Orleans, Louisiana, June 1992. With J.J. Johnson, P.S. Hashimoto, O.R. Maslenikov. "USNRC Structural Damping Research Program". Presented at the 18th Water Reactor Safety Information Meeting, October 1990; and at the Third Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment, and Piping, Orlando, Florida, December 1990. With J.A. Lambright, M.P. Bohn, J.J. Johnson, et al. " Analysis of Core Damage Frequency Due to External Events at the DOE N-Reactor" Sandia Repon SAND 891147, Category UC-610, November 1990. With L.J. Bragagnolo, S.J. Eder. "A Proposed Methodology for the Seismic Design of HVAC Systems". /"~ s Presented at the ATC-29 Seminar and Workshop, October 1990. i With S. J. Eder. " Alternative Seismic Design Guidelines for Flexibly Supponed Distribution Systems." i Founh U.S. National Conference on Earthquake Engineering, Palm Springs, California, May 1990. 1 With S. J. Eder, B. N. Sumodobila, and S. P. Harris. " Seismic Fatigue Evaluation of Rod Hung Systems." Tenth Conference on Structural Mechanics in Reactor Technology, Anaheim, California, August 1989. With C. Scawthorn, K. Jacobs, H. W. Johnson, R. Augustine, and S. W. Swan. "He Saguenay, Quebec Eanhquake of November 25, 1988." Annual Earthquake Engineering Research Institute meeting, San Francisco, California, February 1989. With P. D. Smitfi and S. J. Eder. "SQUG Cable Tray and Conduit Evaluation Procedure." Second Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment, and Piping, Orlando, Florida, December 1988.

     " Structural Reliability of a Sheet Piling Wall." Berkeley, CA: University of California, May 1987.       ,

o . p:\res-sfconw..:$aiar09-95 3

RONALD W. CUSHING t n ~V PROFESSIONAL HISTORY EQE International, Inc., Irvine, California, Principal Engineer,1988-present Bechtel Western Power Corporation - Peach Bottom Atomic Power Station, Delta, Pennsylvania, Senior Startup Engineer, 1987-1988 Bechtel Construction, Inc. - Diablo Canyon Nuclear Power Plant, Avila Beach, Califomia, Field Engineer, 1987-1987 Bechtel Western Power Corporation - Palo Verde Nuclear Generating Station, Wintersburg, Arizona, Startup Engineer, 1981-1987 Bechtel Power Corporation - Startup Support Group, Norwalk, Califomia, Startup Engineer, 1981-1981 Allis-Chalmers Corporation - Compressor and Custom Pump Division, Irvine, Califamia, Field Engineer,1976-1981 PROFESSIONAL EXPERIENCE At EQE, Mr. Cushing is a principal engineer for EQE Engineering Consultants involved in the application of earthquake experience data for component seismic verification at nuclear power plants. Major duties include plant walkdowns and evaluation of seismic adequacy of mechanical and electrical equipment, piping, cable tray and HVAC systems. Specific attention is given to operability, II/1, spatial interaction, and anchorage concems. 1 A Mr. Cushing has investigated sites which have experienced major seismic activity for the SQUG f V earthquake experience database. He is a subject matter expert on the SQUG walkdown training team, and has instructed engineers how to apply SQUG methodology to the resolutien of Unresolved Safety Issue l A-46. Mr. Cushing has extensive experience in construction and startup testing in nuclear and fossil fueled power plants and petroleum refineries, including valve testing, pump performance and vibration testing, system functional and preoperational testing on such systems as plant cooling water, condensate, main and auxiliary steam, turbine control and lube oil, main and auxiliary feedwater, chemical injection, service gas, and demineralizer systems. He was responsible for all plant fire protection systems from construction phase to turnover to client, including Halon, CO 2and air supervised and deluge water systems. He wrote and performed Halon and CO2 flooding tests. He performed vibration, fan performance, and HVAC damper testing on~all HVAC systems. He participated in piping walkdowns of all of the above systems and prepared those systems and packages for turnover to client operations department. He also wTote and reviewed administrative, mechanical prerequisite and pre-operational startup tests for Taiwan and Korea nuclear projects. He has also performed valve maintenance during refueling outages. Duties included planning and supervision of removal, analysis, repair, and installation of various valves in plant. Mr. Cushing is responsible for maintaining a database of replacement parts and components for equipment in nuclear power facilities. Involvement includes collecting experience data and incorporating it into programs which he helped develop for utilities to use in the seismic evaluation of those parts. He is an author of the industry guidelines for the seismic technical evaluation for replacement items. Mr. Cushing has participated in the development of seismic design criteria for fire protection piping and equipment to be installed in nuclear facilities. Development of these criteria involved dynamic analysis of piping, determination of allowable loads and design configurations, and detennination of compliance with ! NFPA and ANSI /ASME codes. N p:\ resumes \ec\rwc-95/iry I

RONALD W. CUSHING

,  PROFESSIONAL EXPERIENCE (CONTINUED)

Ib) Mr. Cushing has conducted root cause analysis of failed plant components. He set up and implemented a failure analysis report program and was responsible for assigning failure reports to proper work group and coordinating completion and distribution. He distributed and tracked implementation of recommended corrective actions. Mr. Cushing also has worked as a member of a Preventative Maintenance Task Force reviewing and evaluating Preventative Maintenance requirements. Mr. Cushing has extensive experience traveling to client locations, such as water treatment and petrochemical plant as well as both fossil and nuclear power plants. He has been involved in consultation, construction, startup, repair and rebuilding of high pressure and large capacity pumps, compressors, motors, and turbines. Mr. Cushing has supervised work crews in field repairs. He became involved in company evaluations of products requiring performance tests and technical data collection and analysis of high pressure feedwater pumps, condensate pumps, circulating water pumps, slurry pumps, etc. EDUCATION PURDUE UNIVERSITY: B.S. Industrial Engineering,1976 REGISTRATION MechanicalEngineer: Califomia f% V PUBLICATIONS AND REPORTS

   " Guideline for the Seismic Technical Evaluation of Replacement items for Nuclear Power Plants (PSE-001)." February,1993. With S. P. Harris, H. W. Johnson, J. M. Abeles. Electric Power Research Institute. Charlotte, N. C. Report NP-7484.
   " Seismic Open Items Resolution (Phase 1) for Chin Shan Nuclear Power Station." September,1992. With W. H. Tong, G. S. Hardy, L. W. Tiong. Prepared for Taiwan Power Company.                                                                         l
   " April 1992 Earthquakes in Desert Hot Springs, Califomia." July,1992. Phenomenal News. Prepared for the U. S. Department of Energy.                                                                                                                  ,

1

    " Guidelines for the Seismic Design of Fire Protection Systems." June,1991. With B. Benda and G. E.                                             I Driesen. Paper presented at Pressure Vessel and Piping Conference, San Diego, CA.                                                               l "Use of Seismic Experience Data for Technical Evaluation of Commercial Grade Replacement items."

June,1991. With R. D. Campbell. Paper presented at Pressure Vessel and Piping Conference, San Diego, CA. O p:\ resumes \ec\rwc-95/irv 2

1 1 I l DOUGLAS J. FREELAND PROFESSIONAL HISTORY EQE lnternational, Inc., Irvine, Califomia, Principal Engineer,1990-present Bechtel Corporation, Norwalk, California, Engineering Supervisor, 1971 1990 Liquid Metal Engineering Center, Canoga Park, California, Stress Analyst, 1970-1971 Rocketdyne, Canoga Park, Califomia, Stress Analyst, 1968-1970 PROFESSIONAL EXPERIENCE Mr. Freeland has over 25 years of professional mechanical engineering and project management experience in the design and analysis of systems and equipment at power, industrial, Department of Energy, and petrochemical facilities As a Principal Engineer at EQE, Mr. Freeland is involved in the application of experience data to the evaluation of mechanical, electrical, instrumentation, control, HVAC, raceway and piping systems and components for earthquakes and other natural phenomena hazards. His responsibilities have included evaluation and analysis of systems and equipment for seismic events at several power plants, including response to Nuclear Regulatory Commission Unresolved Safety issue A-46, utilizing the methods developed by the Seismic Qualification Utility Group (SQUG). The efforts involve field investigations, analysis, development of criteria, and retrofit design. He performed post-earthquake investigations q following the 1994 Northridge Earthquake and documented the performance of piping systems. In addition, Mr. Freeland has performed seismic assessments under the Risk Management and Prevention Program (RMPP) at various chemical, industrial and refinery facilities in California to minimize the potential for release of Acutely Hazardous Materials . He has evaluated the adequacy of non-seismically designed piping at several power plants in support of the Main Steam Isolation Valve Leakage Closure Committee of the boiling water reactor (BWR) Owners' Group. He participated in the development of criteria for the seismic evaluation of HVAC ducts at a DOE site. Prior to joining EQE, Mr. Freeland performed and supervised the design and analysis of critical and noncritical piping systems and hardware for major power and petrochemical plants. He was responsible for evaluating the technical adequacy, development of project criteria and training for pipe stress and support analysis. He frequently traveled to various plants to trouble-shoot critical piping systems and equipment during start-up and operation. Mr. Freeland also developed analytical methods and directed structural testing for rocket engine valves and control components and for liquid sodium system piping, pressure vessels, and components. EDUCATION CALIFORNtA STATE UNIVERSITY, Northridge, CA: Mechanical Engineering,1968 Seismic Qualification Utility Group (SQUG)"Walkdown Screening and Seismic Evaluation Training Course" REGISTRATION f Mechanical Engineer: California ( Pntesumes\ec\djf-95\iry

PHILIP S. HASHIMOTO I PROFESSIONAL HISTORY EQE International, Inc., Irvine, California, Senior Consultant,1985-Present ! Structural Mechanics Associates. Inc., Newport Beach, California, Technical Manager, 1980-1985 l Engineering Decision Analysis Company, Irvine, Califomia, Senior Staff Engineer, 1979-1980 l Agbabian Associates, El Segundo, California, Staff Engineer, 1977-1979 i H.J. Degenkolb and Associates, San Francisco, California, Stmetural Designer, 1976-1977 PROFESSIONAL EXPERIENCE 1 1 Mr. Hashimoto has over 19 years of experience in the analysis and capacity evaluation of nuclear plant, ' hardened, industrial, and conventional structures He has evaluated these structures for a variety of extreme loadings, including earthquake, tornado, extreme wind, and nuclear weapons effects. He has been responsible for the development of methodology and criteria used in these studies. Mr. Hashimoto has presented and defended his technical results to DOE, NRC, and other independent review groups. I Mr. Hashimoto has specialized in the capacity evaluation of DOE and nuclear plant civil structures for seismic and tomado loadings. He is familiar with the full range of applicable codes and criteria, including i DOE 6430.1 A, DOE 5480.28, DOE-STD-1020, BNL 52361, USNRC Standard Review Plan, EPRI Seismic Margin Assessment guidelines, ACI 318, ACI 349, ACI 530, ACI 531, AISC Manual of Construction and LRFD specifications, and Uniform Building Code. He is a member of ACI Committee [ 349, Code Requirements for Nuclear Safety Related Concrete Structures and the Dynamic Analysis of \ Nuclear Structures Committee of the ASCE Structural Division. i l Mr. Hashimoto has performed the dynamic seismic analysis of numerous civil structures at nuclear plants ! and DOE facilities. He has employed both linear and nonlinear analysis methods with a variety of analytical representations, ranging from simplified approximations to detailed finite element models. He has implemented various structural analysis software, such as SAP IV, DRAIN-2D, EASE, ALGOR, etc. Mr. Hashimoto has directed the seismic ar.d tornado analysis and capacity evaluations of numerous DOE structures and storage tanks, including those at the Idaho National Engineering Laboratory, Kansas City Plant, Hanford Reservation, Rocky Flats Plant, and High Flux !sotope Reactor. He has served as Project Manager for EQE's Basic Ordering Agreement with Westinghouse Idaho Nuclear Company. Projects at the INEL performed under his direction include seismic evaluations of high level liquid waste (HLLW) tank vaults and Bin Set I at the Idaho Chemical Processing Plant (ICPP), structural evaluation of the Irradiated Fuels Storage Facility, independent review of seismic analyses for ICPP Building 666 and HLLW tanks, seismic upgrade design of water storage tanks at Argonne National Laboratory West, and structural fragilities for the Advanced Test Reactor probabilistic risk assessment. Mr. Hashimoto is currently serving as EQE's Project Manager for the DOE Kansas City Plant Structural Evaluation Program, a five year, multi-million dollar effort to evaluate the adequacy of all buildings at the j plant for gravity, seismic, and wind loads following current DOE criteria. In this capacity, he has been responsible for development of project plans and schedules. specification of criteria and methods, coordination of project staff, review of technical results, and interfacing with the site contractor and DOE. i s' k PARESUMES\EC\PSH-95. DOC /iry 1

           . , = .-

_ ..m_ _._ . . _ . _ _ _ . _ _ - _. _.___ _ . - . PHILIP S. HASHIMOTO. I PROFESSIONAL EXPERIENCE (CONTINUED) j He has managed a diversity of other projects at DOE sites, including the seismic evaluation of N Reactor Building 181 at the Hanford Reservation, seismic fragility evaluation of N Reactor buildings, seismic evaluation and upgrade of process tanks at the Rocky Flats Plant, and seismic and wind evaluation of , buildings at the High Flux Isotope Reactor by deterministic and probabilistic methods. ; He has directed and performed seismic probabilistic risk assessments and seismic margin assessments for commercial nuclear and DOE reactors. Mr. Hashimoto has most recently served as project manager for : such studies in response to seismic Individual Plant Examination of Extemal Events for the Monticello, ! Prairie Island, Surry, and North Anna nuclear power plants. He has evaluated civil structures and venical l storage tanks in over 25 nuclear power plant probabilistic risk assessments and seismic margin ! assessments. ; Mr. Hashimoto developed the structural capacity fragilities for Phase 1 of the USNRC's Seismic Safety Margins Research Program (SSMRP) and the applications of the SSMRP methodology to other nuclear , plants. He performed special studies to assess the effect of nonlinear behavior on structure seismic response and in-structure seismic input, identify sources of structure dynamic response random variability, l and quantify structure modeling uncertainties. ; 1 Using methodology and techniques similar to those adopted for the seismic structural fragilities, Mr. Hashimoto generated the probabilistic distributions of the intemal pressure capacities of nuclear - , containment structures subjected to loss-of-coolant accidents. Detailed techniques were developed to analyze both reinforced and prestressed containments as well as non-structural components such as hatches, penetrations, etc. He was the principal investigator on two major canhquake engineering research studies sponsored by the USNRC. He investigated the adequacy of R.G.1.61, which specify damping criteria for design basis : elastic analysis of nuclear power plant structures. He also performed research into guidelines and criteria for structure stiffness and damping based upon actual carthquake motions recorded in a low aspect ratio shear wall building. For the Electric Power Research Institute, Mr. Hashimoto performed a research study to investigate the use of data on the performance of ground mounted, anchored venical storage tanks in past canhquakes to assess the seismic adequacy of essential nuclear plant tanks. This study demonstrated that experience data l are applicable to nuclear plant tanks, and anchored tanks are capable of surviving canhquakes having l ground motions greater than most nuclear plant design bases without a loss of fluid contents. Detailed seismic evaluatioris of selected database tanks were performed using current analytical methods. I Mr. Hashimoto directed a program to seismically qualify cable tray supports at Seabrook Station. Selected cable tray systems were dynamically analyzed using detailed finite element models. Other systems were qualified by parametric comparison to representative configurations subjected to shake table testing. Mr. Hashimoto participated in various projects utilizing earthquake experience data to demonstrate seismic adequacy of nuclear plant components. He applied data towards the evaluation of cable tray systems. In addition, he developed quantitative data supponing the use of earthquake experience data in seismic interaction studies of piping systems. ( . l PARESUMES\EC\PSH-95. DOC /irv 2

PHILIP S. HASHIMOTO PROFESSIONAL EXPERIENCE (CONTINUED) Mr. Hashimoto has conducted various studies of structures subjected to nuclear weapons and accidental ) explosion effects. He performed analyses to predict the response oflined and unlined water-filled cavities for the DIABLO HAWK event at the Nevada Test Site. Mr. Hashimoto participated in conceptual design studies of the hardened shelter concept for the MX Missile. Mr. Hashimoto has also evaluated the loading, response, and resistance of device assembly facilities subjected to accidental explosions. l l EDUCATION l 1 1 UNIVER$!TY OF CALIFORNIA, Berkeley: M.S. Civil Engineering,1976 UNIVERSITY OF CAUFORNIA, Berkeley: B.S. Civil Engineering,1975 REGISTRATION CivilEngineer: California AFFILIATIONS American Society of Civil Engineers American Concrete Institute ASCE Dynamic Analysis Committee ACI Committee 349 Earthquake Engineering Research Institute n I 4 O U.S. CITIZENSHIP Yes PUBLICATIONS With M.W. Johnson, D.K. Nakaki, J.J. Wilson, D.T. Lynch, and M.A. Drury, " Structural Load Inventory Database for the Kansas City Plant," presented at the Fourth DOE Natural Phenomena Hazards Mitigation Conference, Atlanta, Georgia, October 19-22,1993. With A.K. Basak," Seismic Capacity and Failure Modes of Flat-Bottom Storage Tanks," Journal of Enercy Encineerint American Society of Civil Engineers, August,1993. With L.K. Steele, J.J. Johnson, and R.W. Mensing," Review of Structural Damping Values for Elastic Seismic Analysis of Nuclear Power Plants," prepared for the U.S. Nuclear Regulatory Commission, NUREG/CR-6011, March 1993. With L.W. Tiong, L.K. Steele, J.J. Johnson, and J.L. Beck'," Stiffness and Damping Properties of a Low Aspect Ratio Shear Wall Building Based on Recorded Earthquake Responses," prepared for the U.S. Nuclear Regulatory Commission, NUREGICR-6012, March 1993. O- l i l PARESUMES\EC\PSH-95. DOC /irv 3 I l I

PHILIP S. HASHIMOTO PUBLICATIONS (CONTINUED) G With E.D. Uldrich and W.D. McGee, " Seismic Scoping Evaluation of High Level Liquid Water Tank Vaults at the Idaho Chemical Processing Plant," presented at the Third DOE Natural Phenomena Hazards Mitigation Conference, St. Louis, Missouri October 15 18,1991. With L.K. Steele, J.J. Johnson, and J.F. Costello, " Review of Regulatory Guide 1.61 Structure Damping . Criteria," Transactions of the i Ith Conference on Structural Mechanics in Reactor Technology, Volume K, August 1991. With L.W. Tiong, J.L. Beck, and J.F. Costello, " Structural Propenies of a Low-Rise Shear Wall Building Obtained from Recorded Earthquake Responses," Transactions of the Ilth Conference on Structural Mechanics in Reactor Technology, Volume K, August 1991. With A.K. Basak, " Failure Modes of Flat Bottom Venical Storage Tanks", presented at the ASCE Specialty Conference on Energy in the 90's, Pittsburgh, Pennsylvania, March,1991. With J.J. Johnson, J.F. Costello, And O.R. Maslenikov, "A Reassessment of Structural Damping Values", presented at the Third Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, Orlando, Florida, December,1990. With J.L. Beck and J.F. Costello, " Seismic Analysis of a Low-Rise Shear Wall Building Using Actual Recorded Eanhquake Motions", presented at the Third Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, Orlando, Florida, December,1990. , I With M.K. Ravindra, R.D. Campbell, P.G. Prassinos, R.C. Murray, " Seismic Risk Analysis of Spent Fuel l v Pools." Paper presented at the Tenth Conference on Structural Mechanics in Reactor Technology, Los Angeles, Califomia, August,1989. With S.P. Harris and R.L. Stover, " Seismic High Wind, Tornado, and Probabilistic Risk Assessments - The High Flux Isotope Reactor, Oak Ridge National Laboratory." Paper presented at the Tenth Conference on Structural Mechanics in Reactor Technology, Los Angeles, California, August,1989. With L.W. Tiong, " Earthquake Experience Data on Anchored, Ground-Mounted Venical Storage Tanks." i Prepared for Electric Power Research Institute, EPRI NP-6276,3412 Hillview Avenue, Palo Alto, CA l 94304. March 1989. With P.G. Prassinos, C.Y. Kimura, D.B. McCallen, R.C. Murray, Lawrence Livermore National Laboratory. M.K. Ravindra, R.D. Campbell, A.M. Nafday, W.H. Tong, EQE Engineering Inc., " Seismic Failure and Cask Drop Analyses of the Spent Fuel Pools at Two Representative Nuclear Power Plants." Prepared for Division of Safety issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, January 1989. With H.T. Tang and L.W. Tiong, "Eanhquake Experience Data Relevant to Nuclear Plant Venical Storage Tanks." Paper presented at the Second Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping with Emphasis on Resolution of Seismic Issues in Low Seismkity Regions, Orlando, Florida, December,1988. With L.W. Tiong and H.T. Tang, " Earthquake Experience Data on Ground Mounted Anchored Venical Storage Tanks." Paper presented at the Ninth World Conference on Eanhquake Engineering, Tokyo, Japan,1988. , %.) PARESUMES\EC\PSR95. DOC /irv 4

PHILIP S. HASHIMOTO A Q - PUBLICATIONS (CONTINUED) With M.K. Ravindra and G.S. Hardy," Seismic Margins Review of Nuclear Power Plants: Fragility Aspects." Paper prese.nted at the Ninth Conference on Structural Mechanics in Reactor Technology, Lausanne, Switzerland, August 1987. With M.K. Ravindra, G.S. Hardy, M.J. Griffin, " Seismic Margin Review of the Maine Yankee Atomic ; Power Station." Prepared for Division of Engineering Safety Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, March 1987. With D.A. Wesley and R.B. Narver. " Seismic Capacities of Existing Nuclear Plant Structures." Paper presented at the Seventh Conference on Structural Mechanics in Reactor Technology, Chicago, IL, August 1983. With D.A. Wesley, " Seismic Structural Fragility investigation for the Zion Nuclear Power Plant." Prepared for Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, October 1981. With D.A. Wesley, " Random Variability of Dynamic Characteristics of Nuclear Power Plant Shear Wall Structures." Paper presented at the Sixth Conference on Structural Mechanics in Reactor Technology, Paris, France, August 1981. With D.A. Wesley. " Nonlinear Structural Response Characteristics of Nuclear Power Plant Shear Wall Structures." Paper presented at the Sixth Conference on Structural Mechanics in Reactor Technology, Paris, France, August 1981. E i i l V P.\ RESUMES \EC\PSH-95. DOC /iry 5

n. CARL R. NELMAN .i

'U i PROFESSIONAL HISTORY EQE lnternational, Inc., Irvine, Califomia, Project Engineer,1990-present Rockwl/ International Corporation, Downey, Califomia, Stress Analyst, 1987-1989; Project Engineer, 1984-1987-Bechtel Power Corporation, Norwalk, California, Piping Engineer, 1983-1984 l i PROFESSIONAL EXPERIENCE - i I At EQE Mr. Nelman is Project Engineer for various seismic interaction, analysis, and seismic qualification j efforts for nuclear facility systems, piping, and equipment. The efforts involve review of data from past j earthquake investigations, post earthquake investigations, development of criteria based on the EQE , Earthquake Experience Database, analysis, field investigations, and retrofit design. The systems and l components evaluated include mechanical, electrical, instrumentation, electrical raceways, and piping ! systems. Major programs have included seismic interaction evaluation for Comanche Peak Steam Electric Station and Watts Bar Nuclear Plant equipment, piping, HVAC, and electrical raceways, and piping evaluation for the Beznau Facility in Switzerland. Mr. Nelman has performed A-46 and IPEEE evaluations for Brunswick and Oconee Nuclear Power Plants. As a mechanical engineer for Rockwell International from 1987 to 1990, Mr. Nelman performed duties as a Stress Analyst for the Space Shuttle program. He performed various analysis reports for numerous O,A components of the Stabilized Payload Deployment System; and performed numerous NASTRAN analyses

     ~ for many and varied components of payload integration mounting hardware, and Shuttle component systems, payloads, and hardware kits.

Mr. Nelman also served as a Project Engineer for Rockwell from 1984 to 1987. His primary responsibility was for the design, development, manufacture, and installation of an MX Missile Guidance and Control > Assembly (GCA) Insertion / Removal Trainer for the Air Force. In addition, he provided project engineer services for design, development, and manufacture of coolant hoses and test equipment fixtures for the Small ICBM GCA. As a Piping Engineer for Bechtel Power Corp. from 1983 to 1984 Mr. Nelman was assigned to the Palo Verde Nuclear Power Plant project. He was responsible for specifying piping and valves for installation, performing material suitability studies, and researching ASME B & PV Code interpretations. In addition to his work in the private sector, Mr. Nelman is a member of the Naval Reserve Civil Engineer Corps. He holds the rank of Commander, and has a Secret security clearance. Mr. Nelman, is a registered Professional Engineer in the State of California. As Stress Analyst for the Space Shuttle Program for Rockwell Intemational, he performed various stress analysis calculations for numerous components of Stabilized Payload Deployment, performed NASTRAN stress analysis for numerous components of payload integration mounting hardware, performed stress analysis and prepared final report for various Shuttle components, payloads, and hardware " kits." For the MX and Small ICBM Missile Programs, he was also the Project Engineer responsible for the design, development, manufacturing, and installation of an MX Missile Guidance and Control Assembly (GCA) Insertion / Removal Trainer and Coolant Hoses for the SmallICBM GCA. P:\ resumes \ec\cm-9h 1

l CARL R. NELMAN EDUCATION t SAN DIEGO STATE UNIVERSITY, San Diego, CA: B.S. Mechanical Engineering,1982 UNIVERSITY OF SOUTHERN CAUFORNIA, Los Angeles, CA: B.A. Psychology,1974 AFFILIATIONS l 1 Society of American Military Engineers l Tau Beta Pi Pi Tau Sigma REGISTRATION Mechanical Engineer: California PUBLICATIONS "Eathquake Preparedness," The Military Engineer, July 1993.

   " Earthquake Preparedness can Prevent Disasters", Navy Civil Engineer, Winter 1995.

O > l i l l O . 1 P.\ resumes \ec\cm-95\irv 2 !

  .  .        .      -       - . - . - -                   _ . . . ~ - . .            - -        .     -. -            .. . . . . - . . . _ ,

i I iI I THOMAS R. ROCHE 4 PROFESSIONAL HISTORY EQE International, Inc., Irvine, California. Technical Manager,1987-present Bechtel Festern Power Corporation, Arizona Nuclear Power Project, Principal Startup Engineer, 1983-1987 Bechtel Western Powr Corporation, Norwalk, California, Mechanical Engineer,1982-1983

SUMMARY

Mr. Roche has over twelve years of experience in the design, engineering, st-rtup and analysis of systems and equipment at power, industrial and Department of Energy facilities. His responsibilities have included evaluation and analysis of systems and equipment for seismic events, preoperational testing of nuclear power plant systems, system engineer for nuclear and non-nuclear power plant systems, equipment qualification and post earthquake mvestigations. PROFESSIONAL EXPERIENCE At EQE Mr. Roche is a Technical Manager and Group Manager in the Engineering Consultants Division. ) He is responsible for various seismic evaluation efforts for systems and equipment. 'Ihe efforts involve development of criteria, analysis, field investigations and retrofit design. Systems and components evaluated include mechanical, electrical, instrumentation, control, raceway and piping systems.

 .y-                                                                                                                                          -l Mr. Roche is responsible for" seismic evaluation efforts related to Nuclear Regulatory Commission                                     i Unresolved Safety issue A-46 and Individual Plant Examination of External Events (IPEEE) for nuclear                                   l facilities. He is the Project Manager for A-46 and seismic IPEEE programs for the Brunswick, H.B.

Robinson, Shearon Harris and Comanche Peak power plants. In this capacity, he evaluates the performance of equipment, subsystems and relays for design basis as well as beyond design basis seismic events. He also participated in related programs for the Bemau, Limerick, San Onofre and Donald C. Cook nuclear power plants as well as the Department of Energy Advance Test Reactor and Savannah River Site. Recently, Mr. Roche has focused on the performance oflifelines and industrial facilities during the 1994 Northridge earthquake. Investigations were performed to gain a better understanding of the performance of

       ' industrial facilities and electrical power systems in order to help mitigate the effects of future earthquakes.
       . He was a Principal Investigator for post-earthquake reconnaissance efforts sponsored by the Electric Power Research Institute (EPRI), Lawrence Livermore National Laboratory (LL NL), and the National Earthquake Hazards Reduction Program (NEHRP). He was the industrial facilies Group Coordinator for Earthquake Engineering Research Institute (EERI) post-earthquake reconnaissance publications. He also contributed                                 ,

sections on industrial facilities and lifelines to reports published by the National Center for Earthquake i Engineering Research (NCEER), and the California Seismic Safety Commission. Mr. Roche has performed and supervised the startup of nuclear power plant systems and equipment, l including mechanical, electrical, instrumentation and control systems. In this capacity, Mr. Roche successfully supervised the testing and commissioning of Palo Verde Nuclear Generating Station emergency cooling water and related systems. O

        - p:\resumesWc\TRR 95/irv                                       i

THOMAS R. ROCHE PROFESSIONAL EXPERIENCE (Continued) Mr. Roche evaluated the performance of non-seismically designed piping and condensers in past earthquakes in support of the Main Steam isolation Valve Leakage Closure Committee of the boiling water reactor (BWR) Owners' Group. His study involved research and field investigations of secondary side systems and equipment during past earthquakes and comparison to nuclear power BWR plants. He analyzed the seismic capacity to seismic demand for large steam surface condensers for earthquake experience database power plants and representative BWR plants. He participated in Nuclear Regulatory Commission (NRC) presentations related to this issue. Mr. Roche has contributed to the development of the earthquake experience data base generated for the Seismic Qualification Utilities Group (SQUG). He concentrates on the response of systems to earthquakes at power and industrial facilities. Systems are investigated for the effects of power interruption, relay actuations due to vibration, relay actuations due to system transients, spurious electrical and pneumatic - signals, and control room alarms. He performed post-carthquake investigations following the 1987 Whittier Narrows, the 1987 Superstition Hills, the 1989 Loma Prieta, and the 1994 Northridge Earthquakes. This seismic experience data is being utilized by the nuclear industry to resolve the seismic issues associated with the NRC's Unresolved Safety issue A-46. Mr. Roche was the systems engineer for safety and non-safety systems at the Palo Verde Nuclear Generating Station. Systems included feedwater, steam, sulfuric acid, hypochlorite, cooling water and emergency core cooling. He resolved design and hardware problems encountered during construction, startup and operation of Palo Verde Units 1,2 and 3. He provided revised designs, dispositions to nonconformances and resolved licensing issues. Mr. Roche performed high energy line break analysis for San Onofre Nuclear Generating Station Unit 1. Q b Analysis involved establishing guidelines, field verifications, calculations, system evaluation for safe shutdown and technical writing. Mr. Roche also administered contracts for replacement of emergency cooling water storage tanks for unit 1, conducted studies for upgrading San Onofre Units 2 and 3 water cooling supply to reactor coolant pumps and provided engineering for system modifications. EDUCATION CALIFORNIA POLYTECHNIC STATE UNIVERStrY, San Luis Obispo, B.S.,1982 UNIVERSITY OF CALIFORNIA, Irvine, " Management Practice for Engineers and Professionals," University Extension Program REGISTRATION Mechanical Engineer: California RELATED TRAINING Completed the Seismic Qualification Utility Group (SQUG)" Systems and Relay Evaluation Course" Completed the Seismic Qualification Utility Group (SQUG)"Walkdown Screening and Seismic Evaluation Training Course" l l Completed the EPRI " Add-on Seismic IPE Training Course" 1 D l U l p:\ resumes \cc\TRR-95/irv 2

 - A                                                                                                             4 V                                                                                                             1 l

i i i APPENDIX 4.3-1 ! Composite Safe Shutdown Equipment List (SSEL) O , Operations Department SSEL Review Statement: : i I have reviewed the Safe Shutdown Equipment List (SSEL) dated 12-20-95, to ensure the SSEL is compatible with approved normal and emergency operating procedures for hot shutdown of the plant following a seismic event along with the possible loss of offsite power for seventy two hours'. I have paid particular attention to the four safe shutdown functions: reactor reactivity control, reactor coolant system pressure, reactor coolant system inventory, and decay heat removal. I have also participated in both simulator demonstrations conducted at the BVPS l Unit-1 Simulator. Based on my review, I have found the SSEL to be acceptable. l Sh & JEffr"efP. Shipe 4 O l l 12/20/95 .

O O O Page No. I BEAVER VALLEY POWER STAileN IRiti 1 Report Date/itee: 12-20-95 / 10:24:14 Colf051TE SAFE 5 NUT 00NN Equ! PENT LI51 (SSEL) 528 IslVIDtal PLAlli CelroNENis LIE EqulP SYSTEM /EqulPENT < EqulPENT LOCAi!Oli -~~-> <-- OP. 51. -> POER SWPORTIE SYS. ret'D INTERCOISECil815 REG. Is. TRAIN CLA15 MARK IRL DESCRIPTI0lt Dug. 'to./Rev./ Zone Building F tr.Elv. Re. or Rom / Col. Soti leiES Ilersal Desired REW7 DMG. Ie./REV- 8 SWPORTIE CGrelENis ISSUE (1) (2) (3) (4) (5) i6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) DMG RE-T/B SRVB 713 RCD N/G R I CLOSED GPEN NO RE-21IZ DC-SWBD-1 SK B-1 A 1101 A 02 52-RIA 01/ REACTOR TRIP 3REAKER 'A' 1102 B 02 52-RTB 01/REACiot TRIP IAEAKER 'B' ONG RE-27B SRVB 713 ROD N/G R I CLOSED OPEN Im RE-217Z DC-$WD-2 K 8-7 A RK-5D, RP-6is YARD 735 AT RW5T $R ON ON VES RE-22ET VITAL SUS 3 A 1201A A 18 LT-45-1004 ti/RWST LEWL TRAN5MITTER VII 1.12-25/92 5tVB 735 Colli til VB-C 1R ON ON VES RE-22ET VITAL SUS 3 A 120~3 A 20 LI-OS-100A $3/RW5T LEVEL ISICATOR 1202A B 18 LT-05-1005 45/RW51 LEWL TRAlt9 TITTER RK-5DBF,RP-68,1506.2 YARD 735 Ai RWST $R C41 ON YES RE-22Ei VITAL SUS 4 A 4-674 12028 8 20 LI-QS-100B QS/RWST LEWL llelCATOR vil 1.12-25/92 SRVB 735 CONT RM VB-C 5R OM 0 11 YES RE-22ET VliAL BUS 4 A 1203A A 18 Li-QS-100C 05/RW5T LEWL TRAll5MITTER RK-5DBF,RP-68,1506.2 VARD 735 Ai RW5T 1R ON ON YES RE-22EV VITAL BUS 1 A 4-674 12038 A 20 LI-OS-100C 05/RW$i LEWL ISICATOR SRVB 735 CONT Ril VB-A 5R ON ON YES RE-22EV VITAL BUS 1 A 12044 8 18 Li-QS-1000 QS/RWST LEVEL TRANSMITTER RK-5D, RP-6B VARD 735 Ai RUST 1R ON ON YES RE-22EV V11AL BUS 2 A 12048 8 20 LRcQS-100 45/RW51 LEVEL RECORDER SRVB 735 CONT RM VB-A 1R ON ON YE5 RE-22EV VliAL SUS 2 A 1205A A 18 FT-CH-122 CH/CWGIE HEADER FLOW 150 6.24-268 & 3875 AILB 722 COL 10-1/4 & J 5 R ON ON YES RE-22L VITAL BUS 2 A TRAN5MITTER 12058 A 20 FI-CH-122A CH/CHARGIE HEADER FLOW ISICATOR Vil 1.12-75 1RVB 735 CONI RM BO-A 5R ON ON YEs RE-22L VITAL BUS 2 - A 1206 N/A 07 FCV-CH-122 CN/ CHARGING FLOW CollTROL VALVE ISO 6.24-268 AILS 722 BLEleER S 2 CPEN CLOSED VE5 RE-22L VITBUS II/III BK A 1206C lt/A 000 50V-CH-122 CH/(FCV-lCH-122) SOLEWID RK-34 AILS 722 BLEleER CIS 5E ENERG ENERG YES RE-21FT PNL-DC-3 BK 8-23 A 1207 N/A fl QS-TK-1 q$/ RUST DWG RV-24A YARD 735 YAR0 1R N/A N/A E RE-63V kcl-Ell, E12 A 1208 A 00A lev-CH-l!$8 CH/RW51-CHARGilC Ptfr 150LAll0N ISO 6.24-277 AILB 722 SLEWER 5R CLOSED GPEN YES RE-21FR ECl-E3 BK J A 1209 5 084 lev-CH-II5C CH/VCi 150LAil0N VALVE ISO 6.24-271 AILB 722 BLEISER 1R OPEN CLO5ED YE5 RE-21FR kcl-E3 BK K A 1210 B 08A lev-Cif -1150 CH/RW51-CHARGIE Ptfr 150LAil0N ISO 6.24-277 AILB 722 SLEleER $R CLOSED GPEII YE5 RE-21FR McCl-E4 OK J A lill B 00A MOV-CH-il5E CH/VCT 150LAi!0ll VALVE ISO 6.24-271 AItB 722 BLEleER SR OPEN CLOSED YE5 RE-21FR kcl-E4 BK K A 1212 A 05 CH-P-1A CH/ CHARGING PL9F DWG RM-2A AILB 722 CH-P-1A CIBICLE 5 R RtBI Rist YES RE-21FN SUS AE BK Ell A 1213 5 05 CH-P-1B CH/CHARGIE Pt99 DWG RM-2A AILS 722 CH-P-It Ct4ICLE 5 E OFF 0FF YE5 RE-21FN BUS DF 8K Fil A ( 1214 A/B 05 CH P-IC CH/ CHARGING Pl39 DWG RM-2A AILB 722 CH4-IC CISICLE 5 R OFF 0FF YE5 RE-21FP BUS AE/DF SK EIS A f CERilFICAi!0N: I the liformation identifying the equipment required to bring t% plant to a safe shutdown conditles on this safe Shutdown Equipment List (55EL) l is, ta the best of our knowledge and belief, correct and accurate. (One or more signatures of Systems or Operations Engineers) 1mu G r eds / EEINEER M QA.d t 7_[2 7 I PrIit or Type Name/iltle Signature Date

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_L Page No. 3 BEAVER VALLEY PONER STATION IRlli I Report Dete/llee: 12-20-95 / 10:24:14 CIBFOSITE SAFE $NUiOOW EqulPENT LIST (55EL) 528 ISIVIDUAL PtJuli CIBFONENTS LIU EOUIP SYSTEWEQUIPEM < EQUIPIGIT LOCATIIBl -----> <-- IF. ST. --> PWEt SWPORilE $V1. ret'D IllTERCOISECTION5 REG.

18. TRAIN CLAS$ IGNMC No. Of$CRIPTI0li thsg. Ile./Rev./ Zone Building Ftr.Elv. Re. er Rom / Col. SIRT leTES Ilernal Desired REqD7 ONG. Is./REV. & SWHRTING CIBF0ENTS 155UE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (II) (12) (13) (14) (15) (16) (17) 1234 A 004 IWW-il-8694 $l/IINSI RCL IIOT LIG 150LATICII 150 6.24-275 $FG8 722 PElli A R CLOSED CLO5ED Im RE-flR kcl-E5 K AR A VALVE 1235 B 084 IWf-11-8698 51/10l$l BCL lei LEG ISOLATION ISO 6.24-368 $FGB 722 PENT C R CLOSED CLOSED le RE-21KK kcl-E6 K BJ A MLVE CLOSED CLOSED 10 RE-21tK NCCI-E5 IK A8 A 12M A 004 IWW-$l-836 SI/Illl51 KL COLD LEG ISOLAlloll ' ISO 6.24-275 $FG8 722 PENT A R VALVE 1237 A 004 IWV-11-863A SI/lA L!I51 TO CMG PISFS $WPLV ISO 6.24-115 SFG8 735 lei R CLOSED CLOSES le RE-21EK kcl-E5 9K U A VALVE 12 3 8 ORA IWV-51-863B $l/18 LM5I 10 CMG Pl8FS StPPLY ISO 6.24-114 SFG8 735 les R CLOSED CLOSED Im RE-21KK kcl-E6 K U A VALVE 1239 8 OIS TV-53-1060 $$/10 RCS IIOTLEG RV $1DE OF LOOP ISO 6.24-3402 RCBI 738 8 RCP CWICLE 5R CLOSED GPEN VES RE-21XS PII-AC-10 IK10-20 A STOP $AIFLE ISOLAil0N RP-lGA 1240 A 008 TV-55-105Al K/NOTLEC 5AIFLE NDR IIISIDE CIDIT ISO 6.24-3402, RCSI 718 PENT $R OPEN OPEN VES RE-flIN PK-DC-3 M 8-59 A 150L TRIP VALVE RP-Ith 1241 B 088 TV-$$-105A2 RC/IIOTLEC $AIFLE imR OUT5fDE Cloti vil 7.067-0133,0261 SFG8 722 PENT A 5R OPEN OPEN VES RE-2iXJ, ISO PE-DC-2 8K 8-59 A 150L TRIP VALVE 6.24-3401,3754 RP-ISA 1244 N/A 21 Cll-TK-1A CN/90RIC ACID TAIEC ANLt 752 BA TAlet Cl2 5 II/A N/A 10 N/A N/A A 1245 N/A 21 CN-TK-18 CN/90RIC ACID TAIOC AttB 752 34 TAlet CW $ N/A II/A NO N/A N/A A 1246 A 05 CM-P-2A CN/90RIC ACID TRAII5FER PlDF AILS 752 84 PISP CIS 1R OFF ON VES RE-21FQ ECl-Ell OK B A 1247 5 05 CN-P-28 Cll/90RIC AC19 TRAll5FER Ptfr AILE 752 B4 Ptar CW $R OFF 0 11 YES RE-21F4 Eti-E12 BK B A 1240 B 004 IWW-CN-350 CN/EER601CV IORATIcil ISOLATION Vil-6.48-5 AILO 722 BLEISER $R CLOSED GPEN VES RE-21F5 Eti-E4 OK $ A 2101 II/A 07 RV-RC-551A RC/ PRE 55WIZER RELIEF SAFETY VALM ISO 6.24-350 RC81 767 PZR ClelCLE $ CLOSED CLOSED NO N/A N/A A 2102 II/A 07 RV-RC-5515 RC/ PRES $WlZER RELIEF SAFETY VALVE 150 6.24-350 RCBI 767 P3 CWlCtf $ CLOSED CLOSED le N/A N/A A 2103 II/A 07 RV-RC-551C RC/ PRES $WlZER RELIEF $AFETY VALVE ISO 6.24-350 RCSI 767 PIR CWICLE $ CLOSED CLOSED NO N/A N/A A 21 3 A 004 NOV-RC-535 RC/ PRE 55tRIZER PORV 150LATI0ll ISO 6.24-350 RCSI 768 PR ClBICLE 1R OPEN CLOSED YES RE-21JQ ECI-E5 SK BE A 2105 A 07 PCV-RC-455C RC/ PRE 551RIZER PORV ISO 6.24-349 RCII 767 FM CWICLE $R 20 CLO5ED OPEN VE5 RE-flJT DC-PE-2 N 8-35 A 2106 8 08A NDV-RC-536 RC/ PRES $WIZER PORV ISOLATION ISO 6.24-350 RCOI 768 P3 CWICif 5R OPEN CLOSED YE5 RE-21JQ ECl-E6 OK BC A CERTIFICAfloll:

The liformation identifying the equipment required to bring the plant to a safe shutdeun tenditten en this Safe shutdema Equipment list (55EL) is,13 the best of our kneuledge and belief, correct and atturate. (One er more signatures of Systems or Operattens Engineers) k b WlE / ElIGIEER t2 27 b[ Prlit er Type Name/iltle 5ignature Date T Si, -* / {116HIEf4- M[ /M2Mff Prlwt er Type Name/iltle E 5 f(nature Date

(g (J p) tv (m) v Page Ms. 4 SEAVER VALLEY POWER STATION 881171 CIBF051TE SAFE $NUTOCiNI EqulPNENT LI51 ($5EL) Report Date/itue: 12-20-95 / 10:24:14 528 lelVicuRL PLANT CMP 0ENTS SYSTEN/EQUIPENT < EQUIPMNT LOCATION ----> <-- OP. ST. --> PWER SWPORilE SYS. ret'D INTERCofEECTIONS REC. LINE EQUIP G. TRAIN class MRK 10. DESCRIPil0N Dug. No./Rev./Zene Building F ir.Elv. Re. or Row /Cel. 50Ri MTES thrsal Desired REqD7 IRE. 2./REV. & SWPORilm CIsr0NENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (B) (9) (10) (11) (12) (13) (14) (15) (16) (17) 2107 0 07 PCV-RC-456 RC/PRESSIRIZER FORV 150 6.24-349 RCSX 767 PZR CWICLE 5R 20 CLOSED GPEN VES RE-flJT DC-PNL-3 BK 8-34 A ISO 6.24-350 RCIX 768 PZR CtBICit 5R OPEN ClostD YES RE-21JQ kcl-E6 BK 00 A 2108 A GBA lev-RC-537 RC/NE55tRIZER FORV ISOLATION 2109 A 07 PCV-RC-455D RC/ PRE 55WIZER PORV 150 6.24-349 RCBX 767 PZR ClRICLE 5R 20 CLOSED WEN VES RE-21JT DC-PK-3 8K 8-34 A PT-RC-402 RCMIDE RAEE RCS PRE 551RE TRAlls DWG RK-It RC9X 717 AISEILUS COL 4-5 5 R ON ON YES RE-22tN VITAL BUS 3 A 2110A A 18 21108 A 20 P!-RC-402A RCSMIDE RAKE PRES $tRE ISICATOR Vil 1.12-23 SRV8 735 CONT IN VB-A 5R ON Oil YES RE-229N VITAL BUS 3 A RCNIDE RANGE RCS PRE 55tRE TRAN5 OWG RK-It, RK-IF RCBX 701 A CtAICLE 5R ON ON VE5 RE-229N VITAL BUS 2 A fillA 8 18 PT-RC-403 fli18 I 20 PI-RC-403 RCSNIDE RAIEE PRES $1RE IISICATOR VII 1.12-23 SRVB 735 CONT RN VB-A 5R ON ON VES RE-229N VITAL BUS 2 A 2118 A 07 FCV-RC-455CI RC/(PCV-RC-4550) FLOW NETERING 150 6.24-3706, RK-ID RC8X 767 PRZR CtBICLE 5 OPEN OPEN ND N/A N/A A 2119 A of FCV-RC-455C2 RC/(PCV-RC-455C) FLOW MTERING ISO 6.24-3796, RK-ID RCBX 767 PRZR CLAICLE 5 OPEN OPEN 10 N/A N/A A 2120 8 07 TCV-RC-45501 RC/(PCV-RC-4550) FLOW NETERING 150 6.24-3706, RK-lO RCSX 767 PRZR C!SICLE 5 OPEN OPEN K3 N/A II/A A 2121 5 07 FCV-RC-45502 RC/(PCV-RC-4550) FLOW NETERIE ISO 6.24-3786 RK-lO RC8X 767 PRZR CtBICLE 5 OPEN OPEN 10 N/A N/A A 2122 8 000 50V-RC-455C) SI/(PCV-RC-4550) SOLENDID 150 6.24-3786,RK-ID RCBX 767 PRZR CISICLE 5R CLOSED GPEN YE5 RE-21Ji PNL-DC-2 8K 8-35 A 2123 8 088 50V-RC-455C2 SI(PCV-AC-455C) SOLENDID 150 6.24-3786,RK-lO RCBX 767 PRZR CISICLE 5R CLO!ED OPEN YES RE-21JT PNL-DC-2 BK 8-35 A 2124 A 085 50V-RC-455DI SI/(PCV-RC-4550) 50LEleID 150 6.24-3786,RK-lO RC8X 767 PRZR CtBICLE 1R CLOSED GPfli VES RE-21Ji PNL-DC-3 BK 8-34 A 2125 A 095 50V-RC-45502 Sl(PCV-RC-45s0) SOLENDID 150 6.24-3706.RK-lO RCBX 767 PRZR CISICLE $R Closed GPEN YES RE-flJT PNL-DC-3 BK 8-34 A , 2126 A 088 50V-RC-456-1 RC/(PCV-RC-456) 50LEIGIO RK-lO RCSX 767 PRZR CISICLE 5R CLOSED GPEN VES RE-flJi FNL-DC-3 RK 8-34 A 2127 A 08B $0V-RC-456-2 RK-!D RCBX 167 PRZR CLBICLE 5R CLD5ED OPEN VES RE-21JT PNL-DC-3 BK 8-34 A RC/(PCV-RC-456) SOLEleID 2128 II/A 07 PCV-CN-108 SI/(PCV-RC-455D) NITR0 GEN PRES $llit IRIG RK-lO RCBX 767 PRZR ClelCLE $ OPEN OPEN 10 N/A N/A A CONTROL 2129 N/A 07 PCV-CN-109 SI/(PCV-AC-455C) NITR0 GEN PRES $lRE OWG RK-ID RCBX 767 PRZR Cts!CLE 5 OPEN OPEN 10 N/A N/A A CONTROL 2130 N/A 07 PCV-IA-108 lA/(PCV-RC-4550) INST AIR PRES $tRE DWG RK-lO RCBI 767 CRANE WALL 5 OPEN OPEN ND N/A N/A A CONTROL 2131 N/A 07 FCV-I A-109 IA/(PCV-RC-455C) INST AIR PRES $URE DWG RK-lO RCII 767 CRANE ilALL 5 GPEN OPEN ND N/A N/A A CONTROL CERllFICAfl0N: The I; formation identifying the equipment required to tring the plant to a safe shutdown condition en this safe Shutdown Equipment List (55EL) Is, ta the test of our knowledge and belief, corrett and atturate. (One or more signatures of Systems or Operattens Engineers) a %ic / toi it Prlit er Type llEr/ Title

                                              & FM     Signature n/u /d  Date
   &v                / UttNEER Prlit er Type Name/fitte 0$%/
                                                      Tfg4dture -
                                                                                                                        /) 22 Fr Date

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U(\ V( Page No. 5 NAVER WALLEY POWER STAilellISili ! Report Date/iler: 12-20-95 / 10:24:14 CarollTE SAFE SIRM EqulPIEW Ll51 (15EL) 52s IRIVicWL PLWT CereNENi$ LIZZ EqulP SYSTDl/EqulPMEllt < EQUlPIEW LOCAil8N ---> <-- OP. ST. --> PWER SWFWillE SYS. RE4'O INTERCWEEtileE REC. W. TRAIN CLASS fulRK 18. DESCRIPil0N Bug. Ilo./tev./2ene Bellding Ftr.Elv, Re. er Reu/Cel. Seti IsfE5 IIsreal bestred Mp? SE. W./REV. & SWFWillE CepeENTS ISSME (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 2132 WA 21 Gil-TK-1A GN/ NITROGEN NUSER ACCifRRATOR RCSX 767 PRN CWICLE 1 WA WA le WA WA A 2133 II/A 21 Gil-TK-18 GII/IlliROGEN HEADER ACCifGRAIGR RCBI 767 PRN CWICLE 5 N/A 11/ 4 15 N/A WA A 2201A A 18 Li-45-1004 41/RW5T LEVEL TRA119tliiER K-50, RP-M VARC 735 AT RUST $t ON ON VE5 RE-2Mi VITAL SUS 3 A 22018 A 20 LI-35-1004 ts/ RUST LEVEL IMICATOR VII 1.12-25/92 3RVB 735 CONT IN VB-C $R ON ON VES RE-2Mi VITAL SUS 3 A 2202A 8 18 LT-45-1008 QS/ RUST LEVEL TRA1190 LITER RK-500F,RP-EB,1305.2 YARD 735 At RU5T $R 0 18 ON VES RE-2Mi VITAL SUS 4 A 4-674 220N 8 20 LI-45-1005 45/RW5T LEVEL IMICAict Vil 1.12-25/92 SRW 735 CONT RIl VB-C 5R 0 11 Oli YES RE-2MT VITAL SUS 4 A 2203A A la LT-45-1000 45/RW51 LEVEL TRA119 TITTER K-588F.RP-W,1506.2 YARD 735 Ai RUST 5t CN 0 11 YES E-22EV V!YAL SUS 1 A 4-674 220'3 A 20 L1-q1-100C 45/RW51 LEVEL IMICATOR styt -735 Colli RN V8-A 5t ON ON VES RE-2MV VliAL BUS 1 A 22004 8 18 LT-QS-1000 45/ RUST LEVEL TRAII91tTTER K-50, RP-M YARD 735 Ai RUST 5R ON ON VES RE-2MV VITAL BUS 2 A 22048 B 20 LR-45-100 QS/RW$i LEVEL REC 0ADER 5tyt 735 Colli Rel W-A 5t ON ON VES RE-FMV VITAL SUS 2 A 2205A B 18 FT-CN-122 CN/ CHARGING IIEADER Flow ISO 6.24-268 & 3875 AXLI 722 COL 10-1/4 & J 5 R ON CII VE5 RE-22L VITAL tus 2 A TRAIIDEITTER 22058 8 20 FI-CH-1224 CN/CilARGillE HEADER FLOW IMICATOR VII 1.12-75 SPV5 735 C0lli RN W-A 5t ON SN VES K-22L VITAL SUS 2 A 2206 1;/A 07 FCV-CN-122 CN/CllARGilE FLOW CONTROL WLVE 150 6.24-2E8 ARS 722 ILEWEt 1 2 OPEN CLOSED TES E-22L VITOUS II/III OK A 220lf 11/4 088 50V-CN-122 CN/(FCV-1CN-122) 50LElml0 K-34 AXLI 722 BLEWER CW $R ENERG EIOC YES RE-22L PE-DC-3 BK 8-23 A 2207 N/A 21 QS-it-1 QS/RW5i OllG RV-244 YARD 735 YARO 5R N/A II/A le RE-63V KCI-Ell, E12 A 2200 A OSA NOV-CH-1158 CN/ RUST-CNARGING PISF 150LAfl0N 150 6.24-277 AXLB 722 BLEWER SR CLOSED GPEN VE5 RE-flFR kcl-E3 SK J A 2209 5 004 IOV-CN-115C CN/VCT ISOLAil0N VALVE ISO 6.24-271 AXLB 722 BLEWER $R OPEN CLOSED YES RE-21FR NEC1-E3 BK K A 2210 B 004 Nov-CH-1150 Cll/RU5T-CllARGilm Pt9F ISOLATICII 150 6.24-277 AXLB 722 BLEWER SR CLOSED OPEN VE5 H-21FR IICCI-E4 IK J A 2211 B 004 IWV-CN-II5E CN/ VET 150LA110ll VALVE 150 6.24-271 AXLS 722 BLEWER 1R OPEN CLOSED YE5 RE-21FR NCCl-E4 8K K A 2212 A 05 C!I-P-14 CN/CilARGING Ptar DMG RM-2A AXLB 722 CM-P-IA CWICLE 5 R Rtal Ripi YES RE-21FN SUS AE SC Eli A 2213 3 05 CM-P-18 CN/CHARGillG PIDF ONG RN-24 AXL5 722 CM-P-It CSICLE $ R OFF 0FF YES RE-21FN BUS OF SK Fil A 2214 A/B 05 Cll-P-IC Cit /CilARGils PisF BMG RM-2A AXLI 722 CH-P-It CWICLE 5 E OFF 0FF YES H-21FP BUS AE/DF BK E15 A C!lilFICAfl0N: The IIfereatles identifying the equipment required to bring the plant to a safe shutdown conditles se this Safe Shutdeue Epipment list (55EL) is,13 the best of eer knowledge and belief, correct and accurate. (One or more signatures of Systees or Operatless Engineers) r~ 1z!z7l9f 1 rRRiE / tisillttR 3 f 4aer.JL FrLt er Type h/iltle Signature Date

                                ~%,m                / tIR1MER t er Type Name/Iltle                                v U qdature
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p f n Page No. 6 BEAVER WALLET POWER STATION L8lli I Report Date/Ilme: 12-20-95 / 10:24:14 CIBF051TE SAFE SMUT 00MN EQUIMNT LI$i (S$EL) 528 IWlVIOUnl PLANT C0fr0NENT1 11 ] EQUIP $YSTEM/ EQUIPMENT < - EQUIPMENT LOCATION -----> <- CP. $T. --> POWER $LFPORilE $YS. REQ'D INTERC018ECTIONS REG. NO. TRAIN CLA11 MARK ND. DESCRIPil0N Ihsg. Ms./Rev./ Zone Building Ftr.Elv. Re. or Row / Col. 50RT NOTES Hersal Oesired REQD7 DNG. NO./REV. & StFPORTING CGFONENTS liSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 2215 A GBA lev-CH-289 CH/ CHARGING MEADER ISOLATION ISO 6.24-268 SFG8 722 PENT A R OPEN OPEN NO RE-flFS ECl-E5 BK 88 A 2216 8 004 MOV-CH-310 CN/ CHARGING NEADER ISOLAfl0N ISO 6.24-253 RC8X 693 49-3 RAD AZ 350 R OPEN OPEN le RE-21F1 kcl-E6 BK AX A 2217 A 08A MOV-CH-275A CH/CH-P-1A MINIFLOW ISOLATION ISO 6.24-265 AXL8 722 CH-P-14 CISICLE R OPEN OPEN NO RE-21FR MCCl-E3 BK H A 2218 A 08A lev-CH-2758 CH/CH-P-18 MINIFLOW 150LAil0N 150 6.24-265 AXtl 722 CH-P-18 CLAICLE R OPEN OPEN le RE-21FR kcl-E3 8K P A 2219 A 00A MOV-CH-275C CH/Cll-P-IC MIN! FLOW ISOLATION ISO 6.24-265 AXtB 722 CH-P-IC CUSICLE R OPEN OPEN le RE-21FR MCCI-E3 BK Q A 2220 8 00A lev-CH-373 CH/CHARGIIC Pt#F REtlRC ISOLATION ISO 6.24-256 AXL8 722 8tEWER R OPEN OPEN le RE-21FR IEil-E4 BK Q A 2221 N/A 21 ISO 6.24-256 RM-2A AXtB 722 LETDOWN CISICLE $ 4 N/A N/A NO N/A N/A A

CH-E.1 CN/ SEAL MATER HEAT EXCHANGER RP-10C 2222 A ORA MOV-SI-867A SI/Bli ISOLATION VALVE ISO 6.24-272 AXtB 722 BLEleER R CLOSED GPEN YES RE-21XI kcl-E5 8K V A 1213 8 08A MOV-51-8678 $1/Bli ISOLAi!0N VALVE !$0 6.24-272 AXtB 722 BLEWER R CLOSED GPEN YES RE-21XT MCCI-E6 BK W A 2224 A 21 PZR-HTR-A RC/ PRE 55tRIZER HEATER RCBX 739 IN PZR R OFF ON YES RE-21Jit 480V BUS INI BK N12 A 2225 8 21 PZR-MTR-8 RC/ PRES $1RIZER HEATER RC8X 739 IN PZR R OFF ON YES RE-21JR 400V BUS IPI BK A 2226 A 21 PZR-HTR-D RC/ PRE 55URIZER MEATEF RCBX 739 IN P2R R OFF ON VES RE-21JS 400V BUS IN SK N A 2227 8 21 PZR-Hit-E RC/ PRE $$tRIZER HEATER RCBX 739 IN P2R R OFF ON VES RE-21J$ 480V BUS IP BC P A 2228A A 18 FT-CH-124 CN/RCP-lC SEAL INJECTIOW FtJd l$0 6.24-3952, RK-3E $FG8 722 PENT A $R ON ON YES RE-22G PRI-PROC 20 VB3 A TRAN9tliTER 22200 A 20 FI-CH-124 CH/RCP-10 $EAL INJECilON FLOW VII 1.12-22, 23 $Rv8 735 CONT RM V8-A $R ON ON VES RE-22G PRI-PROC 20 V83 A IIelCATOR 22294 8 18 FT-CH-127 CH/RCP-18 $EAL INJECil0N FL(w 150 6.24-3953. RK-3E $FG8 722 PENT A $R ON ON YES RE-22G PRI-PROC 9 V82 A TRAN5MlliER 22298 8 20 F1-CH-127 CH/ REP-18 SEAL INJECil0N FLOW VII 1.12-22, 23 SRv8 735 CONT RM V8-A 5R ON ON VES RE-22G PRI-PROC 9 V82 A IWICATOR 2D0A A 18 FT-CH-130 CH/RCP-1A SEAL INJEC110N FLOW ISO 6.24-3630 RK-3E 5FG8 722 PENT A $R ON ON YES RE-22G PRI-PROC 6 V81 A TRAN5MlITER 22308 A 20 FI-CH-130 CH/RCP-IA SEAL INJECTION FLOW Vil 1.12-22, 23 SRV8 735 CONT RM V8-A $R ON ON VES RE-22G PRI-PROC 6 V81 A IWICATOR 3101A A 18 li-QS-1004 QS/RW51 LEVEL TRAN5MITi[R RK-5D, RP-68 YARD 735 AT RWST $R LA ON YES RE-22ET VITAL BUS 3 A CEtilflCATION:

The IIformation identifying the equipment required to bring the plant to a SPfe shutdown conditlen en this Safe Shutdown Equipment List ($$EL) is, to the best of our knowledge and belief, torrect and accurate. (One or more signatures of Systees or Operations Engineers) u n m / - ,ut Prl*t or Iype Name/11tle A Fm Signature m/n/w Date TD, ~ / tNcinCta Priat or Type Name/iltle Wdb-v Thature -

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Page No. 8 BEAVER UALLEY POWER STAiloli181111 Report Date/ilee: 12-20-95 / 10:24:14 Car 0 SITE SAFE 5HUTDept EqulPIENT LIST (55EL) 528 IRIVIBWAL PLANT CSF0KNTS EqulP SYSTEM /IOUIPMENT < EQUIPMENT LOCAfl04 -----> <-- OP. ST. --> POWER SIFPORTIE SYS. req'D INTERCOMECTIONS REG. Lin No. TRAIN CLASS MARK NO. DESCRIPi10N lbsg. No./Rev./ Zone Bulldlag Ftr.Elv. Re. or Row /Cel. SORT efE5 IIernal Desired REqD7 DWG. W./REV. B SlFPORTIE CGF0ENTS 155UE (1) (2) (3) (4) (5) (6) (7) 18) (9) (10) (II) (12) (13) (14) (15) (16) (17) 3114 A 084 M-CH-2758 CH/Cll-P-1B MINIFLON 150LAi!0N 150 6.24-265 AXL8 722 CH-P-18 CIE!CLE R OPEN OPEN le RE-21FR kcl-E3 SK P A 3119 A GBA MDV-CH-275C CH/CN-P-lC MINIFLOW ISOLATI0ll ISO 6.24-265 AXL8 722 CN-P-lC CUBICLE R OPEN OPEN 2 RE-21FR kcl-E3 8K q A 3120 B 00A let-CH-373 CH/CHARGIE Pt9F RECIRC ISOLATION 150 6.24-256 AXL8 722 BLEWER R OPEN OPEN 10 RE-21FR ECI-E4SKq A 3121 N/A 21 CN-E-1 CH/5EAL WATER NEAT EXCHANGER ISO 6.24-256 RM-2A AILB 722 LE'00MN CtalCLE 5 4 N/A N/A W N/A N/A 4 RP-10C 3122 A 08A MOV-SI-867A SI/Bli 150LAi!0N VALVE ISO 4.24-272 AILS 722 BLEWER R CLOSED CLOSED NO RE-21XT MCCI-E5 BK W A 3123 B ORA MOV-51-8678 51/811 150LATIoll VALVE 150 6.24-272 AXLB 722 BLEleER R CLOSED CLOSED 10 RE-21XT kcl-E6 BK W A 3124A A 18 LT-RC-459 RC/PIR LEVEL TRANSMITTER ISO 6.24-3396, RK-1A RC8X 718 CUI51DE PZR CtB 5 R ON ON YES RE-22818 VITAL BUS 1 A 3124B A 20 LI-RC-459A RC/PZR LEVEL IWICATOR VII 7.70-0002, RK-3A SRVB 735 CONI RM 88-B 5R ON 0 18 YES RE-228N VITAL 805 1 A 3125A B 18 LT-RC-460 RC/PZR LEVEL TRANSMITTER ISO 6.24-3396, RK-1A RC8X 718 OUT5IDE PZR CUB 5 R ON ON YES RE-228J VITAL BUS 2 A 31258 8 20 LL-RC-460 RC/PZR LEVEL IWICATOR Vil F.740002 SRVB 735 CONT RM BB-B 5R ON ON VES RE-228J VITAL BUS 2 A 3126A A 18 Li-RC-461 RC/PIR LEVEL TRANSMITTER ISO 6.24-3396, RK-1A RCSX 718 OUISIDE PZR CUB 5 R ON ON YES RE-228K VITAL BUS 3 A 31268 A 20 LI-RC-461 RC/P2R LEVEL IWICATOR VTI 7.70-0002 SRVB 735 CONI RM 88 -8 5R ON ON VES RE-228K VITAL BUS 3 A 3127 A 08A MDV-SI-863A SI/lA LH5110 CHG PtBFS StFPLY 150 6.24-115 SFG8 735 IAf R CLOSED CLOSED le RE-21KK ECl-Ea A VALVE 3128 8 CAA MOV-SI-8618 51/18 LH5I 10 CHG Pt9F5 StFPLY 150 6.24-114 SFG8 735 lef R CLOS [D CLOSED le RE-21EK MCCI-E5 A VALVE 3129 A 07 HCV-CH-399 Cil/ EXCESS LEIDOWN DRAIN DIVERT VII-07.88-9 RC8X 707 EXC LETD PLATF 5R 7 OPEN OPEN ND RE-21FU PNL-DC-3 8K 8-18 A VALVE 3130 B 08A lev-CH-370 Cit / SEAL IILI HEADER ISOLAll0N ISO 6.24-267 AXLB 722 BLEWER R0WI R OPEN OPEN le RE-21F5 kcl-14 BK AC A 3131 8 07 NCV-CH-196 CH/RCP SEAL SlFPtV, IUWS CONT VII-07.86-7 AXtB 722 BLEMER ROON 5R THROT OPEN 10 RI-22G VITAL BUS 2 A 3132A A 18 FT-CH-124 CH/RCP-IC SEAL INJECTION FLOW 150 6.24-3952, RK-3E SFG8 722 PENT A 5R ON ON YE5 RI-22G PRI-PROC 20 A TRANSMITTER t 31328 A 20 FI-f5124 CH/RCP-IC SEAL INJECil0N FLOW VII 1.12-22, 23 SRVB 735 CONT RM V8-A 5R ON ON YES RE-22G PRI-PROC 20 VB3 A IWICATOR ( 3133A B 14 FT-CH-127 CH/RCP-1B SEAL INJECTION FLOW ISO 6.24-3953 RK-3E 5FGB 722 PENT A 5R ON ON YES RE-22G PRI-PROC 9 A l TRANSMITTER CERTIFICAi!ON: The liformation identifying the equipment required to bring the plant to a safe shutdown conditten on this Safe Shutdown Equipment List (SSEL) is, to the best of our knowledge and belief, correct and accurate. (One er more signatures of Systen er Operat!ons Engineers) (C RW / ENCINEER fritt er Type ame/iltle hw M 5ignature i2 21/ Y Date 79A Priit or Type Name/ Title

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                                                                                                          +                                                                                               w>                                                                                                              a Page lle.10                                                                                                                                               BEAVER MLLEY POWER stall 0N Ifili 1 Report Date/ilme: 12-20-95 / 10:24:14                                                                                                                 COIFOSITE SAFE $NUTD0181 EqulPMENT LIli ($1EL) 528 IWlVIDuRL PLAll! COIFONENTS tl~I                                                 EqulP                                                $YSTEM/ EQUIPMENT                                  <         Equ!PMENT LOCAiloll --->               <-- OP. 51. --> POWER $WPotilE SY1. req'O INTERCD181ECileNS RFC.

W. TRAIN CLASS Itutt IID. DESCRIPTICII Dwg. No./tevjZone Sullding Ftr.Elv. Re. er tou/Cel. $0tf NOTES Nereal Desired REqD2 CMG. IIB./REV. & $tFPORilNG [990NENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 3212A 8 18 FT-CM-150 CM/LITIMIAI FLOW TRAll5MITTER Vil 7.050-0010 AXLR 722 COL 11-1/2 & G $ R ON ON YES RE-22J,0WG vlTAL SUS 2 A RK-34 ! 32128 8 20 FI-CM-150 CH/LETD0181 FLOW IRICAiloll Vil 1.12-75 $RVB 735 CONT RIl BI-A $R ON UN YES RE-22J VliAL BUS 2 A 3216 N/A 07 RV-CH-382A CH/$[AL Ritu llDR RELIEF VALVE 150 6.24-1548 RCIX 718 A18tiLUS COL 5 $ CLOSED CLOSED le N/A N/A A 3217 A 07 TV-1$-108 $1/PZW LiqulD SPACE SWLE 150 RCBX 738 PIR CtsittE R Closed Closed NO RE-21ER PNL-AC-10 8K 7 A 150LAI10N I11-2821A,3680.tP-18 , A 3218 A 07 TV-$5-Il0 $$/PZR VAPOR SPACE SAIFLE DWG RM-324, RP-ISA RCBX 738 PZR CIRICLE R CLOSED CLOSED le RE-21KR PHL-AC-10 BK 7 A ISOLAll0N 3219 A 08A MOV-RN-700 RN/tHE INLET 150LAiloll 150 6.24-3197 2081 692 W OF $1 ACC 1A R CLOSED CLOSED le RE-21JV MCCI-E5 BK P A 3320 A OBA MSV-Ril-7204 RH/RW RETURN ISOLATION ISO 6.24-3189 RC8X 692 W 0F SI ACC 18 R CLOSED CLOSED ND RE-flJV MCCI-E5 BK q A 3321 0 00A MDV-Ril-7208 RH/tHR RETURN 150LAll0N ISO 6.24-3191 RCBX 692 W OF St ACC IC E CLOSED CLOSED W RE-21JV MCCI-E6 BK q A 4101A A 18 LT-VT-104A1 WT/Wi-TK-10 LEVEL TRAII5MlitER 150 6.24-4016 YARs 735 YARD $R ON ON YES RE-22FG VITAL BUS 2 A 4101B A 20 LI-Wi-104A1 WT/Wi-TK-10 LEVEL IMICATOR Stv5 735 CONT RN VB-C $R ON ON YES RE-22FG VITAL BUS 2 A 4102A B 18 LT-Wi-104A2 WT/Wi-TK-10 LEVEL TRAll5 Millet ISO 6.24-4017 YARD 735 YARD $t 04 ON YES RE-22FG VITAL BUS 2 A 4102S 8 20 LI-Wi-104A2 WT/lli-TK-10 LEVEL IISICATOR $RVB 735 CONT RH VB-C $R ON ON YE1 RE-22FC VITAL BUS 2 A 41034 A 18 FT-FW-1004 FW/ AUK FEED TO SGA TRAII5MlifEt RK-8A, ISO 6.24-65 $FGB 735 AUX FEED Ptfr 5t ON ON YES RE-2202 VITAL SUS 1 A 4103 A 20 F1-FW-100A FW/ AUX FEED TO SGA Imit VII 1.12-25 SRV5 735 CONT RN VB-C $R ON ON YES RE-220Z VliAL BUS 1 A 4104A 9 18 FT-FW-1005 FW/ AUX FEED TO SGB TRAll5MiiTER RK-84, ISO 6.24-65 SFG8 735 AUX FEED Ptle 5t ON ON YES RE-2202 VITAL SUS 4 A 41048 8 20 FI-FW-1005 FW/ AUX FEED TO SG8 IWIC VII 1.12-25 SRTS 735 CONT EM VB-C 5t ON ON YES RE-22DZ VITAL BUS 4 A 4105A A 18 FT-FW-100C FW/ AUX FEED To SGC itAll5MITTER RK-8A, ISO 6.24-65 5FG8 735 AUX FEED PLOF $R ON ON YES RE-220Z VITAL BUS 1 A 41058 A 20 FI-TV-100C FW/ AUX FEED 10 SGC IWIC Vil 1.12-25 5tV8 735 CONT mt VI-C $R ON ON - YES RE-2202 VITAL OUS 1 A 4106 N/A 21 Wi-TK-10 WT/DEMIN WATER STORAGE TAIK OWG tv-34A.RP-6C YARD 735 YARD 5 N/A II/A E N/A A 4107 A 05 FM-P-3A FW/HDTOR ORIVEN AUX FEEDWATER Pt99 Vil 2.40-11,12 $FGB 735 AUX TEED Pter st 0FF 04 YES RC-21C,M,RE-flM BUS AE SK E16 A E RM-15,6.24-64 410?C A 0F FCV-FW-103A TV/3A AFW PtpF RECIRCULATION VALVE 150 6.24-774 SFGB 735 AFW E00N $R Closed OPE 1 YE5 RE-21HD PNL-DC-3 BK 8-53 A CERTIFICATION. The liformallen Identifying the equipment required to bring the plant to a safe shutdeun tendition en this $afe Shutdown Equipment List ($$EL) is, to the best of our kneuledge and belief, corrett and accurate. (Ome er more signatures of Systems or Operattens Engineers) s Ruiu i EEmER Jrtt er Type Name/iltle

                                                                                                                                        & CA     5ignature u /n /-r  Date EIl *-                                                                / 6N6fWft'                          /--[ -,e,-                            dhI$r Prlit er Type Name/iltle                                                                                      " /59t6ature J                                          Date

f) ) ry V V U Page No.11 BEAVER VALLEY POWER stall 0N tlNii I Report Date/ilme: 12-20-95 / 10:24:14 C0F051TE 5AFE $NUTechst EqulPMENT LIST (SSEL) 528 letVIDiat PLANT CelFONENTS Lin EqulP SYSTEM / EQUIPMENT < - Equ! PENT LOCATION ----> <-- OP. ST. --> POKR SIFP0 Rile SYS. req'D INTERC01BEtil0N5 REG. NO. TRAIN CLAS$ MARK NO. KSCRIPTION Dug. No./Rev./ Zone Sullding Ftr.Elv. Re. er Rom / Col. 50Ri NOTES Normal Desired REqD7 DuC. IO./REV. t StFFORTIE CipFONENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (!!) (12) (13) (14) (15) (16) (17) 41070 A 18 F15-N-151A FW/ AUX FW Ptfr FW-7-3A SIEil0N 150 6.24-3831, 3833 SFGR 722 AfW ROM $ ENERG EERG YES RE-21NO PNL-DC-3 K 8-53 A LINE M Wi-TK-10 FIS 410s 8 05 FW-P-38 NMeTOR DRIVEN AUX FEEDIETER Pt9F VII 2.40-11,12 SFC8 735 AUX FEED Ptfr 5R OFF ON YES RC-21C,M,RE-21H SUS OF K Fl6 A E.RM-10,b.24-64 410ec 3 07 FCV-N-103B FV/38 AFW Ptfr RECIRCEATIGIl VALVE ISO 6.24-774 SFGB 735 AFW tolpi 5R CLOSED GPEN YES RE-21NE Phl-DC-3 SK 8-53 A 41000 5 18 FIS-FW-1518 FW/ AUX W Pt3F FW-P-3B StEliON ISO 6.24-3832 SFCI 722 AFW R0WI 5 EERG ENERG MS RE-21E PE-DC-3 BK 8-53 A LINE FROM WT-TK-10 FIS 4100E A/S 008 DV-FP-12 FP/ AUX FEED WATER Ptfr KLUCE VLV RS-16C SFG8 722 NE R CLO5ED CLOSED 10 10.1-474 PNL-DC-4 A 4109 3 00A* MOV-N-151A FU/ AUX FEED FLOW CONTROL VALVE 6.48-55,7.65-34,44 SFC8 735 AUX FEED Pt99 5R 17 OPEN THR01 YES RE-flHF,6.24-65 kcl-E6 BK A6 A 4110 A 00A feV-FW-151B FW/ AUX FEED FLOW CONTROL VALVE 6.48-55,7.65-34,44 SFG8 735 AUX FEED Ptfr 1R 17 OPEN iMROT YES RE-21tlF.6.24-65 MCCI-E5 BK A6 A 4111 8 004 MDV-FW-151C FW/ AUX FEED FLOW CONTROL VALVE 6.40-55,7.65-34,44 SFGE 735 AUX FEED Ptse 1R 17 OPEN TlROT YE5 RE-21MF.6.24-65 MCCI-E6 8K AN A 4112 A 09A MOV-FW-151D FW/ AUX FEID FLOW CONTROL VALVE 6.48 55,7.65-34,44 SFG8 735 AUX FEED Pt#F 1R 17 OPEN THROT YE5 RE-21NF,6.24-65 MCCI-E5 BC AN A 4113 8 ORA Mov-FW-151E FW/ AUX FEID FLOW CONTROL VALVE 6.48-55,7.65-34,44 SFG8 735 AUX FEED Pt99 5R 17 OPEN THROT VES RE-flMF,6.24-65 MCCI-E6 BK AJ A 4114 A ORA MOV-FW-151F FW/ AUX FEED Flow ColliROL VALVE 6.48-55,7.65-34,44 SFGB 735 AUX FIED Pt#F 5R 17 OPEN THROT YE5 RE-21HF,6.24-65 MCCI-E5 SK AJ A 4115 N/A 00A MDV-FW-160 FW/FW-P-4 DISCMARGE 150LAil0N 150 6.24-383 TROS 693 BASEMENT 9 PtSF R CLO5ED CLO5ED NO RE-21MF MCCI-43 SK 3J A VALVE 4116 A ORA lev-RW-103A RW/*A'KADER W FLOW TO RECIRC 6.48-32,33 AXLB 722 COL K $R CLOSED GPEN YES RE-21LA,6.24-12 ECI-E3 8K B A SPRAY 8 4117 0 08A MOV-RW-1038 RW/*A'NEADER RW FLOW TO RECIRC 6.48-32,33 AILS 722 COL K $R CLOSED GPEN YES RE-21LA,6.24-12 MCC1-E4 BK B A SPRAY 8 4118 N/A 20 FR-MS-478 FW/RC-E-1A LEVEL RECORDER Vil 1.12-25 SRVB 735 CONT RM 88-C 5t ON ON YES RE-22Z VITAL BUS 2 A 4119 N/A 20 FR -MS-488 FW/RC-E-18 LEVEL RECORDER Vil 1.12-25 SRVO 735 CONT RM 88-C 5R ON ON YE5 RE-22AA VITAL SUS 2 A 4120 N/A 20 FR-MS-498 FW/RC-E-IC LEVEL RECORDER Vil 1.12-25 SRVB 735 CONI RM 88-C 5R ON ON M5 RE-22AB VliAL BUS 3 A 4121A A 18 Li-FW-474 FW/RC-E-1A NARROW RAKE LEVEL 150 6.24-3394 RK-It RCBX 718 AfstlLUS COL 16 5 R ON ON YES RE-22W VITAL BUS 1 A TRANSMITTER 41218 A 20 LI-N-474 FW/RC-E-1A NARROW RAEE LEVEL VII 1.12-25 1RVB 735 CONT RM VB-C 5R ON ON YES RE-22W OliAL BUS I A IEICATOR CERTIFICATION: The liformatlee identifying the equipment required to bring the plant to a safe shutdeun tendittee on this Safe Shutdown Etralpment List (SSEL) is,13 the best of our knowledge and belief, corrett and accurate._,,10ne er more signatures of Systees or Operattens Engineers)

                                               -)         r-b         E Q R_1_6 / EEINEER                N'%) IJ2A A.A JL                              N 7 ~7 9 Prl t er Type Name/11tle                               Signature                                      Date r SL~            / mimt Prl t er Type Name/iltle 04 A'JS.  ~

nIn'rr

                                                   " 5M Pature '                                     ITate

v v v Page lie.12 BEAVER VALLEY POWER STATION talli 1 Report Date/itee: 12-20-95 / 10:24:14 CIsro$lTE SAFE SIIUf00181 EqulPIIENT LIST (15EL) 528 ISIVIDUAL PLAffi CopFONENTS LI3 EqulP SYSTEM / EQUIPMENT < EQUIPMENT LOCATION - - -> <-- CP. ST. --> POWER SIFFORillE SYS. req'D IllTERColelECTIONS REG. W. TRAlti CLASS IWWtt MD. DESCRIPTION Dwg. fle./Rev./ Zone Bullding F ir.Elv. Re. er Rew/ Col. 50RT WIES Normal Des' red REqD7 IRC. W./REW. 8 SIFPORTING CIBFMilT5155UE (1) (2) (3) (4) (5) (6) (7) (4) (9) (10) (11) (12) (13) (14) (15) (16) (17) 4122A B 18 ti-FN-475 FW/RC-E-1A NARROW RAIEE LEWL 150 6.24-3394, RK-1B RCOX 718 Af0AJLUS COL 16 5 R 0 18 ON VES RE-22W VITAL BUS 2 A TRAfl981TTER 41228 8 20 LI-FW-475 FW/RC-E-1*. IIARROW RAfEE LEVEL Vil 1.12-25 SRYB 735 CONT RM VB-C 5R ON 0 11 VE5 RE-22W VliAL BUS 2 A IWICATOR 41234 4 18 LT-N-476 FW/RC-E-IA IIARROW RAfEE LEVEL ISO 6.24-3085, RK-It RC81 718 AfstfLUS COL 15 5 R ON ON VE5 RE-22Z VliAL BUS 3 A TRANSMITTER 4123 A 20 LI-FW-476 FW/EC-E-1A IIARROW RANGE LEVEL VII 1.12-25 SRVB J35 CONI RM VB-C 5R ON CII YES RE-22Z VITAL BUS 3 A IMICATOR 4124A A 18 Li-IW-484 FW/IIC-E-18 IIARROW RAfEE LEVEL 150 6.24-3MI, RC8X 738 AfeeJLUS COL 9 5R ON ON VE5 RE-22X VliAL BUS 1 A TRAN5NiiTER RK-1A, IF 41248 A 20 LI-FW-444 FW/RC-E-18 flARit0W RAfEE LEVEL VII 1.12-25 SRV8 735 CONT RM V8-C 5I ON ON VE5 RE-22X VITAL BUS 1 A IWICATOR 4125A B 18 li-FW-485 FW/RC-E-It 114RROW RANCE LEVEL ISO 6.24-3363, RCBI 738 Af0RJLUS COL 9 5R ON ON VE5 RE-22X VITAL BUS 2 A TRAll9itTTER RK-IA,IF 41258 8 20 LI-FW-485 FW/RC-E-18 leutROW RAfEi LEVEL Vil 1.12-25 SRVB 735 CONT RM V8-C 5R 04 ON VES RE-221 VITAL BUS 2 A IWICATOR k 4126A A 18 LT-N-486 FW/RC-E-lO flARROW RAfEE LEVEL 150 6.24-3M2, RC8X 718 AleRJLUS COL 9 5R ON DN VES RE-22AA VITAL BUS 3 A TRAfl5NITTER RK IA, IF 41268 A 20 LI-FW-486 FW/RC-E-lO IIARROW RAfEE LEVEL VII 1.12-25 SRVB 735 CONI RM VG-C 5R ON 0 18 YE5 RE-22AA VITAL BUS 3 A IWICATOR 4127A A 18 LI-FW-494 W/RC-E-IC llARROW RANGE LEVEL OWG RK-18. RK-60 RCBX TIS AfstJLUS COL 5 5R ON ON VE5 RE-22V VliAL BUS 1 A TRAfl91 LITER 41278 A 20 ti-FW-494 FW/RC-E-IC IIARROW RANGE LEVEL VII 1.12-25 SRVB 735 CONT Ril VB-C 5R ON 0 18 YES RE-22V VITAL BUS 1 A IWICATOR 4128A B 18 LT-FW-495 FW/RC-E-IC ltARROM RANGE LEVEL ISO 6.24-3364 RCBI 718 Af0RJLUS COL 5 5R ON ON VES RE-22V VITAL BUS 2 A TRANSMITi[R RK-18, IF 41288 8 20 LI-FW-495 FW/RC-E-It IIARROW RAIEE LEVEL VII 1.12-25 SRVB 735 CONT RM V8-C 1R ON ON VES RE-22Y VITAL BUS 2 A IWICATOR 4129A A 18 LT-FW-4% FW/RC-E-lC NARROW RAfEE LEVEL ISO 6.24-3885, RK-18 RCBX 718 Af8EJLUS COL 4 5R ON 0 11 VE5 RE-22AB VITAL BUS 3 A TRAfl5NITTER CERilFICATI0ll: The 12 formation Identifying the equipment required to bring the plant to a safe shutdeun conditlen oc this Safe Shutdown Equipment List (15EL) is,13 the best of our knowledge and belief, correct and accurate. (One or more signatures of Systems or Operations Engineers) d b MllI / ENGINEER JL%(R 12!27 ( PrLt or Type Name/iltle 51gnature Date D/,.s / ENRf1EETR hd[, M.ddhr Prht or Type Name/iltle " FijE4ture Date

(h o G (G Page D.13 BEAVER VAluV POKR STAil0N 19!!T I Report Date/Ilse: 12-20-95 / 10:24:14 COWOSITE SAFE SMUTDONN Equ!PMENT LIST ($5EL) 528 IWlVIguAL PLANT COWONENTS EqulPMENT LOCATION -----> <-- CP, ST. --> PONER $WPORilNG $YS. req'O INTERColelEtil0N5 REG. Ll3 EqulP SYSTEM /EQUIPIENT < Dug. No./Rev./Zene Building F tr.Elv. Rs. or tow /Cel. Sati leTES Ilernal Destred REqD7 DNG. W./REV. & StrPORilNG CtpFONENTS ISSUE W. TRAIM CLA55 MARK NO. DESCRIPTION (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 41298 A 20 LI-fW-496 FW/RC-E-lC llNtit0N RANGE LEVEL VII 1.12-25 SRVE 735 CONT RM VB-C $R ON ON YES RE-22AB VITAL BUS 3 A IWICATM 4201A A 19 1RS-RC-413 RC/ LOOP 1A MOT LEC RE11$iANCE VII 7.41-33 RCII 718 EL 732 $R 19 ON ON YES RE-229N VITAL SUS 1 A i[WERATWE DETECTOR 4202 8 19 TRS-RC-410 RC/ LOOP 1A COLD LEC RESISTANCE ~Vil 7.41-33 RCB1 718 El 732 5R 19 ON DN YES RE-229P VITAL BUS 2 A TDPERATWE DETECTOR 4202A A 19 TRE-RC-423 RC/ LOOP 18 MOT LEC RESI3 FAKE Vil 7.41-33 RC8X 718 El 732 $R 19 ON ON YES RE-228N VliAL BUS I A TEWERATURE DETECTOR 42025 8 19 TRS-RC-420 RC/ LOOP 18 COLD LEC RE115 FAKE VII 7.41-33 RCBI 718 El 732 1R 19 ON ON YE5 RE-22BP VITAL BU5 2 A TERERAinRIE DETECTOR 4203A A 19 TRS-RC-433 RC/ LOOP IC HOT LEC RE515fANCE Vil 7.41-33 RCBI 718 El 732 5R 19 ON ON YES RE-229N VITAL BUS 1 A TERERATURE DETECTOR 4203 8 19 IRB-RC-430 RC/ LOOP IC COLD LEC RESISTANCE Vil 7.41-33 RC81 718 EL 732 5R 19 ON 04 YES RE-22SP VliAL BUS 2 A TEWERATURE DETECTOR 42C3C 5 20 TR-RC-410 RC/ REACTOR COOLANT COLD LEG 3 PEN $RVB 735 CONT RM V8-A R ON ON YE5 RE-220P VliAL SUS 2 A RECORDER 4203 A 20 TR-RC-413 RC/ REACTOR C00UINT NOT LEG 3 PEN 5tVE 735 CONT RN V8 R ON ON YES RE-2204 VITAL BUS I A RECORDER 4204 A 07 KV 4fi-104 MS/REstouAL NEAT RELEASE ISO 6.24-6 SFGB 752 MSVH 5R 10 CLOSED GPEN YES RE-220R VITBUS I OK 1-7 A 4205 A 07 PCV4tS-101A MS/A LOOP ATM STEAN DipF 150 6.24-6 $FGB 752 MSVH $ 10 CLOSED GPEN YES RE-21JD VliAL BUS 2 A 4205C A 000 50VJfS-101A MS/(PCV-lMS-101A) CONTROL SOL [NDID RK-8A SFG8 751 M5VM $R DEERRG DEEMERG le RE-21JD PHL-DC-3 BK 8-14 A 42050 A 008 50V MS-101A4 M5/(PCV-1MS-101A) CONTROL 50LEMID RK-8A $FGB 751 M5VM $R DEENERG DEEMERG Im RE-21JD PNL-DC-3 BK 8-23 A 4205E A 18 PSM-101A MS/ATMDSPflERE 5 TEAM Dlff 1.C. IA 150 6.24-2 5FG8 768 MSVN $ ENERG ENERG YES RE-flJD PNL-DC-3 BK 8-14 A 4206 5 07 PCVM-1018 MS/B LOOP ATM STEAM Dlff 150 6.24-6 SFG8 751 MSVN 1 10 CLOSED GPEN YES RE-21JD VITAL BUS 2 A 4206C B 008 50VM-1018 MS/(PCV-lMS-10lt) CONTROL SOLENDID RK-8A SIG8 751 MSVN 5R DEEMERG DEENERG 10 RE-212 PNL-DC-2 BK 8-14 A 4206D B 098 50VM-10184 MS/(PCV-lMS-1018) CONTROL 50LENDID RK-8A STGB 751 M5VH $k DEENERG DEEllERG 10 RE-21JD PNL-DC-2 8K 8-23 A 4206E I 18 PS M -101B MS/ ATMOSPHERE STEAM Dtpf 5.G.18 150 6.24-2 SFG8 768 MSVH 5 DIERG ENERG YES .E-21JD PNL-DC-2 OK 8-14 A 4207 8 07 PCVM-101C MS/C LOOP ATM STEAM Dlff 150 6.24-6 SFG8 752 MSVH 1 10 CLOSED :*EN YES RE-21JD VITAL SUS 2 A CEtilFICAll0N: The Icformation identifying the equiparat required to bring the plant to a safe shutdown condittoa en this Safe Shutdown Equipment List (SSEL) Is, t3 the best of our knowledge and belief, correct and accurate. (One or mere signatures of systems er Operations Engineers) 8 N9816 / ENGINEER m) RAAR t 7 [2 7 i Prl.t er Type Name/Iltle 5ignature Date 7M# / BEINED Prlit er Type Name/ Title hf_/ re- // - W Date 6' 54$rature '

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D D d Page b.15 BEAVER VALLEY POER STAil0N lAlli 1 Report Date/itee: 12-20-95 / 10:24:14 CtpFOSITE 5AFE $NUTD0lAl EqulMNT LIST (55EL) 528 IslV10ML PLMi CIBFONENT5 Ll'I EqulP SYSTEM / EQUIPMENT < EQUIPMENT LOCAil0N ---> <-- OP. ST. --> POER SLFPORTING SYS. REl'D INTERCOMECTIONS REC.

m. TRAIN class MARK 18. DESCRIPildN Dug. Ite./Rev./Zene Building F tr.Elv. Es. er Reu/Cel. SORT WTE5 Nereal Desired REqD7 ONG. M./REV. & 54FPORTIE CtBF0ENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17)

SIl A 06 ldt-P-1A RW/ RIVER MfER Pl8F 2.42-14,16,23 INTS 705 A CISICLE 5R ON ON YES RE-flKU.K-32E, BUS 1AE BK E10 A 32J,150 6.24-801, RP-4K, 4L 5101C A 09 V5-F-57A V5/INTME STRutitRE CtBICLE l'1 RS-2E INTS 725 A CUBICtf 5R ON ON VES RE-21sti MCCl-El 8K B A StFPLV FM 5103 A 0 V5-D-57Al V5/IETAKE STRutitRE OUTSIDE AIR R9-FE RS-26A & C INTS 725 A CUBICLE 5R CLOSED OPEN YES RE-219tf MCCI-El OK 8 A DNFER 510lf A 0 V5-D-57A2 VS/ INTAKE STRUtitRE RECit AIR RB-2E R$-26A & C INTS 725 A CUBICLE 5R CLOSED GPEN VES RE-flief MCCI-El BK 8 A DNFER 5102 B 06 WR-P-18 RW/ RIVER WATER PtMP 2.42-14,16.23 INTS 705 B CUBICLE 5R OFF ON YE5 RE-flew,RC-32E, BUS 10F BK F10 A 32J, ISO 6.24-801, RP-4K, 4L 5102C B 09 VS-F-578 V5/ INTAKE STRUCTtRE CtBICLE R2 RS-2E INTS 725 t CUBICLE 5R ON ON YE5 RE-21tti MCCI-E2 BK 8 A SLFPLY FM 5102D 8 0 VS-D-57tl V5/ INTAKE STRUCitRE OUTSIDE AIR RS-2E RS-26A & C INTS 725 8 CISICLE 5R Closed GPEN YES RE-flief MCCI-E2 9K P A DNFER 5102E B 0 V5-D-5782 VS/ INTAKE siRUCTLRE RECIR AIR RS-2E RS-26A & C INT 5 725 8 CISICLE 5R CLOSED GPEN YES RE-2itti MCCI-E2 8K 8 A ONFER 5103 A/S 06 WR-P-1C RW/ RIVER WATER Pt9F 2.42-14,16,23 INTS 705 C CUBICLE 5R OFF ON YES RE-21KX,RC-32E, BUS IAE OR IDF S A 32J, ISO 6.24-001, RP-4K, 4L

                                 $10X A/B 09                               V5-F-57C       V5/ INTAKE STRUCTLRE CISICLE R3      RB-2E                              INTS    725        C CUBICLE    5R        ON       ON       YES RE-21fti         fECI-El/2 8K E      A SUPPLY FM 5101 A/B 0                                V5-0-57C1      V5/ INTAKE STRLKTURE OUISIDE AIR     RB-2E RS-26A & C                   INTS    725        C CtBICLE    5R        CLOSED GPEN YES RE-21tti               MCCI-El/2 BK E      A DNFER 5103E A/B 0                               VS-D-57C2      V5/ INTAKE STRUCTURE RECIR AIR       RS-2E RS-26A 1 C                   INTS    725        C CUBICLE    5R        CLOSED GPEN       YE5 RE-21ftf         MCCl-El/2 8K E      A DNFER 5104 8                             GBA MOV-RW-102Al      RW/Ptfr DISCHARGE 150                6.48-22,23                         INTS    705        A CUBICLE    5R        CLOSED GPEN YE5 RE-21KZ,150            MCCl-El BK D        A 6.24-801, RP-4L CERTIFICATION:

The IJersatten identifying the equipment required to bring the plant to a safe shutdeun tendition en this Safe Shutdown Equipment list (Sitt) terrect and accurate. (One or mere signatures of Systems or Operattens Engineers) is, ti the best of our knowledge and belief,& Fe n /n/w prl t er Type Name/iltlet- / omiR Signature Date Ud# Prlit er Type Name/iltle

                                                                           / ENfriMEft                   N1b
                                                                                                         *' 51ghhture '

Mb Date

f) r) / 4%) (v/ (V i , Page No.16 BEAVER VALLEY POWER STAil0N tlN!! ! Report Date/ilee: 12-20-95 / 10:24:14 CWF051TE SAFE $1RH00MN EQUIPMNT tt$i ($5EL) 52B IslVIOUAL PLANT CWF01ENTS SYSTEM / EQUIPMENT < EQUIPMENT LOCAL!0N ----> <- OP. ST. --> POWER SlFPORilNG SYS. req'D INTERC018ECil0NS REG. t!!! EQUIP W. TRAIN CLASS MARK m. DESCRIPi!ON Dwg. No./Rev./Zene Building Fir.Elv. Re. er Rew/Cel. SORT Mits Normal Desired req 07 OWG. M./REV. & StFPORTING CIDFONENTS 155UE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5105 A GBA MOV-N-102A2 RW/PtBF DISCHARGE 150 6.48-22.23 INis 705 A CtBICLE 5B CLOSED GPEN YES RE-21KZ,150 K Cl-El BK C A 6.24-801, RP-4L 5in B OBA NOV-RW-10281 RW/Ptpr DISCHARGE 150 6.48-22,23 INTS 705 I CIAICLE $R CLOSED GPEN YES RE-21KZ, ISO NCCl-E2 BK D A 6.24-801, RP-4L 5107 A GBA MOV-RW-102B2 RW/Ptfr DISCHARGE 150 6.48-22.23 INTS 705 B CURICLE $R CLOSED GPEN YES RE-21KZ, ISO MCCl-E2 BK G A 6.24-801, RP-4L 51'3 B OBA MOV-RW-102C1 RW/Pter DISCHARGE 150 6.48-22,23 INTS 705 C CtRICLE $R CLOSED OPEN YES RE-flEZ, ISO kcl-E2 BK H A 614-801 RP-4L 5109 A ORA, MOV-RW-102C2 RW/Plar DISCMARGE l$0 6.48-22,23 INTS 705 C CUBICLE $R CLOSED GPEN YE5 RE-21KZ,150 MCCI-El BK H A 6.24-801, RP-4L 5110 A 07 PCV-RW-130A RW/5EAL WATER PCV FOR RW Pt#F 130 6.24-3345 INTS 705 A CtBICLE $ CLOSED OPEN NO 130 6.24-1345 N/A A 5111 B 07 PCV-RW-1308 RW/ SEAL WATER PCV FOR RW PtpF 150 6.24-3346 INTS 705 B CtRICLE S CLOSED OPEN m ISO 6.24-1346 N/A A 5112 A/B 07 PCV-RW-130C RW/ SEAL WATER PCV FOR N Pt99 ISO 6.24-3347 INTS 705 C CtBICLE 5 CLOSED OPEN W 150 6.24-3347 N/A A 5113 N/A 21 CH-E-7A CH/ CHARGING Pt99 MEAT EXCN Vil 2.32-18 AXtB 722 CH-P-1A CIS S N/A N/A E N/A N/A A 5114 N/A 21 CN-E-78 CH/CNARGING Ptff HEAT EXCH Vil 2.32-18 AXLB 722 CN-P-18 CtB $ N/A N/A NO N/A N/A A 5115 N/A 21 CM-t-7C CN/ CHARGING Pt99 HEAT EXCN Vil 2.32-1B AXtB 722 CH-P-IC CtB $ N/A N/A NO N/A N/A A 5116 WA 21 CC-E-1A CC/CCR MEAT EXCN 4.ll-10,RC-24K,RV-76 AILS 735 N/A $ N/A N/A ND 110 N/A A A,8 6.24-68,RM-2A 5117 N/A 21 CC-E-1B CC/CCR HEAT EXCH 4.ll-10,RC-24K RV-76 AXtB 735 N/A 5 N/A II/A NO ISO N/A A A,8 6.24-68,RM-2A s 5118 N/A 21 CC-E-IC CC/CCR HEAT EXCH 4.II-10,RC-24K RV-76 AXLI 735 N/A $ N/A N/A NO l$0 N/A A A,B 6.24-68,N-2A 5119 8 OBA MOV-RW-106A RW/[CR lli EXCH ISOLATION 6.48-51,52 AXLR 722 N/A $R 18 OPEN CLOSED YES RE-21tA,6.24-68 MCCI-E4 BK P A 5120 B OBA MOV-RW-106B RW/CCR HT EXCH ISOLAi!0N ISO 6.24-68 AXLB 722 N/A R OPEN OPEN m RE-21tA MCCl-E4 BK 0 A 5111 A GBA MOV-RW-ll3A N/ DIESEL GEN COOLING ISO 150 6.24-159 PG Ptar 722 PC Ptfr 5R CLOSED OPEN VES RE-21LA MCCI-E3 BK H A 5122 A GBA MOV RW-ll30 RW/Di[5EL GEN COOLING ISO 150 6.24-160 PG PtDF 722 PG Pt99 5t CLOSED OPEN YE5 RE-21tA ECl-E7 BK J A 5123 I OBA MOV-RW-Il3C RW/OlESEL GEN COOLING ISO 150 6.24-159 PG Ptif 722 PC Pt99 1R CLOSED OPEN YE1 RE-21LA MCCl-E8 BK M A CEtilTICATION: The liformatlos identifylng the equipment required to bring the plant to a safe shutdown condities en tbls $afe Shutdown Equipment List ($1EL) is, to the best of our knowledge and belief, correct and accurate. (One er more signatures of Systees or Operations Engineers) O feR R 4 / ENGINEER Prlit er Type Name/ Title Signature Q t 1!27 Date

                                                                                                                                                                           !9i NdA               / flCTIER                                                                     dea [,[                                      M                 W PrLL or Type Name/11tle                                                  " SignaRbre                                                                      'Date

r t V V t Page No.17 BEAVER VALLEY POWER STATION 191111 Report Date/itee: 12-20-95 / 10:24:14 CipFOSITE SAFE 5NUTOIRAI EqulPIENT LIST (S5EL) 528 le!VIDUAL PLAlfi CIBFCIENTS I LINE EOUIP 5YSTEM/ESUIPMENT c EQUIPENT LOCATIoll ----> <- OP. $1. --> PIRIER SIFPIRTIE SY1. RE4'D INTERCINSECTiell5 REG.

18. TRAIN CLAS$ telRK 10. DEStalPiloll Dug. Ilo./Rev./ Zone Building F tr.Elv. Re. er Rom / Col. 50RI MTES Normal Desired req 07 OMG. le./REV. 8 SIFFORTIE CIBF01ENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5124 5 otA tev-N-1121 N/ DIESEL GEN COOLIE ISO 150 6.24-160 DGBX 735 DIESEL GEN 12 5t CLOSED OPEN YE1 RE-21tA ECl-E8 BK J A

, 5125 4 004 MDV-N-Il4A N/CCR NT EXCH 150LATI0ll ISO 6.24-68 AXtt 722 N/A $R 18 OPEN CLOSED VES RE-21tA ECl-E5 OK D A 5126 A GBA scV-N-1145 N CCR HT EXCN isotATION 150 6.24-68 AXLI 722 N/A R OPEN IFEN NO RE-21LA MCCI-E3 BK AC A 004 lev-RW-Il6 150 6.24-64 AXtB 722 N/A Ct05ED CLOSED NO RE-21KZ MCCI-E3 BK AD A , 5127 A N/5TRAIIIER 150LAil0N R I 5128 5 00A lev-N-ll? N/5ftAllER 150LAi!0ll l$0 6.24-68 AXLB 722 N/A R CLOSED CLOSED le RE-21KZ ECI-E3 IK G A 5129 N/A 21 EE-E-IA EE/ DIE 5EL GEN COOLIE NT EXCH !!0 6.24-159, RM-104 DGBX 735 DIESEL CEN 11 1 N/A N/A la N/A N/A A 5130 N/A 21 EE-E-Il EE/ DIESEL GEN COOLIE HT EXCN 150 6.24-160, RM-10A DGBX 735 OIESEL GEN R2 $ II/A II/A 10 N/A N/A A 5131 A 004 MDV-RW-Il6A RW/ AUX N Plpe StFPLY TO A N NOR ISO 6.24-521 YARD 730 N VALVE PIT R CLO5ED CLOSED le RE-flEZ kcl-E7 BK Y A REACTOR PLANT 5132 8 05A lev-RW-Il68 RW/ AUX N Pl8F 5tFPLY TO 8 N NDR 150 6.24-521 YARD 730 W VALVE Pli R CLOSED CLOSED 110 RE-21KZ McCl-E8 BK Z A REACTOR PLAlli 5133 A 08A MOV-RW-103A RW/'A'14EADER N FLOW 10 RECIRC 6.48-32.33 AXLB 722 COL K 5R CLOSED GPEN YES RE-21tA,6.24-12 MCCI-E3 SK B A SPRAY 8 5133C A/B ces DV-FP-9 FP/ TOWER CNARC0AL VENT FILTER RB-16C STOR 735 LUNCll ROON R CLOSED CLOSED 10 RE-21GV PML-DC-4 A DELUGE VALVE 5134 3 084 MOV-RW-1035 RF/*A'NEADER RW FLOW TO RECIRC 6.48-32,33 AXLB 722 COL K $R CLO5ED GPEN YES RE-21tA,6.24-12 MCCI-E4 BK I A SPRAY 8 5135 A 00A MOV-RW-10K RW/'B' NDR N FLOW 10 RECIRC SPRAV 150 6.24-68 AXLt 722 N/A R CLOSED CLOSED NO RE-21LA kcl-E3 BC C A 5136 5 00A MOV-RW-103D N/'B' NDR RW FLOW 10 RECIRC SPRAY 150 6.24-68 AXtt 722 II/A R CLOSED CLOSED ND RE-21LA MCC1-E4 BK C A 5201 A 09 VS-F-55A VS/EMERG SWITCEEAR SUPPLY Fall DWG RB-17L SRVE 725 CABLE MEZZ 5R 12 0FF Oil YES RE-21MZ ECI-E9 BK P A 5201C A 18 IS-HV-55A VS/TDF SWITCH FOR V5-F-55A DWG RS-17G $RVB 713 SW MRG SER $ ENERG ENERC YE5 RE-flMZ A 5202 8 09 VS-F-558 VS/EMERG SilliCEEAR SUPPtY FAN DWG R8-17L SRVE 725 CABLE MEZZ sR 12 0FF ON YES RE-21MZ MCCl-E10 BK X A 5202C B 18 15-HV-558 VS/TDF SWITCH FOR V5-F-558 DWG Re-17G 5tV8 713 SW EMERG SER 5 ENERG MRG YES RE-flMZ A j 5203 A 09 VS-F-16A V5/DERC SWITCNGEAR EXNAUST Fall DWG RS-17L $RVB 725 CABLE MEZZ $R 12 0 18 ON YES RE-flMZ McCl-E9 BK AF A 5204 5 09 VS-F-168 VS/EMERG SWITCEEAR EXilAUST Fall DWG RS-17L SRVE 725 CABLE MEZZ $R 12 0FF ON YES RE-21MZ kcl-E10 BK AC A 5205 A 0 V5-D-16A VS/EERG $UITCEEAR EXNAUST DlWFER OWG R8-17L SRv8 725 CAttE MEZZ $R OPDI OPEN ND RE-flMZ MCCI-E9 BK AF A CERTIFICAi10N: Ibe liformation identifying the equipment required to bring the plant to a safe shutdeun condition on this safe Shutdown Equipment List (55EL) is, ta the best of our knowledge and belief, correct and accurate.,(One er more signatures of Systees or Operattens Engineers) b bQ R th / ENGINEER Prht er Type Name/iltle n3 .L e 5tgaature i2!27 Date f T.$$ & / EN9tNEtR ll /& W _ Priat or Type Name/iltle " /T19Aature Date

O O O Page Nr.18 8P.YER VALLEV PONER stall 0N lAlli 1 COlF0$ lit SAFE SNUTOIRAI EqulMNT LIST (SSEL) Report Date/itee: 12-20-95 / 10:24:14 528 IMIVIOUAL PLAlli CIBFONENTS SYSTEM /EqulMNT < EqulMNT LOCAT10N -----> <-- OP. ST. --> PERIER SWPORTING SYS. REQ'8 INTERCIBSECiloll5 REG. LIU EQUIP thsg. No./Rev./ Zone Bulldlag Fir.Elv. Re. or Rom /Cel. SORT NOTES Normal Desired REqD7 ONG. IRI./REV. 8 SIPPORTING CIBF01ENTS ISSUE NO. TRAIN CLASS IIUlK NO. DESCRIPil0N (1) (2) (3) (4) (5) (6) (7) (0) (9) (10) (11) (12) (13) (14) (15) (16) (17) SRVE 725 CABLE MEZZ $R CLOSED GPEN YES RE-21MZ MCCI-E10 SK AC A 5206 8 0 VS-D-168 VS/EMERG SNITCMGEAR EXNAUST DMFER 1 RIG RS-17L 768 BY FILTER BAlet R OPEN OPfil M RE-21MS MCCI-E3 BK V A 5207 A 00A VS-D-4-1A VSMIN FILTER BM IPSTREAM 8700-RS-811 (L 1/2-10 AXLB BYPASS ISOLATION DMFER 1/2) VSMIN FILTER BAlet IFSTREMI 8700-RS-8N (L 1/2-10 AXLB 768 BY FILLER BAlet R OPEN OPEN NO RE-21MS MCCI-E4 BK V A 5208 8 00A VS-D-4-It BVPASS 150LAflell DMFER 1/2) VSMlli FILTER BAlet LEAK 8700-RS-8H (K AXLt 768 BY FILTER BAlet R CLOSED CLOSED NO RE-flMS PE-AC-El BK 3 A 5209 A 00A VS-D-4-2A COLLECTION TRAIN 8 IN ISOL DAM I/2-10) AXLR 768 BY FILTER BAlet R CLOSED CLOSED NO RE-21M5 PE-AC-E2 IK 2 A 5210 5 08A VS-D-4-28 VSMIN FILTER BAIOC LEAK 8700-RS-811 (K-10) COLLECilell TRAIN A IN 150L DMI AILB 722 BLEMER CIRICLE R CLOSED CLOSED NO RE-21MT MCCl-E4 BK N A 5211 B ORA VS-D-4-38 VS/CMG Pl#F CUBICLE NDRll EINAUST 8700-R8-88 (J-10 DMFER . 1/2)t4-5212 A 08A E-0-4-4A WS/CHG PIDF CutlCLE EMER EXMAUST 8700-R8-8N (K 1/2-9 AXLB 768 BY BATCM TAlet R OPEN OPEN M RE-21MS Pill-AC-Il BK 3 A DMFER 3/8) 5213 8 dea VS-D-4-48 VS/CMG Pl#F Cl81LCE EMER EXMAUST 8700-R8-8N (K1/2-9 AXLR 768 BY SATCH TAlet R OPLN OPEN NO RE-21MS PE-AC-E2 BK 2 A DMFER 3/8) AILS 768 AT Fall 5R CLOSED GPEN YES RE-21MS N/A A 5214 A 0 VS-D-4-7A VS/ LEAK COLL EXHAUST FAN 8A 8700-RS-8G (G SUCTICII 150LATICII DMFER 1/2-11) 768 $ CLOSED GPEN NO RE-21MS N/A A 5215 8 0 VS-D-4-78 VS/ LEAK COLL EXHAUST Fall 4A 8700-RS-8G (G AXLB NORTH NALL DISCHARGE BACKTLON DNPER 1/2-11) 5216 A 0 VS-D-4-8A VS/ LEAK COLL EXHAUST Fall 48 8700-RS-8G (G AXLB 768 At Fall SR CLOSED GPEN VES RE-flMS N/A A SUCTION ISOLATION DNFER 1/2-12) AXLt 768 $ CLOSED GPEN NO RE-21MS N/A A 5217 8 0 VS-D-4-88 VS/ LEAK COLL EXHAUST FAN 48 8700-RS-8G (G NDRTH WALL DISCHARGE 8ACKFLON DMFER 1/2-12) 5218 A/8 08A VS-D-4-94 VSMIN FILTER SAlet [lVS-FL-4,5,6] 8700-RS-8N (K-10 AXLB 768 BY FILTER 8Alet R OPEN OPEN YES RE-21MS PNL-AC-Il it 1 A IN DMFER 1/4) 5219 A/S OSA VS -D-4 -9B VSMIN FILTER BAlet [lVS-FL-4,5:6] 8700-Re-8N (K-10 AILB 768 BY FILTER SAlet R OPEN OPEN YES RE-21M5 PR-AC-Il BK 1 A OUT DMFER 7/8) 5220 A/S 09A VS-D-4-104 V5 MIN FILTER BAlet [lVS-FL-7,8,9] 8700-RB-8J SECT AILB 768 BY FILIER BAlet R CLOSED CLO5ED YES RE-21MS PR-AC-Il BK 1 A IN OMPER 17-17 5221 A/S ORA VS-D-4-108 VSMIN FILTER BAlec [lVS-FL-7,8:9] 8700-R8-8J SECT AXLB 768 BY FILTER BAlet R CLOSED CLOSED YES RE-21MS PIE-AC-Il BK 1 A OUT DMFER 17-17 CERilFICAil0N: The 11 formation identifying the equipment required to bring the plant to a safe shutdeun condition on this Safe Shutdeun Equipment List (SSEL) Is, ts the best of our knowledge and belief, correct and accurate._(One er more signatures of Systees or Operations Cagineers) R r e /E,1GmR Print er Typeramellitle AFM 5tgaature u/n4c Date T[/e / EMetNEg hf, N M r V Prht or Type Name/Iltle Kl9tature Date

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1 (p) _/ v Page No. 20 SEAVER VALLEY PONER STAi!ON Ifill 1 Report Date/Tlee: 12-20-95 / 10:24:14 CGPOSITE SAFE INUTDetel EQUIPENT Lisi ($$EL) 528 ISIVIDUAL PLANT CIDFONENTS LI'.I EQUIP $YSTEM/ EQUIPMENT < EQUIPMENT LOCAT10N -----> <-- CP. ST. --> PONER SlFPotilNG $V5. RE4'D INTERC0181ECTIONS REG. NO. TRAIN CLASS MARK m. DESCRIPTION Dwg. No./Rev./ Zone Sulldlag Fir.Elv. Es. er tow / Col. S0ti IGTE5 Noreal Destred RE407 DMG. ID./REV. & SIMORTING CSFONENTS !$5UE (1) (2) (1) (4) (5) (6) (7) (8) (3) (10) (11) (12) (13) (14) (15) (16) (17) 5237 A 09 V5-F-404 V5/CONit0L R091 RETWN AIR FAff DMG RS-17J, R8-17K StV8 713 CR WNT 5t ON ON VES RE-21MJ MCCi-E9 8K C A 5238 8 09 v5-F-40B VS/ CONTROL Romi RETWN AIR Fall DMG RS-17J RS-17K StVB 713 CR VENT $t CN ON VES RE-211L) ECl-E10 BK C A 5239 A/S 0 V5-AD-7 VS/vs-F-40A SUCTION DOFER 5tVB 713 CR VENT $t 13 OPEN OPEN NO RE-21M kcl-E9 OK C A 5240 A/S 0 VS-AD-8 V5/VS-F-408 $UCTION DNFER StV8 713 CR VENT $t 13 OPEN OPEN N0 RE-21M ECl-E10 OK C A 5241 4/5 0 VS-AD-9 V5/VS-F-404 DISCNARGE DNFER StVB 713 CR VENT $R 13 OPEN OPEN le RE-21NJ kcl-E9 8K C A 5242 A/B 0 V5-AD-10 V5/V5-F-405 DISCHARGE DNFER ONG #8-17J. RS-17K StVB 713 CR VENT $E 13 OPEN OPEN NO RE-flpt) MCCI-E10 BK C A 5243 A/B 08A VS-D-40-1A V5/CONit0L Roel AIR INTAKE DMFER Vil $tVB 713 CR VENT $R OPEN OPEN NO RE-21E.R8-FD,1 kcl-E9 BK U A 10.1-326,327,328,329 FJ,17K 5244 A/S OBA V5-D-40-18 V5/ CONTROL ROOM AIR INTAKE DNFER VII StV5 713 CR WENT $R OPEN OPEN No RE-21E,R8-20,1 MCCI-E10 BK J A 10.1-326,327,328,329 7J,17K 5245 A/B 08A VS-D-40-lC VS/ CONTROL RM Alt EXHAUST DNFER Vil StVB 713 CR VENT 5t 13 CPEN OPEN NO RE-21ML,tt-20,1 MCCI-E9 OK V A 10.1-326,327,328,329 7J,17K 5246 A/S 08A V5-D-40-ID VS/CONit0L RM Alt EXHAU$f DMFER Vil $tVt 713 CR WNT $t 13 OP(N GPEN NO RE-flE,tt-2D,1 kcl-E10 BK K A 10.1-326,327,328,329 7J,lFK 5247 A/B 07 VS-D-40 IF VS/ MIN OUTSIDE AIR INTAKE DEFER VTI StVS 713 CRWNI 1R 13 OPEN OPEN NO RB-20,17J,17K N/A A 10.1-326,327,328,329 5248 A/S 07 VS-D-40-lG V5/ MAX OUTSIDE Alt INTAKE DMFER VII $tVB 713 CR WNI 12 13 OPEN OPEN No RS-20,17J,17K N/A A 10.1-326,327,328,329 5249 A/B 07 VS-D-40-lH VS/ Alt RECIRC DMFER VTI SRVB 713 CR WNi $t 13 OPEN OPEN NO R8-20,17J,lTK N/A A 10.1-326,327,328,329 5250 A/S 07 V5-D-40-lK VS/ Alt RECIRC 04FER Vil StVB 713 CRWNT $t 13 OPEN OPEN NO RS-2D,17J,17K N/A A 10.1-326,327,328,329 5251 A/B 0F VS-D-40-lM V5/V1-F-404 & B EXMAUST DMFER VTI SRV8 713 CR VCNT $R 13 OPEN OPEli N0 RS-2D,17J,17K N/A A 10.1-326,327,328,329 5252 A/S 0 VS-AD-3 VS/VS-AC-IA Sutil0N DEFER 5tVB 713 CR VENT 5t 13 OPEli CPEN N0 RE-2]MJ N/A A 5253 A/B 0 VS-AD-4 VS/VS-AC-IB SUCil0N DMFER StV8 713 CR VENT $R 13 OPEN OPEN NO RE-21NJ N/A A 5254 A/B 0 VS-AD-5 VS/V5-AC-1A DISCHARGE DMPER 5tV8 713 CR WNT 5t 13 OPEN OPEN N0 RE-21NJ N/A A 5255 A/B 0 VS-AD-6 V5/VS-AC-18 DISCHARGE DAMPER SRVB 713 CR WENT $R 13 OPElf OPEN NO RE 21MJ N/A A CERTIFICAll0N: The 11 formation identifying the equipment required to bring the plant to a safe shutdown tenditlen en this $afe Shutdown Equipment List (55EL) is,13 the best of our knowledge and belief, corrett and accurale. (One or more signatures of Systems r Operations Engineers) k EEA / ENGINEER i ht4 t '2_ 2 ~7 / T Prht er Type ame/iltle Signature Date

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                      %                                                                                          (g                                                                                                 f7 BEAVER VALLEY POWER stall 0N Ifili 1 Page No. 22                                                                            CIBF011TE SAFE $NUTDetAl EqulPENT LIST (SSEL)

Report Date/Tlas: 12-20-95 / 10:24:14 528 ISIV10 MAL PLANT CIBFONENTS

                                                                                                     <          EQUf89ENT LOCATION -- - >
                                                                                                                                                       <-- OP. $T. --> POWER SIFFORTIE Sts. req'D INTERC018ECil0N1 REG.

LIH EqulP SYSTEN/EqulPENT ND. TRAIN CLA$$ M K NO. DESCRIPil04 Dug. Ilo./tev./ Zone Building Fir.Elv. te. er tou/Cel. SORT IOTES Normal Desired req 07 DMG. NO./REV. & SIFFORTIE Cl890ENTS 115UE (6) (7) (8) (9) (10) (II) (12) (13) (14) (15) (16) (IT) (1) (2) (3) (4) (5) DIESEL GEN B1 5t ON ON YES RE-218X MCCI-E8 8K N A 5300D A 12 EE-C-2A EE/ DIESEL GENERAfot 5 FART Alt Vil 2.19-10, RM-104 DG8X 735 CipFRES$0t EE/ DIESEL GEERATOR STARI Alt. VII 2.19-13 RM-10A DG8X 735 DIESEL GEN 82 1E ON ON VES RE-218X McCl-E7 IK i A 5300E B 12 EE-C-18 CofrRE550R VII 2.19-10, RM-10A DGBX 735 DIESEL GEN 82 5t ON ON VES RE-218X McCl-E8 SK i A 5300F 8 12 EE-C-28 EE/ DIESEL GENERATOR START AIR CofFRES$04 EE/Il DIESEL GIIERATOR DWG RM-104 E8X 735 DIESEL GEN 11 $2 0FF ON VES N/A N/A A 521 A 17 EE-EG-1 DGBX 7 35 DIESEL GEN 82 12 0FF ON VES N/A N/A A 5302 8 17 EI-EG-2 EE/B2 DIESEL GENERATOR DMG RM-10A DWG RM-104 DG8X 735 DIE 5EL GEN 82 5t 0FF ON YES RE-21BX MCCI-E7 8K Q A 5~3 A 05 EE-P-IA EE/ FUEL OIL ftANSFER PtDF 735 DIESEL CEN 82 St 0FF ON VES RE-218X McCl-E7 OK t A 5304 A 05 EE-P-18 EE/ FUEL OIL TRANSFER Pt9F DMG RM-104 DG8X DE RM-104 715 DIESEL GEN 81 $R OFF ON YES RE-21BX McCl-E8 8K q A ! 5305 8 05 EE-P-IC EE/ FUEL OIL TRANSFER PISF DG8X t 735 DIESEL GEN 11 5t 0FF ON VES RE-218X MCCI-E8 BK I A ! 5306 8 05 EFcP-lO EE/ FUEL CIL IRAN 5FER FIDF DWG RM-104 DG8X 5307 A 21 EE-TK-1A EEADG FUEL OIL STORAGE TM DMG RP-65A VARD 724 YARD $ N/A N/A NO N/A N/A A ! 5308 8 21 EE-TK-le EEADG FUEL OIL STORAGE IM DWG RP-65A VARD 724 YARD 5 N/A N/A le N/A N/A A I NO N/A I 5309 A 21 EE-iK-24 EEADG FUEL OIL DAY TAE VII 2.19-15,tP-65A DG8X 735 DIESEL GEN B1 1 N/A N/A N/A A 5310 8 21 EE-tK-28 EEADG FUEL OIL DAY TAIEC Vil 2.19-15,tP-65A DGBX 735 DIE 5EL GEN 82 $ N/A N/A NO N/A N/A A 5311 A 21 EE-TK-3A EE/ DIESEL ENGINE STAti Alt TAfst VII 2.19-15,tf-65A DGBX 735 DIE 5EL GEN 81 5 N/A N/A 10 N/A N/A A 5311C A 07 RV-EE-201A EE/3A Alt TAftt REllEF Vil 6.39-109 DG8X 735 DIESEL GEN 11 5 N/A N/A 11 0 N/A N/A A 5312 A 21 EE-TK-38 EE/ DIESEL EEINE STAti Alt TM Vil 2.19-15,tP-65A DGBX 735 DilSEL GEN 81 $ N/A WA NO N/A N/A A 5312C A 07 RV-EE-2018 EE/38 Alt TAftt RELIEF VII 6.39-109 DG8X 735 OlESEL GEN 81 $ N/A WA ND ll/A N/A A 5313 A 21 EE-tK-3C EE/ DIESEL ENGINE START Alt TAE Vil 2.19-15,RP-65A DG8X 735 DIESEL GEN 11 $ N/A N/A 10 N/A N/A A 5313C A 07 RV-EE-201C EE/3C Alt TAlet RELIEF VII 6.39-109 DG8X 735 DIESEL CEN 01 1 N/A N/A NO N/A N/A A 5314 A 21 EE-TK-3D EE/ DIESEL ENGINE START Alt TM VII 2.19-15,tP-65A DG81 735 DIESEL GEN 81 5 N/A N/A NO N/A N/A A 5314C A 07 RV-EE-202A EE/3D AIR TAf8C RELIEF VTI 6.39-109 DG81 735 DIESEL GEN 81 5 N/A II/A le N/A N/A A 5315 A 21 EE-TK-3E EE/ DIESEL EEINE START Alt TAISC Vil 2.19-15,tP-65A DG8X 735 DIE 5EL GEN 81 5 N/A N/A NO N/A N/A A CERTIFICATION: The liformation identifying the equipment required to bring the plant to a safe shutdown tenditten en this Safe Shutoaus Equipment List (15EL) is, ta the best of our kneuledge and belief, correct and accurate. (One er more signatures of Systems or Operations Engineers) E rNIE / ENGINEER em D e ts- 12 27 C Prtot or Type Wiie/iltle Signature Date T / ENGINEER Prtat or fy,*pe Name/iltle k8

                                                      "/ Mgnature
                                                                     .a-                         /> b.7 Date J'

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O O O Page Ms. 23 BEAVER WALLEY PENER STATION IRGIT 1 CtBFOSITE SAFE SNUTDEIRI EqulMNT LIST (15EL) Report Date/Tlee: 12-20-95 / 10:24:14 528 IIBlVIDUAL PLANT CipF0ENT5 EqulP SYSTEM / EQUIPMENT < EQUIPleElli LOCATICII -----> <-- OP. ST. -> PONER SWPORTIE SYS. RE8'D thTERCOISECTIGIIS REG. LIJ NO. TRAIN CLASS MARK IIll DESCRIPTION lbsg. No./Rev./Zene Building F tr.Elv. Re. er Rou/ Col. SORT NOTES lloreal Desired RE407 DE. NO./REV. & SWPORTIIE CerelEllTS 155E (6) (7) (8) (9) (10) (11) (12) (13) (14) (D) (16) (17) (1) (2) (3) (4) (5) 07 RV-EE-2028 EE/3E AIR TM RELIEF Vil 6.39-109 DG81 735 DIESEL Gell 81 5 11/A N/A 10 N/A II/A A 5315C A 5316 A 21 EE-TK-3F EE/ DIESEL EEIE SYMT AIR TM VII 2.19-15,RP-65A DGII 735 DIESEL GEN 91 5 N/A II/A le WA WA A 07 RV-EE-202C EE/3F AIR TM RELIEF VII 6.39-109 DG8I 735 DIESEL GEli 11 5 N/A N/A IS N/A N/A A 5316C A DIESEL GEN 82 5 N/A It/A NO N/A N/A A 5317 8 21 EE-TK-44 EE/ DIESEL EElIE STMT AIR TM VII 2.19-15,RP-65A DGBI 735 5317C 8 07 RV-EE-2034 EE/44 AIR TM RELIEF vil 6.39-109 DC8X 735 DIFtEL GEN 82 5 N/A N/A 18 WA II/A A > 5318 8 21 EE-TK-48 EE/ DIE 5EL EEINE STMT AIR TM VII 2.19-15,RP-65A DGBI 735 DIESEL CEN 82 5 N/A N/A 10 N/A N/A A 5318C 8 07 RV-EE-2038 EE/48 AIR TM RELIEF VTI 6.39-109 DG8I 735 DIESEL GEN 82 5 N/A N/A NO N/A N/A A EE/ DIESEL EKINE STMT AIR TM VII 2.19-15,RP-65A DGBI 735 DIESEL GEN 82 5 N/A II/A 10 0 II/A WA A 5319 8 21 EE-TK-4C VII 6.39-109 DG8I 735 DIESEL GEN 02 5 WA N/A NO N/A II/A A 5319C B 07 RV-EE-203C EE/4C AIR TM RELIEF 5320 8 21 EE-TK-40 EE/ DIE 5EL EEINE STMT AIR TM VII 2.19-15,RP-65A DGtX 735 DIESEL GEli 12 5 II/A N/A 10 0 WA N/A A 5320C 8 07 RV-EE-204A EE/40 Att TM RELIEF Vil 6.39-109 DGBI 735 DIESEL GEN 12 5 N/A N/A 11 0 N/A N/A A 5321 8 21 EE-TK-4E EE/ DIESEL EEINE STMT AIR TAls: VII 2.19-15,RP-65A DGet 735 DIESEL Gell 82 5 N/A N/A 16 N/A N/A A i 5321C 8 07 RV-EE-2040 EE/4E AIR TM RELIEF VII 6.39-109 DGRI 735 DIESEL GEN 82 5 li/A N/A NO WA N/A A Vil 2.19-15,RP-65A DGOI 735 DIESEL GIN 82 5 N/A N/A 10 ll/A N/A A 5322 B !! EE-TK-4F EE/ DIESEL EEIIE STMT Att TM 5322C B 07 RV-EE-204C EE/4F Att TM RELIEF Vil 6.39-109 DGBI 735 DIESEL GEN 12 5 N/A N/A 10 N/A WA A 5323 A 20 PNL-DICEN-1 EE/ DIESEL GENERATOR 51 CONTROL DE RE-58A DG8I 735 DIESEL GEN 11 5 ON CII VE5 N/A II/A A PANEL 5324 8 20 PNL-DICEN-2 EE/ DIESEL CENERATOR 52 CONTROL DNC RE-58A DG8X 735 DIESEL GEN 82 5 GN ON YES N/A N/A A PANEL 5345 A 09 VS-F-22A V5/DG BLOG Ost4UST Fall DGBI 756 DGet R00F 5R OFF ON VES RE-211F KCI-E7 8K E A 5326 8 09 V5-F-228 VS/DG SLDG EINAUST FAN DG01 755 DGI2 R00F 5R OFF ON VE5 RE-218F MCCI-E8 SK E A 5327 A 0 V5-D-22-1A V5/DG SLDG EINAUST DNFER VTI 10.1-1073,RS-27A DGBI 756 DGil ROOF 5t CLOSED GPEN VES RE-file PNL-AC-E3 BK E3- A 5328 8 0 V5-D-22-18 VS/DG BLDG EIHAUST DAIFER VII 10.1-1073,$R-27A DG8X 756 DGl2 ROOF 5R CLOSED GPEN YES RE-file PNL-AC-E4 BK E4- A 5329 A 0 VS-D-22-2A V5/DG BLDG AIR SUPPLV DNFER DGBI 745 DGIl 5R CLOSED GPEN VES RE-211F PNL-AC-E3 BK E3- A CERTif! CATION: The lifersatten identifyleg the equipment required to bring the plant to a safe shutdeue tenditlen en this safe Shutdown Equipment List (15EL) is, ti the best of our kneuledge and belief, correct and accurate. (One or more signatures of Systems er Operattens Engineers) R E b?Rs6 / EEINEER w O 12 !?Date7!H"' Prl.t er Iype Name/ Title 519aature Tfb. / ENGINEER C//M /8MW Date Prl#t or Type Name/ Title Mijdhture "

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J J ) Page No. 27 BEAVER VALLEY Pl!WER STAilWIIEllI I Report Date/Ilme: 12-20-95 / 10:24:14 Colro$ lit SAFE $NUIONAI EqulPIElli Lisi ($$EL)

528 IWlVICWL PLAIII CSF01ENTS LIH EqWIP $YSTEWESUIPNENT < EqulPIENT LOCATION ---> <-- OP. $1. -> PCNER $1FFORilE SYS. req'O INTERCOISECTISIS KG.: 10. TRAIN CLAS$ IINIK NO. DESCRIPTION thog. lie./Rev./Zene Bulldlag Ftr.Elv. Re. er Rew/ Col. $0RT IISTES leereal Desired REqD7 BMG. W./REV. a $1FFORTIIIG CSPOIENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 8042 8 14 PE-K-2 39/125 VOLT K POWER Dltitl8UIl0N OWG RE-27A SRVS 735 CONTROL $ 0 11 0 01 le N/A II/A A >

PAllEL 8043 A 14 PE-K-3 39/125 VOLI K POWER DISTRIBUTION DMG RE-27A $RVB 735 CONTROL $ ON ON No ll/A N/A A PANEL i 8044 A 20 PE-DG-$EG-1 M/ RELAY PANEL ' DMG RE-278, 25R $RVB 713 AE $UGR $ ON ON YES WA II/A A 8045 8 20 PE-DG-$Eq-2 M/ RELAY PANEL DWG RE-278, 25R SRVE 113 DF SWGR $ ON CII YES N/A II/A A 0046 A 20 PK-DGEA-1 36/HLAY PAIEL ONG RE-584 DG8X 735 DIESEL GEN 11 5 0 11 ON YES II/A N/A A 8047 8 20 PK-OGEA-2 36/ RELAY PANEL ONG K-50A DG8I 735 DIESEL GEN 82 $ ON ON YES 11/A II/A A 8048 A 14 PK-PR -NTR-A RC/ PRES $4AlIZER MATER $ POWER DIST. DWG RE-212,42K SFGB 735 W CABLE VAUli $ ON ON YES N/A WA A PAIIEL 8049 8 14 PE-Pt-HTR R RC/ PRES $lRIZER llEATERS POWER DIST. ONG RE-212, 42K $FGB 735 E CASLE VAULT $ 0 11 ON YES N/A II/A A PAIIEL 8050 A 14 PNL-PR-NTR-D RC/ PRES $URIZER lEATERS POWER DIsi. DWG RE-21JS, 42K $FG8 735 W CARLE VAULT $ ON ON YES N/A N/A A I PAIEL 8051 5 14 PNL-PR-NTR-E RC/ PRES $WRIZER NEATER $ POWER DIST. OWG RE-flJS, 42K SFG8 735 E CABLE VAULT $ GN 0 11 YES N/A N/A A PANEL j 8052 A 20 PE-EL-19 36/ RELAY PAIEL '94 RE-27C $RVB 713 RELAY $ 0 11 ON YES WA II/A A 8053 A/B 20 PR-REL-21 M/ RELAY PANEL DWG RE-27C SRYB 713 RELAY $ 0 11 0 11 YES N/A N/A A 8054 8 20 PNL-REL-22 36/ RELAY PAIEL ONG RE-27C SRV8 713 RELAY $ ON ON YES II/A N/A A 8055 A 20 PNL-REL-31 30/ AUX RELAY PANEL DMG RE-278 $RV8 713 AE $WGR $ ON 0 11 YES ll/A N/A A 8056 8 20 PE-REL-32 38/ AUX RELAY PAIEL DWG RE-21EA, 278 SRVE 713 DF SWGR $ 0 11 0 11 YES II/A N/A A 8057 A 20 PE-REL-33 38/ AUX RELAY PANEL DWG RE-275 SRV8 713 AE $WGR $ ON ON Yi$ II/A N/A A 8058 8 20 PE-REL-34 38/ RELAY PANEL DWG RE-278 $tVB 713 DF SUGR $ ON ON YES N/A II/A A 8059 A 20 PE-REL-35 38/ RELAY PAIIEL DMG RE-275 SRV8 713 AE $WGR $ ON Oil YES WA N/A A 90u i 20 PE-REL-M 38/ RELAY PANEL CMG RE-278 SRV5 713 DF SWGR $ ON ON YES N/A II/A A Me. A 20 PNL-REL-37 38/ RELAY PANEL DMG RE-2?S $RVB 713 AE SWGR $ ON 0 11 YES B:/A II/A A CERTIFICATI0II: The liformatlee identifying the etlulpment required to bring the plant to a safe shutdeun toedities en this $afe Shutdeue Equipment List ($$EL) is,13 the best of our knowledge and belief, correct and accurate. (One or more signatures of Systems er Operettees Engineers) kPritt er Type Ed R BE / EEllEER Hame/ Title aw 12/27 9[ Signature Date Nd# / -E4EilEElI h'[ .[ w /M Prlat er Type Name/ Title " Pl9(aturf " ' Date

m J l Page No. 28 SEAVER WLLEY PRER STATION 185ti 1 Report Date/flme: 12-20-95 / 10:24:14 C990511E SAFE slRITMAI EqulPIENT Ll5T (55EL) 528 ISIVltlant PLAlli CarWEWS LIIE EqutP SYSTEft/EqulMW < EqulPIEW LOCAf tel ----> <-- SP. 51.

PEER 5trPORilE SY1. req'O IMERCONCilel5 REG.

Q. TRAIN CLASS NRAK IE. SESCRIritell Bug. Ils.Aev./2eme Bulldtag F ir.Elv. Re. er Reu/Cel. SORT letES Iternal Bestred RE97 OE. IB.AEV. 8 StrPORilE CereIEMS 155tE (1) (2) - (3) (4) (5) (6) (7) (4) (t) (10) (11) (12) (13) (14) (15) (16) (17) 00E2 8 20 FIL-REL-M 38/ RELAY NIEL DE RE-278 5tV5 713 SF SifGR 5 ON ON VES N/A N/A' A 00E3 5 20 PNL-REL-DGI 3E/ RELAY NIEL DE RE-504 DGSK 7 35 DIESEL GEN 82 5 ON 0 18 VES II/A N/A A 8054 A 20 PNL-SMUTON-A 01/MAGEEY SilWTOOUN NIEL D E RE-27C SRW 713 MCC RACK 5 N/A N/A 11 / 4 N/A N/A A 0055 8 20 PNL-SilUTOII-8 01/EIERGEKY SilWT90lRI NIEL BMG RE-27C SHO 713 PROC REK 5 N/A N/A II/A N/A N/A A 8056 A 14 Pit-VlitUS-1 36/ VITAL SUS DIST NNEL 1 DE RE-27A SRVB 735 CONTROL 5 ON CII VE1 II/A N/A A 8067 8 14 PNL-Vii0US-2 3B/VliAL BUS DIST PAIIEL 2 BMG RE-27A SHE 735 CONTROL 1 ON ON YES N/A WA A SOES A 14 Pet-VITOUS-3 3B/V10AL BUS Disi PAIEL 3 ONG RE-27A SHO 735 CGIITROL 5 0 18 ON VES N/A . N/A A 8069 B 14 Pit-VITEUS-4 3B/ VITAL Ius BIsi PAIIEL 4 ONG RE-27A SHB 735 CONTROL 5 0 11 ON VES N/A N/A A 8070 A/S 02 REAC-TR-5NGR Ol#EETOR TRIP SWITCitGEAR bug RE-275 1RVB 713 RCD N/G RolBI $ II/A N/A N/A N/A N/A A Stil A 20 RK-AUK-RELA 01/III5tRWIEN AIS COIIIROL RELAY ONG RE-27C SRVE 713 PROC RACK 5 N/A N/A N/A II/A N/A A RACK 0072 5 20 RK-AUK-Rett OI/IIISTRipIElli AfD CONTROL RELAY OtfG RE-27C SRVO 713 PROC RACK 1 N/A N/A II/A II/A N/A A RACK 8073 A 20 RK-AUK-RPisi-A Ol#EACTOR PROTECTIst TEST RACK OlfG RE.iFC 1RVB 713 PROC RACK 5 N/A II/A II/A N/A N/A A 0074 , t 20 RK-AWK-RPi$f-B 01/ REACTOR PROTECTICII TEST RKK DMG RE-27C SRV8 713 PROC RACK 5 ll/A II/A N/A N/A N/A A 8075 A 20 RK-left-INS-1 02/EKORE IRfCLEAR Ill51RMIITATICII DMG RE-27A SMS 735 CollTROL 5 N/A N/A II/A N/A II/A A RACK 8076 8 20 RK-IRE-Ill5-2 02/EEIRE IRELEAR INSTRMNTATI0lt OMG RE-27A SRVB 735 CWifROL 5 N/A N/A lt/A N/A II/A A REK 8077 A 20 RK-MI-PROC-1 04/ PLANT IIISTRMNT/PROTEtil0N infG RE-27C, RC-8A, 508 713 PROC RKK 5 N/A N/A II/A N/A N/A A REK SB 8070 A 20 RK-MI-PROC-2 04/PLAffi Ill5TRtflENT/ PROTECTION DWG RE-27C. RC-8A. SRV8 713 PROC 2MK 5 II/A N/A N/A II/A N/A A REK 85 8079 A 20 RK-MI-M00-3 04/PLAlli INSTRMNT/PROTEtildll DWG RE-27C. RC-84, SRV5 713 PROL RACK $ N/A N/A N/A II/A N/A A RACK 05 0000 B 20 RK-MI-PROC-10 04/ PLANT Ill5TRWlENT/ PROTECT 10lt OWG RE-27C RC-SA, SRV8 713 PROC RACK 1 II/A N/A N/A N/A N/A A RACK 85 CERilFICAll0ll: The taformatten identifylog the egulpment regelred to bring the plant to a safe shutdemn toedittee en this safe shutdeun Egulpment List ($$EL) is,13 the best of our kneuledge and tellef, c tt and accurate. (One er more signatures of Systems or Operattees Eagleeers)

   $ bRlE                / ENGINEER                                                  s     N                                % 't !2 ~7 !'I $

Prl.L or Type llame/iltle Signature Date 7 d / IEllEER Prlit er Type Name/ title Od ' J- [I Date V TITnaMre

w Page lie. 29 BEMER llhtLEY PIRER STAllSI 1Rlli I Report Dete/ Time: 12-M-95 /10:24:14 Cipr05tTE SAFE SIRITSIRRt EgillPIGIT LIST ($$EL) 5N IIBlVIGNil PLAlff CerWEllis , Ll2 EgillP SY5TEWEqulPIGIT < EqulPIGIT LOCAllell ----> <-- OP. ST. -> PelER 5trPORillE SYS. MG'O lilTERCMBECilWE REC.

10. TRAIN CLAS$ IEIRE 18. MSCRIPilGI Bug. lie./Rev./Zene Building F ir.Elv. Re. er Rew/ Col. 557 leTES Ilereal Desired MSD7 OIE. IB./REV. 8 StrPORTIIC C909EllT1155UE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) -(13) (14) (15) (16) (17) ;

8001 8 20 N-MI-PROC-12 04/ PLANT IIETRtBWIT/ PROCESS RACK RE RE-2K, RC-SA, SRVE 713 PROC REK 5 II/A WA N/A II/A WA A 88 8002 8 20 RK-PRI-PROC-Il 04/PLAllt III5ftifEllr/ PROCESS RACK DIE RE-2K, RC-8A, SMO 713 PROC RACK $ II/A N/A II/A II/A II/A A 88 4083 8 20 RK-PRI-PROC-13 M/PLAllt IIIETRiflENT/McCE55 RACK ^ DIE RE-2K, RC-SA, SRW 713 PROC RACK $ 1/A WA N/A N/A WA A 88 8804 A 20 RK-MI-PROC-14 04/PLAlli IIISTRtpKitT/MOTECTI0le DIE RE-2?C RC-84 $RVB 713 PROC REK $ WA N/A II/A 11/ 4 II/A A RACK 88 8005 A 20 RK-MI-PROC-15 04/PLAlli MOCE55 BIE RE-2K, RC-8A, $RVB 713 PROC REK 5 N/A N/A II/A II/A II/A A IN5falfGIT/PROTECiloll REK 85 i 8086 A 20 RK-MI-PROC-16 04/ PLANT lil5TRWWIT/PROTECTI0ll CIE RE-2K, RC-GA, $RVB 713 PROC REK . 5 N/A N/A N/A WA N/A A RACK M 3087 A 20 RK-MI-M00-17 04/PLAllt IIISTRtBENT/PRCTECTION DIE RE-2K, RC-84, SRW 713 PROC RACK $ N/A WA WA N/A WA A RACK 88 J 80st A 20 M-MI-PROC-18 04/ PLANT Ill5TRl81ENT/Pil0TECil0N DIE RE-2K, RC-84, SRVB 713 PROC RACK 5 N/A N/A II/A N/A II/A A RACK OB 8089 8 20 RK-PRI-Mot-25 04/ PLANT lli5TRiflENT/ PROCESS REK OIE RE-2K, RC-84, SMB 713 PROC RACK $ ll/A N/A N/A II/A II/A A-88 , 8000 B 20 RK-PRI-Pil0C-26 04/PLAIIT llI5ftifEIIT/ PROCESS RACK IRE RE-2K, RC-8A, SRVB 713 PROC REE 5 WA II/A II/A N/A N/A A l 88 0091 8 20 RK-MI-PROC-30 04/PLAlli IIISTRifEllf/Pil0TECTION IRE RE-2K SRUB 713 PROC RACK 5 N/A N/A N/A N/A N/A A REK l 8092 8 20 RK-MI-PROC-31 04/PLAlli III51RIBIEllT/Pil0TECTIoll ole RE-2K SRVE 713 Pil0C RACK $ ll/A N/A 11/ 4 WA II/A A REK 8093 A 20 RK-PRI-PROC-34 04/PLAlli IIISTRl81ENT/PROTEtil0N DIE RE-27C SRV8 713 PROC RACK $ N/A N/A II/A N/A II/A A RACK . 3094 A 20 RK-PRI-PROC-35 04/PLAIIT lil51RWENT/Pil0TECTION DIE RE-2 K SRVB 713 PROC RACK $ N/A II/A II/A N/A WA A REK 8095 A 20 RK-REE-PROT-A 01/ REACTOR Plt 0 TECTI 0ll RACK DIE RE-2K SRVB 713 PROC RACK $ N/A N/A WA N/A WA A 8096 8 20 RK-REE-PROT-8 01/ REACTOR MOTECiloll RKK DIE RE-27C 3R48 713 PROC REK $ 11 / 4 N/A N/A N/A N/A A CERilFICAtl0N: The liformation identifying the equipment required to bring the plant to a safe shutdeun condition en this Safe Shutdeun Egulpment List (55ELI is, to the best of our kasuledge and belief, correct and accurate. (One or more signatures of syst er Operations Engineers) k [ERRlb / ElEllEER > MC l'2 !2 *7 / 7 S~ ! Frht er Type Name/iltle Signature Date T. bra / flWilEft hd[ / , Prkt er Type Name/Iltle 655gHidre Date ,

f l

                     ^                                                                                            O                                                                                     O l

l Pase lisi 30 BEAVER VALLEY PelER STATION ISili 1 l Report Date/ilme: 12-20-95 / 10:24:14 Cer051TE SAFE 51Rilm EqulPIENT LIST ($$tt) 528 IstvisstL PUult CerelENTS LIIE EqulP SY5TDl/EqulPIElli < EqulPIENT LOCATIW1 ~~-> - <-- Ir. ST. -> PCMER StrPWTIIE SYS. req'O INERCWEECilWii REG.

2. TRAIN CLASS fuRK 18. MSCRIPTIolt Bug. Ile,/Rev./Zene Bulldlag Fir.Elv. Re. er Rau/ Col. SORT miES lisrest testred REqBi mm. m./REV. 4 StrPW TIIE Es pWE W S lisuE l (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 8057 A 20 K-REC-P-IST-A 01/REKTOR PROTECil0N TEST RACK suG RE-27C 5tVB 713 PROC RKK $ 11/ 4 II/A II/A WA N/A A SSRB B 20 K-REC-P-T11-8 01/ REACTOR Pil0TEtil0N TEST RACK SuG RE-27C SRV5 713 PROC RACK 5 II/A It/A II/A N/A N/A A 0099 A 20 RK-5EC-PROC-A N/PUWIT IN5fttBIENT/PROTECTitle - BMG RE-27C, RC-88 $RVB 713 PROC PKK $ II/A II/A N/A N/A II/A A RACK K Site 8 to K-SEC-PROC-8 04/ PLANT lil5TRtfl[NT/PROTEtil0N IMG RE-27C, RC-88, 5tVB 713 PROC RACK $ WA II/A N/A II/A N/A A

! RACK SL 8101 A 20 RK-5EC-PROC-C 04/ PLANT INSTRMilf/PROTECTIoll SE RE-27C. RC-88, StVB 713 PROC RACK $ II/A N/A N/A II/A N/A A RACK SL 8102 B 20 M-SEC-PROC-D M/PLMit til51Rl8Elli/PROTECTICII OIE RE-27C. RC-OS, StVB 713 PROC RACK $ N/A II/A N/A N/A II/A A RACK SL 8102A A 20 RK-VS-E-IA 444/ CONTROL ROON 109 CollTROL AIR $RVB 713 AC EQUIP 200N $ 11/ 4 II/A II/A WA II/A A CertE550R RACK 81028 5 20 RK-VS-AC-18 44A/C0llTROL ROWI Alt IIAltiLillG Iffli SRVE 713 AC EqulP Roel 1 II/A WA 11 / 4 N/A II/A A StrPLY Fall 5 RACK 8102C A/S 20 RK-VS-E567 V1/ CONTROL ROWI MEATERS VS-E-5, 6 StVB 713 AC EQUIP ROWI $ N/A WA II/A N/A II/A A

                                       &7 81029 A/S 20        RK-VS-E8-12       V1/REK FOR VS-E-8-1 & 8-2                                     SRV8        713       AC EqulP ROWI $           It/A      II/A     II/A II/A         II/A                 A 3103 A         03   SW-1-8hl          35/400 VOLT E TRFN Di$CONECT            DWG RE-275            stVB        713       At SIER        S          CLOSED CLOSED II/A N/A               N/A                  A SMITCM 8104 5         03   SW-t-SPI          36/400 VOLT AC TRFN DISCONECT           llIIG RE-278          SRV8        713       DF SIER        $          CLOSED CLOSED N/A N/A                WA                   A SWITCH 8105 A         04   TRAll5-1-8-NI     37/400V AMK ENERG SUS INI               BMG RE-278            SRV8        713       NDRimL $lEt    $          0 11 -    CII      VE1 N/A           N/A                  A 8106 8         04   TRANS-I-9-PI      37/400V AUK DERG BUS IPl                CIC RE-278            SRVE        713       0F SIER        S          ON        ON       YE$ N/A           N/A                  A 8107 A/B 20 VERTIO                    01/Imill INSTRtflENIAll30 DISPLAY DIIG RE-27A 3BA             StVB        735       ColliROL       $          N/A       11 / 4   ft/A II/A         N/A                  A PAllEL 8108 A         20   PNL-REL-40        36/ RELAY PAllEL 40                     RE-27C, 25N           SRVB        713       IIORimL SilGR  $          ON        ON       VE1 N/A           N/A                  A 8109 8         20   PIE-REL-41        36/ RELAY PAIEL 41                      RE-27C, 25N           sRV8        713       leRett SWGR    S          0 11      ON       VE1 N/A           N/A                  A 8115 A         20   PNL-PAS-RA        36/PO$f EC10ENT 5AfrLE SYS RELAY RE-42A                       sRVB        735       RELAY RODN     $          0 11      0 11     VES N/A           N/A                  A PAllEL CERTIFICAil0ll:

The IIformatten identifyleg the equipment required te Irlag the plant to a safe shutdeun tendities en this safe Shutdeun Equipment List (55EL) c (One or more signatures of Systees er Operattens Engleeers) R n auie , DEillutis, to the best of our kneuledge andobelief,4Lct /n 4c ans accurate.FR Prht er Type Name/iltle 5ignature Date TMe* * / -flETWER Pritt er Type Name/ Title (( V Mqdature

                                                                                                   /      .7h r Date

                                                                                         /Q                                                                                                                                                                                                                /]                                                                                                                                                                   .fg Y                                                                                                                                                                                                                                                                                                                                                                                       N.)       ,

Page lee. 31 SEAVER VALLEY poler STATICII(Siti I Report Date/itee: 12-20-95 / 10:24:14 CipF051TE 5AFE SMUTDolAl EQUIPMENT Lisi (55EL) 528 Ile!VIDULL PLAlli CIBF0ENTS tl2 EQUIP SYSTEN/ EQUIPMENT < EQUIPMENT LOCATICII ----> <-- OP. ST. -> POWER 5trPORTING SYS REQ'8 INTERC01elECil0115 REG.

10. TRAIN CLA55 MMtK NO. DESCRIPil011 Dug. No./Rev./Zene Building f ir.Elv. Re. or Rom / Col. SORT llDTES Normal Desired REQDi DWG. Is./REV. 8 StrPOR(IE CGTOIENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 8116 3 20 PNL-PAS-RS 36/P05i ACCIDENT SmetE SV5 RELAY BE-42A SRVB 735 RELAY ROON 5 ON ON VES N/A N/A A PANEL 8117 A/B 20 PNL-AM5AC 458/AllTICIP TRAll5 WM SCRAM RE-27C SRV8 713 PROCESS RACK RM 1 DN ON YE5 8700-1.20-1174 N/A A MlilGAillE SYS ACillAT CIRCT THRU 1177 81B 8 01 NCC-1-14 37/400W EC FED FRtut 400W $125fA RE-30C. 400 AXLB 735 SOUTN OF LWFLlt 1 ON 0 11 YES N/A N/A A l-4 BU51M OKR4117 8119 A 20 18-348A VS/IERM 30X W/ RELAY LOC let 18-348 DWG RE-25AW AXL8 768 COL GI/08111/2 5 ON ON YES RE-21M5 PIIL-AC-El A 3120 8 20 18-349A VS/ TERM 00X W/RELAV LOC let 18-349 DWG RE-25AW AXLS 768 COL GI/88111/2 5 ON ON YES RE-21M5 PNL-AC-E2 A 8121 A/B 18 QS-RACK-1 05/ RACK FOR RW51 IIEAT TRACE (EAsi I!WG I.81-52 SH 3 YARD 735 YARD 5 N/A N/A le N/A N/A A SIDEOFRUSi) 8122 A/B 18 QS-RACK-2 45/ RACK FOR RWii It!AT TRACE (NE DK 1.81-52 SM 2 VARD 735 VARD 5 N/A N/A NO N/A N/A A SIDEOFRW5T) 8123 A/S 18 QS-RACK-3 45/ RACK FOR RW51 IIEAT TRACE (SOUTH VARD 735 VARO $ N/A N/A NO N/A N/A A SIDE OF RWST) 8124 A/B 18 QS-RACK-4 01/ RACK TOR RUST MAT TRACE (SE YARD 735 YARD 5 N/A II/A 11 0 N/A N/A A SIDE OF RW51) 8125 A 18 PNL-MS-1014 MS/INSTRtBIENT RACK FOR 50V4t1-101A RK8A SFG8 751 MSVN 5 R/A N/A N/A N/A N/A A Ale 50V-8t$-101A4 8126 8 18 PNL4t$-1018 N5/INSTRt4ENT RACK FOR 50V4t$-1918 RK-8A SFGB 751 MSVH $ N/A N/A N/A N/A N/A A Ale 50V-MS-10184 8117 5 18 PIIL-NS-101C MS/INSTRtBENT RACK FOR 50V4ts-10lt RK-8A SFG8 751 MSVH $ N/A 1(/A N/A N/A N/A A Ale 50V4t5-101C4 8128 A/B 20 RK-RA04WN-7 RM/ RADIATION MONITOR RACK 17 SRVB 735 CONTROL R0131 5 ON ON YES N/A VITAL BUS 1. 2 A 8129 A 18 PNL-SI-02 45/D15TRIBUTIO11 PAllEL DWG RE-63AQ SFG8 722 PIPE itBGEL $ ENERG ENERG VES RE-6E kcl-Ell BK i A 81 3 A 04 TRF-SI-02 45/5ATETY llLIEtitoll MAT TRACE DWG RE-63AQ 5FG8 722 FIPE itseIEL 5 ENERG ENERG* YES RE-63H HCCl-El! BK T A PNL-51-02 8131 8 18 PNL-11-06 45/Dl5TRIBUil0N PANEL DWG RE-63AQ SFG8 722 PIPE Tif01EL 5 EIERG EIERG YES RE-63H HCCI-Eli BK i A 8132 8 04 TRF-11-06 45/5ATETY llUECil0N HEAT TRACE DE RE-63AQ SFG5 722 PIPE itileIEL 1 ENERG EIERG YES RE-63M NCCI-Ell BK i A PR-51-06 CEtilFICA110N:

The LIformation identifying the equipment required to bring the plant to a safe shutdeun condition on this Safe ilmtdeun Equiparat List (SSEL) is, ta the best of our kneuledge and tiellef, correct and accurate. (One er more signatures of Systems or Operations Engineers) R ru n s / EE-R Prht or Type Name/Iltle

                                                                                                                  & F6                                Signature n/nAc   Date Prht er Type Name/ Title N rA                       / EletitER                                       hI[

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SSEL FOOTNOTES (Column 11)

1. Rx Trip Breaker opens automatically upon loss of power to the undervoltage relay.

2. Air-operated valve - Fails open upon lose of air; if failed open, valve could be isolated and flow controlled with bypass valve CH-29 Blender Cubicle, CH-22 would be closed to isolate FCV-122.

3. (DELETED)

4. Analysis of Charging Pump established it's ability to operate without CCR in Seal Water Heat Exchanger.

5. (DELETED)

6. Letdown Isolation Valves CH-LCV-460 A & B are air-operated and will fail closed on a loss of air.

7. Excess letdown is normally isolated at power.

8. Closing MOV-CH-378 or 381 causes RV-CH-382A to lift which diverts flow to the PRT.

9. Main Steam Isolation Valves MS-TV-101 A, B & C.are air-() operated and fail closed on loss of power or air.

10. The RHR and~ atmospheric valves require air to open but in the event of a loss of air, can be manually opened.

11. (DELETED)

12. Each Train has 100% of required capacity.

13. Air Recirculation Dampers are air-operated and fail open.

14. The Battery Chargers were chosen in addition to the i batteries because of the "72-hour" requirement.

15. (DELETED)

16. Air-operated valve fails closed on loss of air.

17. Needs to be closed to throttle aux. feed flow after first 1/2 hour.

18. This valve may be needed to go closed in the unlikely event that river water will need to be supplied to the steam generators. l

19. TRB's are considered NSSS equipment, immersed in RCS fluid.

20. PORV's require air to operate, mechanically acceptable.

12/20/95

GENERAL : A. Number series are assigned as follows (" Function" field designators underlined): 1000 - Beactivity Control; 1100 Rods & 1200 Boration 2000 - RCS Eressure Control; 2100 Decrease & 2200 Increase 3000 - RCS Inventory Control; 3100 CVCS & 3200 Leakoffs 4000 - RCS Heat Removal; 4100 Aux Feed & 4200 Steam Dump 5000 - Support Systems; 5100 River Water'(31), 5200 HVAC (Ell & 5300 (and up) Electrical (EA) 7000 - NOT INCLUDED HERE - Supplemental equipment not part of A-46, but SQUGGED to confirm seismic adequacy. 8000 - Enclosures / supports for electrical equipment 9000+- Essential relays (Separate List) l l f (/ O 12/20/95

4 i i i i 4 E i 4 1

A'rPENDIX 4.3-2 Seismic Review Safe Shutdown Equipment List (SSEL) 1 I

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l l) y f (J/ ( V BEAVER VALLEY P0utt 17AT10E UNIT 1 R Date/19ee: 12-21-95 / 12:44:59 Usi (55EL) 462 ISIVIOlltL PLANT CSF8ENTS tilt EQUIP 515ftN/EqulPMENT < EqWil9ENT LOCAil0N ----> <-- OP. Si, -> POWEt SWPORTIE SYS. Rit'D INitRCONCil0N5 REG. m TRAIN CLASS Ituft M. DESCRIPil0N Ibsg. No./Rev./2ene 9 ell 4in9 Fir.Elv. Be. er Rou/Cel. 50Ri ISTES Normal Desire 4 REqD7 DWG. In./REV. & SWPORTIE CSFCEWIS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 5307 A 21 EE TK-1A EE/EDG FUEL Oll STORAGE TAE DWG RP-654 VARO 128 VARD 5 N/A N/A IC ll/A N/A A 5308 8 21 EE-tK-15 Et/EDG FUEL OIL STORAGE TAE DWG RP-65A VARD 724 VARO 5 N/A WA 10 ll/A N/A A 5109 A 21 (E-tK-24 EE/tDG FUEL Olt DAT TAE VII 2.19-15,RP-e5A DCSX 735 OltSEL GEN Il 5 N/A WA NO N/A N/A A 53:0 8 21 El-TK-28 Et/EDG FUEL Ott DAY IANK Vil 2.19-15,RP-654 DG81 735 DitSEL GEN 82 5 N/A N/A N0 d/A N/A A 5311 A 21 EE-TK-3A tt/ DIESEL EEINE START AIR IAE Vil 2.19-15,RP-65A DCBI 735 Dltitt GEN 11 5 N/A N/A 10 N/A N/A A 5312 4 21 It-tK-38 ft/ DIESEL EEINE STARI A!R TAE Vil 2.19-15,RP-65A DG81 735 DitSEL GEN II 5 N/A N/A NO N/A N/A A 5313 A 21 El TK-3C Et/DIESIL EEINE START AIR TAE Vil 2.19-15,RP-65A DC8X 735 DIESEL GEN 81 5 N/A N/A 10 N/A N/A A 5314 A 21 E E -TK-30 EE/ DIESEL INGINE STARI AIR TA* Vil 2.19-15.RP-65A 0C81 735 DitSEL GEN 81 5 N/A N/A NO N/A N/A A 5315 A 21 E E-tK-3E EE/DitsEL INCINE START AIR IAE Vil 2.19-IS,RP-65A DGPS 735 DIE 5it GEN 11 5 N/A N/A 10 N/A N/A A 5316 A 21 It-it- 3F EE/ DIESEL ENGINE STARI AIR TAE Vil 2.19-15,RP-65A DC8X 735 DIESEL GEN 81 5 N/A N/A 10 N/A N/A A 5317 8 21 E E-f r -4A Et/DIFSEL ENGINE START AIR TANK Vil 2.19-15,RP-65A DG81 735 DIESEL GEN 82 5 N/A N/A le N 'A N/A A 5318 5 21 EE-1K 48 EE/ DIESEL IEINE START AIR TAE Vil 2.19-15,RP-65A DC81 735 DIE 5tt GEN 82 5 N/A N/A 10 N/A N/A A 5319 8 21 EE-tK-4C IE/ DIESEL ENGINE START Alt IAE Vil 2.19-15,RP-65A DC81 735 DIESEL GEN 82 5 N/A N/A 10 N/A N/A A 5320 8 21 E E-tK-4D IE/ DIESEL EEINE STARI AIR IANK Vil 2.1915,RP-65A DC81 735 3ttitt GEN 82 5 N/A N/A NO N/A N/A A 5321 8 21 E E-it-4E (E/ DIESEL ENGINE START AIR IAE Vil 2.19-15,RP-654 DC81 735 DIE 5ft GEN 82 5 N/A N/A NO N/A N/A A 5322 5 21 El-TK-4F EE/Ditstl EEINE START AIR TAE Vil 2.19-15,RP-65A DGB1 735 DIESEL GEN 82 5 N/A N/A NO N/A N/A 4 1205 N/A 07 FCV-CN-122 CN/CNARGING FLOW CONTROL VAtVE 150 6 24-268 AItB 722 BttleER 5 2 OPtN CLOSED VES RE-22L Vlistf5 II/Ill BK A 4107C A 07 FCV-FW-1034 FW/34 AFW Ptff REClRCULAll0N VALVE 150 6.24-774 5FC8 735 AUX FEED PtfF 5R CLO5ED OPEN VES RE-21HD PNL-DC-3 BK 8-53 A 4108C 8 07 T' V-FW-1038 FW/]B AFW Pt#F RECIRCULAtl0N VALVE 150 6.24-774 SFC8 735 AUX FEED PLDP 5R CLOSED GPEN VES It-21NE PNL-DC-3 BK 8-53 A 1118 A 07 FCV-RC-455C1 RC/(PCV-RC-455C) FLOW NETERING 150 6.24-3786 RK-lO RC8X 767 PRR CUBICLE 5 GPIN OPEN NO N/A N/A A

  !!!9 A       07     FCV-RC-455C2                    RC/(PCV-RC-455C) FLOW NETERING                                                                          150 6.24-3786 RC-ID RCBI          767                PRR CUBICLE 5                    OPEN OPEN 10                                  N/A                                               N/A                A 2120 8       07     FCV-RC-455DI                    RC/(PCV-RC-455D) FLOW NEftRING                                                                          150 6.24-3786, RK-lO RC8X         767                PRR CUBICLE 5                    GPEN OPEN NO N/A                                                                                N/A                A 2121 8       07     FCV-RC-455D2                    RC/(PCV-RC-4550) FLOW NETERIE                                                                           150 6.24-3786 RK-ID RCBI          767                PER CUBICLE 5                    GPEN GPEN NO N/A                                                                                N/A                A 8133         20 f t-CDL-1A                          FP/CO2 SYSTEN tl PE FOR TME                                                                             DWG RN-104            DG8X        735                DIE 5EL CEN 91 5R                CLOSED CLOSED le                              RE-21GI                                           PE-DC-3 BK 8-3     A DitSEL GEN RdoN WEST 8134         2G     FE-CDL-15                       FP/CO2 SYSTEN 01 PNL FOR THE                                                                            DWG RN-104            BG8X        735                DIESEL GEN 82 5R                 CLOSED CLOSED 10                              RE-21GI                                           PE-DC-2 BK 8-3     A DIESEL GEN ROON EAsi 12058 A     20     FI-CN-122A                      CN/CNARGIE NEADER FLOW IISICAi0R Vil 1.12-75                                                                                  3RYB        735                CONT IN BB-A        5R           04      ON                 VES RE-22L                                                           VITAL BU5 2        A

                                                                                                                                                                                                /3                                                                                                                                                              p Page Ms. 4                                                                                                                                                                      SEAVER MLLEY POWER STATION lAlli i tePort Date/ Time: 12-21-95 / 12:44:59                                                                                                                                                     SEI9'IC ttvitV SAFE SilWftslal EqWIMNE Lisi (55tt) 462 lelVIsmL Ptmi CWreENTS LINE        flu!P                                                                                              $YSTEN/fgulPIENT                                                     <          EtWIPIENT LOCATION -->                     <- OP. ST. --> POWER SWPERilNG SYS. Ett'D INTERCOlBECTIONS ttG.

ND. TRAIN CLASS IURE 10- DESCtlPiloll Dug. No./tevJZeme Bulldlag f ir.E lv. Rs. er Rom / Col. Soti NDit$ lisraat Destred Ett0? BMG. NO./ttV. 4 SEPP 0tillE CSF01ENTS ISSUE

                                                                                                                                                - = . - - . - . .         . - = . . - - = =        - . - . - - . = . . . . -             . - - .                                    . . . . . . . . . . . . . . - .                                                        . . .
   -         .     - - . . . - . = - - . .

(1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (IT) 22288 A 20 fl-CN-124 CH/ECP-lC SEAL IIDECil0ll FLOW Vil 1.12-22, 23 StV8 735 CONT RN V8-A 5t ON ON Yt1 Rf-220 Pf t-Ptit 20 VI) A IMICAfot Vil 1.12-22, 23 StV4 735 CONT RM V8-A s' ON 0 11 YES RE-22G PRI-PROC 9 V82 A 22298 8 20 fl-CN-127 CN/RCP-II SEAL ICECTION FLOW INDICATOR 22308 A 20 FI-CN-130 CM/tCP-1A SEAL IIUECil01 FLOW Vil 1.12-22, 23 SRV8 735 CONT RM V8-A 5t ON 04 YES tt-22G Pti-PROC 6 V81 A INDICATOR 32128 8 20 F1-CH-150 CN/LEIDOWN FLOW l@! Call 0N VII 1.12-75 StVB 735 CONT RM 88-A 5t ON ON Yt1 RE-22J VliAL BUS 2 A 41038 A 20 F 1-FW-1004 FW/Auf FEED 10 SGA INDIC Vil 1.12-25 StVB 735 CONT RM V8.C 5t ON ON YES RE-220Z VliAL BUS I A 41048 8 20 FI-N-1008 FW/ AUX FEED 10 SG8 Itt)lt Vil 3.12-25 5tVB 735 C0hi EM V8-C $R ON ON YES Rf-2202 VliAL BUS 4 A 41058 A 20 F 1-FW-1000 FW/ AUX FELO 10 SGC INDIC VII 1.12-25 5tVB 735 CONI RM V8-C 5t ON ON VES RE-22D2 VIIAL SUS I A 41070 A 18 Fl5-FW-I51A FW/ AUX FW PUMP FW-P-34 $UCIl0N 150 6.24-3831, 3833 STG8 722 COLUMN C4 5 [NERG ENERG Y(5 RE-21HD PNL-DC-3 BK 8-53 A LINE FROM Wi-tK-10 FIS 41080 8 18 FIS-f W1518 FW/ Aux FW PtNP FW-P-38 $UCif 0N ISO 6.24-3832 SFCB 722 COLINN C4 5 INERG ENERG V[5 RE-21Hf PNL-DC 3 8K 8 53 A LINE IROM Wi-tK-10 FIS 4118 M/A 20 FR MS-478 FW/tC-t-1A ttVEL ttCORDER Vil 1.12-25 5tV8 735 CONI RM 88-C 5t ON ON VES f f-22Z VITAL BUS 2 A 4119 M/A 20 FR MS-438 FW/RC-t-18 LEVEL RECORDER Vil 1.12-25 SRV8 735 CONI RM 88-C 1R 04 ON Yt1 II-22AA VilAL SUS 2 A 4120 N/A 20 f t-MS-498 FW/tC-E-IC LEVEL RECORDER Vil 1.12-25 StV8 735 CONI RM 88-C 5t ON ON YES #f-22A8 VITAL BUS 3 A 1205A A 18 FT-CN-122 CH/ CHARGING HEADER FLOW ISO 6.24-268 8 3875 AILB 722 COL 10-1/4 & J 5 t ON ON YE5 RI-22L VITAL BUS 2 A IR ANSMlilit 2228A A 18 Ti-CN-124 CM/RCP-lC SEAL INJECIl0N FLOW ISO 6.24-3952 RK-3E SfG8 722 PENT A 5t ON ON Yt$ It-22G PRI-PROC 20 V83 4 IRAN 5MlITER 222eA 8 18 FT-CN-127 CM/RCP-18 SEAL INJttil0N FLOW 150 6.24-3953, RK-X SFG8 722 PENT A 5t ON ON Yts RE-22G Pfl-PROC 9 V82 A itANSMllIII 22304 A 18 FT-CN-130 CH/tCP-IA SEAL llOECil0N FLOW 150 6.24-3630, RK-3E 5FG8 722 PENT A 5t DN ON YES RE-22G Pti-Pt0C 6 V81 A it4N5MIITER 3212A 8 18 Ti-CM-150 CH/tETDOWN FLOW TRAN5MITTER Vil 7.050-0010 AXLB 722 COL 11-1/2 & G S R ON ON Yt1 at-22J,0WG VITAL BUS 2 A RK-3A 4103A A 18 FT-FV-1004 FW/ AUX FIED TO SCA TRAN5MITTER RK-8A,150 6 24-65 SFG8 735 AUX FIED PtBF 5t ON 0 11 YES RE-220Z VITAL BUS I A 4104A 3 18 FT-TV-100B TV/ AUX FttD TO SGS TRAN5MITitt RK-8A, ISO 6.24-65 SFG8 735 AUK FEED Pt#F 5t ON ist YES RE-220Z VITAL BUS 4 A 4105A A 18 F1-TV-100C TV/ AUX FEID 10 SGC TRAll5MiiTER RK-84, ISO 6.24-65 SFC8 735 AUK FitO Pter 5t 0 18 ON Yts RE-220Z VITAL SU51 A 4107 A 05 FV-P-34 FV/ MOTOR DRIVEN AUX FEEDWAftt PLIF Vil 2.40-11,12 STG8 735 AUX FEE 9 Ptfr 5t 0FF Oil YES RC-21C,N,Rt-21N SUS At IK (16 A t,BI-18,6.24-44 4108 8 05 FV-P 38 FV/MTOR ORIVEN AUK FEEDWAlti PtBF VII 2.40-11,12 SFG8 735 AUK FEED PIDF 5t OFT ON Yts RC-fit,M,RE-21N SUS OF BK FI6 A t,Wi-18,6.24-64

_ _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ ~ _ - - _ _ _ _ _ _ .

                       %                                                                                                                                    {N                                                                                                         }

J V v Page lie. 5 BEAVER WLLEV 78MER STAT 10llISiti 1 Report Date/itee: 12-21-95 / 12:44:59 SEl981C REVIEW SAFE SWIIERRI E00lPIENT Ll1T (15EL) 462 ISIVIOWL PLANT CIBFGANT5 LIE EOUTP $YSTDl/ EQUIPMENT < EQUIPIENT LOCAf foll ----> <-- CP' ST. --> POWER SIFFORilE SY1. RE4'D INTERColelECilSIS REG. M. TRAIN CLAS5 NARC W. DESCRIPTION Dwg. No./Rev./Zene Sulleing F tr.Elv. Re. er New/Cel. 50RT IR)iES lisrael. Desired RE907 DWG. IRL/REV. 4 StFPORTIIE CGPOIENTS 155UE (1) (2) Q (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 2132 N/A 21 Ch IF-1A CN/ NITROGEN NEADER ACCIMILATOR RC8X 767 PRZR C15fCLE 1 N/A II/A M N/A N/A A 2133 N/A 21 CN-iK-1B CN/NiiROGEN NEADER ACCtHJLATOR RCSX 767 PRZR CtSICtE $ N/A N/A NO N/A N/A A 1229 B 07 NCV-CN- 346 CN/RCP SEAL stFPlV, NAW CONT VII-07.86-7 AXtB 722 BLEWCR ROON 1R THROT OPEN m RE-22G VifAL BUS 2 A 1733 A 07 NCV-CN-381 CN/ EXCESS LEIDOWN ORAIN DIVERT Vil-07.88-9 RC8X 737 EXC LEID PLATF 5R 7 OPEN OPEN NO RE-21fU PNL-DC-3 BK 8-18 A VALVE 4204 A 07 NCV NS 104 N5/RE5100AL NEAT RELEASE 150 6.24-6 1FC8 . 152 N5VN $R 10 CLOSED OPEN VES RE-221)R VliBU51 BK 1-7 A 5335 A 16 INV VilBU5-1 IF5/ VITAL BUS 81 INVEtiER OWG RE-278 SRVB 713 AE SWGR 1R ON ON VES 1.24-111 NCCl-E9 A 5336 B 16 INY-VliBUS 2 LPS/ VITAL BUS 92 INVERTER OWG RE-27B SRV9 713 0F SWGR SR ON ON VES 1.24-11I MCCI-E10 A 5337 A 16 INV-VilBUS-3 IF1/ VITAL BUS Il INVEtiER OWG RE-278 SRVB 713 At SWGR 5R ON ON VES 1.24-111 MCCI-E9 A 53 2 8 16 INV-VIIBUS- 4 IF5/ VITAL BU$ 84 INVERIER OWG RE-278 SRV8 713 0F SWCR $R ON ON VES 1.24-l % MCCI-[10 A 3204 A 07 (CV-CH 460A CH/LETOOWN 150lAfl0N VALVE 150 6.24-242 RCBI 718 A CUBICit 5R 6 OPEN CLOSED YES RE-21FU PHL 3 BK 8-18 A 3205 5 07 LCV CN 4608 CN/tETDOWN 150LA110N VALVE ISO 6.24-242 RCBI 718 A CUBICLE 52 6 OPEN CLOSED VES RE-21FU PHL DC-3 BK 8-18 A 41218 A 20 LI-N-474 N/RC-E-1A NARROW RANGE LEVEL Vil 1.12-25 $RV8 135 CONT RN V8-C 1R ON ON YES RE-22W VliAL RUS I A IWICATOR 41228 5 20 ti-FW-475 N/RC-E-1A NARROW RANGE LEVEL Vil 1.12-25 $RV8 135 CONT RN VB-C 5R ON ON VES RE-2?W VilAL BUS 2 A 121CATOR 4129 A 20 ll-FW-476 FW/RC-E-1A NARROW RANGE LEVEL Vil I.12-25 SRVB 135 CONT RN V8-C $R ON EH YES RE-222 VilAL BUS 3 A 12tCATOR 412G A 20 ll-FW-484 FW/RC-E-1B NARROW RANGE LEVEL Vil 1.12-25 SRV6 735 CONT RN VB-C $R ON ON YES RE-22X VITAL BUS I A INDICATOR 41258 8 to LI-N-485 TV/RC-E-1B NARROW RANGE LEVEL VII 1.12-25 SRvB 735 CONT RN VB-C $R ON ON YES RE-22X VliAL 80$ 2 A 12lCAf0R 4126B A 20 tl-FW-486 FW/RC-E-1B NARROW EANGE LEVEL VII 1.12-25 SRVE 735 CONT RN VS-C 1R ON ON VES RE-22AA VITAL BUS 3 A IWICATOR 41278 A 20 LI-N-494 TW/RC-E-IC 114RROW RANGE LEVEL Vil 1.12-25 SRVB 735 CONT RN VR C $8 Oli GN VES RE-22V VliAt SUS I A IWICATOR 41280 B 20 tl-FW-495 TW/RC-E-lC NNIROW RANGE LEVEL Vil 1.12-25 SRVB 735 CONT RN VB-C $R ON ON VE$ RE-22V VliAL SUS 2 A le!CATOR 41218 A 20 LI-N-4% N/RC-E-lC IIARROW RANGE LEVEL Vil 1.12-25 $RVE F35 Colli RN VI-C 1R ON 0 18 VE1 RE-22AB VilAL SUS 3 A IWICATOR 12010 A 20 Ll-41-1004 QS/ RUST LEVEL IMICATOR VII 1.12-25/92 5tVI 735 CONT RN VB-C $R ON 0 11 VES RE-22ET VITAL SUS 3 A 12025 8 20 L1-05-1005 ti/RW5T LEVEL le!CATOR Vil 1.12-25/92 SRVB 735 CONI RN V8-C $R Oli 0 11 YES RE-2?[I VITAL SU$ 4 A 1202 A 20 LI-QS-1000 QS/RWST LEVEL lelCATOR vil 1.12-25/92 1RVB 735 CONT IN vg-A $R ON ON YE1 RE-22EV VliAL BUS 1 A

pg M f\ k Page lie. 6 MAER WLLEY POIER STAiltBI 19111 1 Report Dete/Tlee: 12-21-95 / 12:44:59 stime!C REVIEW SAFE $HWISEIAI ($UtRIEglI Ll$i ($$EL) 462 IMIViOWL PLANT Capr0 NEWS i (IE EOUTP $YSTEN/ EQUIPMENT < EQUIPIElli 10 CAT 1018 ---> <- OP. St. --> POWER StrPORTIE SYS. REQ'O IIIIERCelettileNS REG. l M. TRAIN CLA51 144RK M. DESCRIPil0N Dwg. No./Rev./ Zone Bulldlag Fir.Elv. Re. er Row / Col. SORT 110T15 floreal Desired REQD7 OMG M./REV. 8 StrPORinE CINFONEllis ISSUE

                                     . . . . = = . .                                                            = = =                           . = = . . . . = = . . . = . . = = . . = . . . = = . = = . .                                     .      = . . . .              =       . . .                                             .         . . .

(1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 31248 A 20 LI-RC-459A RC/PZR LEVEL lelCATOR VII 7.70-0002. RK-3A SRVE 735 CONI RM 58-B $R ON ON Yt$ RE-22OH VITAL SU5 I A 31258 8 20 tl-RC-460 RC/PZR ttVEL IWICATOR VII 7.70 0002 1RV5 735 CONT RM 98 8 1R ON ON Yt1 RE-228J VliAL BUS 2 A 31268 A 20 LI-RC-461 RC/PZR LEVEL l@lCATOR Vil 7.70-0002 5tVB 735 CONT RM B8-8 5R ON ON Yt$ RE-229K VliAL BUS 3 A'

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A A s U U J Page Ms. 8 BEAVER VALLEY POWER $1 Ail 0N LAlli i Report Date/Tlee: 12-21-95 / 12:44:59 SEl98tC REVIEW 5AFE $NWTOCISI E451PIENT Lisi (15EL) 462 IslVieunt PLar C0wCNEWis LIE EFJIP SY1 TEM /ESUIPIENT < EqulPMENT LOCAil0N ---> <- OP. ST. --> PotEt SWPORTING 5V5. req'8 INTERCOIBECT10N5 REC. se. TRAIN Ctass wK NO. eEStalPilou 8=9. No./Rev./Zene Buildin9 Ftr.Elv. Re. er Rew/Cel. $0ti notes Nereal Desired req 07 Sm. No./ttV. 8 SUPP0tilNG twCNENTS ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 4110 A 08A MOV-FV-1518 FW/ AUX FEED FLOW CONit0L VAtVE 6.48-55,7.65-34,44 5FC8 735 AUX FEED Pl#F 5t 17 OPEN INR01 YES RE-21NF,6.24-65 MCCI-E5 Ct A6 A 4111 8 08A MOV-FW-151C FW/ AUX FEED FLOW CONTt0L VALVE 6.48-55,7.65-34,44 SFG8 735 AUX FEED PW 5t 17 OPEN INROT YES RE-21NT,6.24-65 NCCI-E6 8K AM A 4112 A 08A MOV-FW-151D FW/ AUX FEED FLOW CONTROL VALYC 6.48-55,7.65-34,44 SFG8 735 AUX FEED Pt#9 iR 17 OPEN THR01 YES RE-21NF,s.24-65 MCCI-E5 8K AN A 4113 8 08A MOV-FW-151E FW/ AUX IEED FLOW CONit0L VALVE 6.48-55,7.65-34,44 5FC8 735 AUX FEED Pt99 5t 17 CPEN THROI YE1 RE-21HF.6.24-65 kcl-E6 8K AJ A 4114 A 08A lev-FW-151F FW/ AUX FEED ILOW CONTROL VALVE 6.48-55,7.65-34,44 SFC8 735 AUX FEED Ptte 5t 17 OPEN THROT YES RE-21HF,6.24-65 MCCI-E5 SK AJ A 4214 8 ORA MOV MS-105 MS/ATW TUR8INE $1EAM StFPLY 6.48-95, % SFCB 735 M5VH $t OPEN CLOSED YES RE-21HY,150 MCCI-E6 BK BA A ISOLA 110N 6.24-625 2104 A ORA MDV-RC-535 RC/ PRESSURIZER PORY ISOLAil0N ISO 6.24-350 BC8X 768 Pit CtBICLE $R OPEN CLOSE0 YES RE-21]Q MCCI-E5 BK BE A 2l06 8 08A MOV RC 536 RC/PRESSURilti PORV !$0LATION ISO 6.24-350 RC8X 768 PZR Ct41CLE $R OPEN CLOSED YE1 RE-21JQ MCCl-E6 BK BC A flC3 A OBA MOV-RC-537 RC/ PRESSURIZER PORV ISOLAll0N ISO 6.24-350 RC8X 768 PZt CU6tCLF $R OPEN CLOSED YE5 RE-21JQ MCCl-E6 8K BD A 5104 8 ORA - MDY RW-102Al RW/Ptff DISCHARGE 150 6.48-22.23 (NTS 705 A CtBICLE SR Cl0 SED OPEN YES RE-21KZ,lSO MCCI El BK 0 A 6.24-801, RP-4L 5105 A ORA McV-RW-102A2 RW.ttef DISCHARCE 153 6.48-22.23 INTS 705 A CtBICit 5t CLOSED OPEN VE5 RE-21K2.lS0 MCCl-El BK G A 6.24 801, RP-4L 5106 8 08A MOV RW-10281 RW/PW DISCHARGE ISO 6.48-22,23 INTS 705 8 CU51CLE $R CLOSED OPEN YES RE-2]Kl.lSO HCCI E2 BK 0 A 6.24-801 RP-4L 5107 A ORA MOV-RW-10282 RW/Plff O!SCHARGE 150 6.48-22,23 INTS 705 8 CtNICLE 1R CLOSED OPEN YES RE-21KZ,lSO MCCl-E2 BK G A 6.24-801, RP-4L 5103 8 08A MOV-RW-102Cl RW/Pl#f DISCHARGE 150 0.48-22,23 INTS 705 C CISICLE 5t CLOSED OPEN YES RE-21KI, ISO MCCl-E2 BK N A 6.24-801, RP-4L 5109 A 08A MOV-RW-102C2 RW/PtRf DISCHARCE 150 6.48-22,23 INTS 705 C CUBICLE St CLOSED GPEN YE5 RE-211Z,lS0 MCCI-El BK H A 6.24-801, RP-4L 4116 A ORA MDV RW-103A RW/'A' HEADER RW FLW 10 RECIRC 6.48-32,33 AXLB 722 COL K $R CLOSED OPEN YES RE-21LA,6.24-12 MCCl-E3 8K 8 A SPRAY 8 4117 8 08A lev-RW-1038 N/'A'MEADER RW ILOW TO RECIRC 6.48-32,33 AXLB 722 COL K 5t CLOSED GPEN YE5 RE-21LA,6.24-12 McCl-E4 SK 8 A SPRAY 8 5119 8 08A MOV-RW-106A RW/CCR NT EXCN ISOLAll0N 6.48-51,52 AXLS 722 EAST CENTRAL $t 18 CPEN CLOSED YES RE-21LA,6.24-68 MCC1-E4 BK P A 5111 A 08A MOV-RW-ll3A- RW/ DIESEL CEN COOLING 150 150 6.24-159 DG81 735 DIESEL CEN 11 1R CLOSED OPEN YES RE-21LA MCCI-E3 BK N A 5122 A 00A peV-RW-1138 RW/Di[SEL GEN COOLING 150 ISO 6.24-160 DG8X 735 DIESEL CEN RI $R CLOSED (FEN YES RE-tilA kcl-E7 BK J A 5123 8 08A MN-RW-ll3C RW/ DIESEL GEN COOLING 150 ISO 6.24-159 DG81 735 DIESEL GEN R2 $R CLOSED GPEN YE5 RE-21LA kcl-E8 BK N A 5124 8 08A lev-RW-ll301 RW/ DIESEL GEN COOLING ISO 150 6.24-160 BC8X 735 DIESEL CEN 82 $t CLOSED GPEN VES RE-2ilA IECl-E8 BK J A $125 A 084 MOV-RW-114A RW/CCR NT EXCN ISOLAi!0N ISO 6.24-68 AXLB 722 EA$i CENTRAL $R 18 OPEN CLO5ED YES RE-21LA MCCI-E5 OK D A

I

           %'                                                                                                                                                                                                                                                                   %A Page No. g                                                                                                                                                            SEAVER httEY POWER stall 0N INII 1 Report Date/iler: 12-21-95 / 12:44:59                                                                                                                                            SEl981C REVIEW SAFE $Nuiselsi EqulPIEW LIST ($$tt) 462 Im!VisWL PLANT CorolEE5 LINE       EgillP                                                                                  SYSTEN/ESUIPENT                                                         <            EgiflPNEW LOCAil0N ---->               <- OP. SI --> PMR StrPORTIE SYS. RES'D INTERC018Eil0N5 REG.

Is. TRAIN class leRK NO. DESCRIPil0N Dug. IIs./Rev./2eer Bull 4teg F tr.Elv. Re. or Rew/ Col. 50RT NDTES IIsreal Bestre4 REqD7 85. No./REV. & SUPPORilE CWWOIENf3 I5 SUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 8016 A 20 let-NI-31A 02/50ERCE RAKE PREAf9LiflER Vil 1,20-052 STGB 735 V CABLE VAULT 5 N/A 11 / 4 II/A N/A N/A A 8017 8 20 let NI-32A 02/$0lRCE RANCE PREWLIFIER Vil 1.20-772 SFG8 735 E caste VAULT $ N/A II/A N/A N/A N/A A 8135 20 PCC-FE-IA ' FP/ PILOT CONTROL CABINET FOR DE RM-10A 0C81 735 DIESEL GEN ll 1 N/A N/A N/A N/A N/A A ffC-FP-605-1 8136 20 PCC-FE-18 FP/ Pit 0T CONTROL CABINET FOR DWG Rtt-104 DGBX 735 DIESEL GEN 82 1 N/A N/A N/A N/A N/A A IFC-FP-605-I 2128 N/A 07 PCV-CN-108 51/(PCV-RC-455D) NITROCEN PRES 5URE DWG RK-lO RCBX 767 PRZR CUBICtt 5 OPEN OPEN NO N/A N/A A CONTROL 2129 N/A 07 PCV-CN-109 SI/{PCV RC-455C) NITROGEN PRESSURE DWG RK-ID RCBX 767 PRZR CUBICLE 5 OPEN OPEN NO N/A N/A A CONTROL 2133 N/A 07 PCV-I A-108 I A/(PCV RC-455D) INSI AIR PRES 5URE DWG RK-10 RCBI 767 CRANE Watt 5 OPEN OPEN to M/A N/A A CONIROL 2831 N/A 07 PCV-l A-109 I Af(PfV-#C-4550) IN5I AIR PRE 55tRE DE RK-lO RCBI 767 CRANE Watt 5 OPEN OPEN NO N/A N/A A CONTRot 4205 A 07 PCV-N5-101A NS/A E00P AIN STIAN Otw 150 6.24-6 SFC8 752 NSVH 5 10 C105E0 OPEN YES RE-21JD VliAt BUS 2 A 4206 8 07 PCV NS-1018 NS/S LOOP AIN $iEAN DUlf 150 6.24-6 SFC8 752 NSW $ 10 CLOSED GPEN YES RE-21JD VliAL BUS 2 A 4207 B of PCV NS-10lt NS/C LOOP ATM 5TEAN Dlw 150 6.24-6 $FG8 752 N5VH $ 10 CLOSED OPEN TES RE-21JD VITAL BU5 2 A 2105 A 07 PCV RC-455C RC/ PRE 55URIZER PORV 150 6.24 349 RC81 767 PZR CUBICLE 5R 20 Closed OPEN YES RE-?lJT DC-PNL-2 BK 8-35 A 2109 A 07 PCV-RC-4550 RC/ PRE 55URIZER PORV 150 6.24-349 RC8X 767 PZR CUBICtf 5R 20 CLOSED OPEN YES RE-flJi DC-PNL-3 BK 8-34 A 2107 8 07 PCV RC-456 RC/ PRE 55tR12ER FORV 150 6.24-349 RC8X 767 PZR CtRICLE $R ~ 20 CLOSED GPEN YES RE-21JT DC-PNL-3 BK 8-34 A 5110 A 07 PCV-RW-1304 RW/ SEAL WATER PCV FOC RW Ptw 150 6.24-3345 INTS 705 A CUBICLE 5 CLOSED GPEN NO 150 6.24-3;45 N/A A i 5111 8 07 PCV-RW-130B RW/ SEAL WATER PCV FOR RW Ptp 150 6.24-3346 INTS 705 B CUBICLE S CLOSED GPEN IID 150 6.24-3346 N/A A 5112 A/B 07 PCV-RW-130C RW/ SEAL WATER PCV FOR RW Ptw 150 6.24-3347 INTS 705 C CUB! Cit 5 CtCSED GPEll NO ISO 6.24-3347 N/A A i 2110B A 20 PI-RC-402A RC$/ WIDE RANGE PRE 55tRE telCATOR Vil 1.12-23 SRVB 735 CONT RM V8-A 5R ON CII YES RE-229M VITAL SUS 3 A 21118 8 20 PI-RC-403 RC1/ WIDE RAEE PRE 55tRE IslCATOR Vil 1.12-23 $#VB 135 CONT RM V8-A SR 0 18 ON YES RE-228M VITAL SUS 2 A 8034 A 14 PIE-E-8US-lE 3B/ VITAL BUS DIst PAIEL IE DWG RE-27C SRVB 713 RELAY $ ON ON VE5 II/A N/A A 8035 8 14 PNL-AC-BUS-IF 3B/ VITAL BUS Ol1T PAfIEL IF DWG RE-27C SRyt 713 RELAY 5 ON CII VES N/A N/A A 8036 A 14 PNL-AC-El 3B/120 VOLT AC POWER DI$ltituiloll SWG RE-278 SRVI 713 AE SWGR $ 0 11 ON YES N/A II/A A PAIEL t 4037 9 14 PNL-AC-E2 3B/120 Voti AC POWER DISTRIOUTiON DMG RE-278 SRVB 71; DF SMGR 1 CN ON VES N/A II/A A PANEL

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g d] V V Page Ms.11 BEAMR VALLEY PWER STATI0llIRIII 1 Report Date/ Time: 12-21-95 / 12:44:59 SEl9 tlc REVIEW SAFE $NUIDast EqulMNT LIST ($5EL) 462 IWIVicist PLANT CONONENTS i if3 EQUlf SYSTEM /EDUIPNENT < EQUIPMElli LOCATION ---> <- CP. ST. -> POWER $WPORTING SYS. REQ'B INTERC018ECTIONE REG. i No. TRAIN CLAS$ ItWK NO. DESCRIPTION Dug. Ils./Rev./2sne Building Fir.Elv. Re. er Rom /tel. 50RT NOTES Normal Destred req 07 OWG. No./REV. 8 SWPORillE; COW 0lENTS 155UE ! (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 8050 A 14 PNL-PR-NTR-D RC/ PRES $1RIZER NEATER $ POER DIST. ONG RE-21J5. 42K SFGB 735 W CABLE VAULT $ ON 0 18 VES N/A N/A A PANEL 8051 8 14 PNL-PR-IITR-E RC/ PRE 55URIZER NEATER $ POWER DIST. DWG RI-21J$. 42K $FG8 735 L CABLE VAULT $ ON ON YES II/A N/A A PAEL 8052 A 20 PNL-REL-19 36/DG Il PROTECTION RELAY PANEL DWG RE-27C SRV8 713 RELAY 5 ON ON YE5 N/A N/A A 8053 A/B 20 PNL-REL-21 36/lMERTREQUENCY RELAY PANEL DWG RE-27C SRV8 713 RELAY 5 ON ON YES N/A N/A A REACIOR COOLANT PLM'S 8054 8 p PNL-REL-22 36/DG R2 PROTECil0N REI.AV PANEL DWG RE-27C SRV8 713 RELAY 5 ON ON VES N/A N/A A M55 A 20 PNL-R EL -31 39/ AUX RELAY PANEL DWG RE-278 SRV8 713 AE SWGR 5 ON ON YE5 N/A N/A A 2056 8 20 PNL-REL-32 38/ AUX RELAY PANEL DWG RE-21EA. 278 SRV8 713 DF SWGR S ON ON YES N/A N/A A 8057 A 20 PNL-REL-33 38/ AUX RELAY PANEL DWG RE-278 5tyt 713 AE SWGR 5 ON ON YES N/A N/A A 8058 8 20 PNL-REL-34 38/ AUX RELAV PANEL DWG RE-278 SRV8 713 DF SWGR 5 ')N ON YES N/A N/A A 0059 A 20 PNL-REL-35 38/RELAV PANEL DWG RE-278 SRVB 713 At 5WGR 5 ON ON YES N/A N/A A C060 B 20 PNL-REL-36 38/ RELAY PANEL DWG RE-278 SRV8 713 DF 5WGR 5 ON ON YES N/A ' N/A A 8061 A 20 PNL-REl-37 38/RELAV PANEL DWG RE-278 SRVB 713 AE SWGR S ON ON YES N/A N/A A 8062 8 20 PNL-REL-38 38/ RELAY PANEL DWG RE-278 SRV8 713 DF SWGR 5 ON ON YE5 N/A N/A A 8108 A 20 PNL-REL-40 36/ RELAY PANEL 40 RE-27C. 25N SRV8 713 NORNAL SWGR 5 ON ON YE5 N/A N/A A 8109 8 20 PHL-REL-41 36/ RELAY PANEL 41 RE-27C. 25N SRV8 713 NnRimL SWGR $ ON ON YES N/A N/A A 8063 8 20 PNL-REL-DGE 36/DG ISOLAfl0N RELAY PANEL OWG RE-58A DG81 7 35 DIESEL GEN R2 5 ON ON YES N/A N/A A 8064 A 20 PNL-5NUTON-A 01/ENERGENCY SHUTDOWI PANEL DWG RE-27C SRV8 713 PROC RACK 1 N/A N/A N/A N/A N/A A 8065 8 20 PNL-5NUIDN 8 01/ENERGENCY SNUIDOWN PANEL DWG RE-27C SRVB 713 PROC RACK 5 N/A N/A N/A N/A N/A T 8129 A 18 PE-51-02 45/Dl5TRIBUil0N PANEL DWG RE-63AQ SFG8 722 FIPE Tul8IEL 5 ENERG ENERG YES RE-6M NCCI-Ell 8K i A 8131 B 18 PNL-51-06 45/Dl51RIBUlluN PANEL DWG RE-63AQ SFG8 722 FIPE ItRINEL 5 ENERG ENERG YES RE-63H NCCl-Ell BK i A 8066 A 14 PNL-VliBUS-1 38/ VITAL SUS DIST PANEL 1 DWG RE-27A SRV8 735 CollTROL 5 0 11 ON YES II/A N/A A ! 8067 8 14 PNL-VIISUS-2 38/YllAL BUS Disi PAEL 2 DWG RE-27A SRv8 735 ColliROL $ ON ON YE5 N/A N/A A l 8068 A 14 PNL-VIT8US-3 38/V!8AL BUS DIST PANEL 3 OWG RE-27A SRV8 735 CONTROL 5 ON ON YES II/A N/A A 8069 8 14 PNL-VlitUS-4 30/VilAL BUS DIST PAEL 4 DWG RE-27A 5tVB 735 CONTROL 5 ON 0 11 YE5 N/A II/A A 420$E A 18 P5-MS-101A M5/AIN05PMERE STEAM Diff 5.G. lA I$0 E.24-2 SFG8 768 M5VN 5 ENERG ENERG YES RE-flJD PE-OC-3 BK 8-14 A 4206E 8 18 PS-Il5-1018 MS/ATIW5PMERE STEAM DtDF $_C.18 ISO 6.24-2 SFG8 768 M5VN 5 EERG EERG YES RE-212 PE-DC-2 IK 8-14 A _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ - = _ _ - _ _ .- _ _ _ -. _ . _ _ _ _ _ _ - _ - - . _ _ - _ _ _ - - _ _ _ -

(] . { (~N V V O Page No.12 MAVER VALLEV POER stall 0N 1811T 1 RePert Date/Tler: 12-21-95 / 12:44:59 SEI911C REVIEW SAFE 5NUI88181 EqulPNENT List (55ft) 462 letVI8tml PLMi COW 0ENi$ tlE EQUIP $VSTEM/ESUIPMEAT < EQUIPMENT LOCA!!0N ---> <-- 0F. $i. --> POWER $WPORTIE $VS. req'8 INTERCOMCTIGE REG. M. TRAIN CLASS NARK No. DESCRIPilolf Bug. No./Rev./ Zone Sullding Fir.Elv. Re. er Rou/Cel. SORT mits Normal Oestred REQ 07 OuG. M.AEV. & $WPORilE CMcENi$ ISSUE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17) 4207E 8 18 P5 -NS-101C NS/AINOSPNERE $fEAN OtN 1.G. IC 150 6.24-2 STG8 768 N5VM $ ENERG ENERG VES RE-21JD Pit-DC-2 9C 8-14 A 2110A A la PT-RC-402 RC/ WIDE RAEE RCS PRES $1RE TRANS DE RK-18 SC81 717 Af81ULUS COL 4-5 $ R ON ON VES RE-228N VITAL BUS 3 A 2111A B 18 PI-RC-403 RC/blDE RANr.E RCS PRE 55tRE TRAN5 DE RK-18 RK-IF RC81 692 A CIRICLE 5R ON ON VES RE-228N VliAL BUS 2 A 8121 A/8 18 QS-RACK-1 95/ RACK I A RWST NEAT TRACE (EAST DWG 1.81-52 $N 3 YARD 735 YARD $ N/A .1/A NO N/A N/A A SIDE OF RWST) i 8122 NB 18 QS-RACK-2 05/ RACK FOR RW51 NEAT TRACE (NE DWG 1.81-52 $H 2 VARD , 735 VARD 5 N/A N/A NO N/A N/A A 110E OF RWST) 8123 A/B 18 QS RACK-3 Q$/ RACK FOR RW51 HEAT TRKE (SOUTH YARD 735 YARD $ N/A N/A NO N/A N/A A SIDE OF RWST) 8124 A/8 18 QS RACK-4 05/ RACK FOR RWST HEAT TRACE (SE VARD 735 YARD 5 N/A N/A NO N/A N/A A slDE OF RW51) 1207 N/A 21 QS tK-1 Q5/REFUELIE WATER STORAGE TAtat DWG RV-24A VARD 735 VARD $R N/A N/A NO RE-63V HCCl-Ell, E12 A 8070 A/B 02 R E AC -IR -5WCR 01/REACIOR TRIP SWITCEEAR DWG RE-278 SRV8 713 R0D N/G ROON 5 N/A N/A N/A N/A WA A 8071 A 20 RK.AUA RELA 01/IN5TRMNI AW CONTROL RELAV DWG RE-27C SRV8 713 PROC RACK $ N/A N/A N/A N/A N/A A RACK 8072 8 20 RK- AUK-REl8 01/IN51RMNT AW CONTROL RELAY DWG RE 27C SRV8 713 PROC RACK $ N/A WA N/A N/A N/A A RACK C'J73 A 20 RK-AUX-RPIST-A 01/ REACTOR PROTECI!ON TESI RACK DWG RE-27C SRV8 713 PROC RACK $ N/A N/A N/A N/A N/A A 8074 8 20 RK-AUX RPTSI-8 Ol/REACIOR PR01ECil0N TEST RACK DWG RE-27C SRV8 713 PROC REK $ N/A N/A N/A N/A N/A A 8975 A 20 RK NUC-IN5-1 02/EXCORE NUCLEAR INSTRMNTA110N DWG RE-27A $RV8 735 CONTROL 5 N/A N/A N/A WA N/A A RACK 8076 8 20 RK-NUC-INS-2 02/EXCORE NUCLEAR INSTRMNIAi!0N DWG RE-27A SRV8 735 CONTROL $ N/A N/A N/A N/A N/A A RACK 8077 A 20 RK-PRI-PROC-1 04/ PLANT INSTRtNENT/PROTECil0N DWG RE-27C, RC-8A, SRV8 713 PROC RACK $ N/A N/A N/A N/A N/A A RACK 88 8080 8 20 RK-PRI-PROC-10 04/ PLANT IN51RMNT/PROTEti10N DE RE-27C, RC-8A, 1RV8 713 PROC RACK $ II/A N/A N/A N/A N/A A RACK 88 8082 8 20 RK-PRI-PROC-Il 04/ PLANT lil5TRMNT/PROCES$ RACK OWG RE-27C, RC-8A, SRV8 713 PROC RACK $ N/A N/A N/A N/A II/A A OS 8081 0 20 nK-PRI-PROC-12 04/ PLANT INSTRMNT/ PROCESS RACK OWG RE-27C, RC-8A, $RV8 713 PROC RACK $ N/A N/A N/A N/A N/A A 88 8083 8 20 RK-PRI-PROC-13 04/ PLANT IETRMNT/PROCES$ RACK DWG RE-27C RC-5A, 5tV8 713 PROC RACK $ N/A N/A II/A N/A . N/A A OS 8084 A 20 RK-PRI-PROC-14 04/ PLANT lil5ftMNT/ PROTECTION DE RE-1/C, RC-8A, SRV8 713 PROC RACK $ N/A N/A N/A N/A II/A A RACK 88

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8EAVER 5AMT.f PIRIER STATIW1ISIII I Pale No 13 i JIC REVIEW Report Date/ilme: 12-21-95 / 12:44:59 SAFE $11WI8elsi EqulMNT LIST (SSEL) 462 ISIVl81Rit PLANT CIBF0lENTS c EQUIPIENT LOCATIoll ---> <-- OP. ST. --> PelER SIFFORilE SYS. req'O INTERC018ECilell5 REG. LilE EqulP SYSTEN/ EQUIPMENT le. TRAIN CLASS NRRK 110. DESCRiffl0N Dwg. No./Rev./ Zone Bulldlag F tr.Elv. Re. er Rom / Col. 50Ri leTE5 Normal Desired req 07 OIE. NO./REV. & StPPORTING 09901ENTS ISSUE

     . . . . . . . . . . . - . - - . - . ..-....--.-....-.-..-..-....-.-.---....-...-.-..-..=.-.-.....--.--.-.....                                                                                    . . . . . . . . . . - . - . . . -   . -   . . . . . .

(8) (9) (10) (11) (12) (13) (14) (15) (16) (17). (1) (2) (3) (4) (5) (6) (7) 8085 A 20 RK-PRI-PROC-15 04/ PLANT PROCESS DE RE-27C, RC-84, SRVB 713 PROC RACK $ N/A N/A N/A N/A WA A INSTRMNT/PROTECil0N RACK 88 8086 A 20 RK-PRI-PROC-16 04/ PLANT INSTRtMENT/PROTECil0N DE RE-27C, RC-8A, SRV8 713 PROC RACK 5 N/A N/A N/A N/A N/A A RACK 88 8087 A 20 RK-PRI-PROC-17 04/ PLANT IN5ittMNT/ PROTECTION DE RE-270, RC-8A, SRV8 713 PROC RACK $ N/A N/A N/A N/A N/A A RACK 88 8088 A 20 RK-PRI-PROC-18 04/ PLANT INSTRtJNENT/PR0i[Cil0N DWG RE-27C, RC-8A, SRVB 713 PROC RACK 5 N/A N/A N/A N/A N/A A RACK 88 8078 A 20 RK-PRI-PROC-2 04/ PLANT INSTRMNT/PROTECil0N DWG RE-270, RC-8A, SRV8 713 PROC RACK 5 N/A N/A N/A N/A N/A A RACK 88 8089 8 20 PK-PRI-PROC-25 04/ PLANT INSTRIMNT/PROCES5 RACK DWG RE-270, RC-8A, SRV8 713 PROC RACK 5 N/A N/A N/A II/A N/A A 88 8090 8 20 RK -PRI-PROC-26 04/ PLANI INSTRMNT/ PROCESS RACK DWG RE-27C, RC-8A, SRV8 713 PROC RACK 5 N/A N/A N/A N/A N/A A 88 8079 A 20 RK PRI-PacC-3 04/ PLANI (H5IRIMENI/PR0iECil0N DE PE-27C, RC-8A, SRVB 713 PROC RACK 5 N/A N/A N/A N/A N/A A RACK 88 8091 8 20 RK-PRI-PROC-30 04/ PLANT INSTRUNENT/PROTECil0N DWG RE-27C SRVB 713 PROC RACK 5 N/A N/A N/A WA N/A A RACK 713 $ N/A N/A N/A N/A N/A A 8092 8 20 RK-PRI-PROC-31 04/ PLANT INSTRMNT/PROTECil0N OWG RE-27C SRV8 PROC RACK RACK 8093 A 2C RK-PRI-PROC-34 04/ PLANT INSTRtMNT/ PROTECTION DWG RE-27C SRv8 713 PROC RACK $ N/A N/A N/A N/A N/A A RACK 8094 A 20 RK-PRI-PROC-35 04/ PLANT IN51RtMENT/PR0iECil0N DE RE-27C SRV8 713 PROC RACK $ N/A N/A N/A N/A N/A A RACK 8128 A/S 20 RK-RAD MON-7 ilN/RAOIATION lONITOR RACK E7 OWG RE-27A 5RVB 735 CONTRot ROON 5 ON ON VES N/A VITAL BUS 1, 2 A 8095 A 20 RK-REAC-PROT-A 01/ REACTOR PROTECTION RACK DE RE-27C SRV8 713 PROC RACK 5 N/A N/A N/A N/A N/A A 8096 8 20 RK-REAC-PROT-8 01/ REACTOR PROTECTION RACK DE RE-27C SRV8 713 PROC RACK 5 N/A N/A N/A II/A N/A A 8097 A 20 RK-REC-P-ISi-A 01/REACIOR PROTECIl0N TE31 RACK OE RE-27C SRV8 713 PROC RACK $ N/A N/A N/A N/A N/A A 8098 8 20 RK-REC-P-isi-B 01/REACf3R PROTECil0N TESI RACK DE RE-27C SRW 713 PROC RACK $ N/A N/A N/A N/A N/A A 8099 A 20 RK-SEC-PROC-A 04/ PLANT INSTRt9ENT/PROTECTICII DWG RE-27C, RC-88, SRVB 713 PROC RACK $ N/A N/A II/A N/A N/A A RACK 8L 8100 8 20 RK-SEC-PROC-8 04/PLAlli Ill5TRlRENT/PROTEti!OII DE RE-27C, RC-88, SRVB 713 MCC RACK $ N/A II/A WA N/A N/A A RACK SL 8101 A 20 RK-5EC-PROC-C 04/PLAlli IN5fttMENT/PROTECTICII DIE RE-27C, RC-88, SRv8 713 PROC RACK $ N/A 11 / 4 II/A II/A N/A A RACK SL

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ML20097C837

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1.3 BACKGROUND

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ML20097C837

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1.3 BACKGROUND

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