ML20002E373

Zimmer Seismic Qualification Review Team Evaluation/ Qualification Status Rept.

ML20002E373
Person / Time
Site:	Zimmer
Issue date:	12/10/1980
From:	Brocato V, Mcconaghy W NUTECH ENGINEERS, INC.
To:
Shared Package
ML20002E370	List: ML20002E369 ML20002E371 ML20002E373 ML20002E374
References
CGE-03-144, CGE-3-144, NUDOCS 8101270651
Download: ML20002E373 (29)

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g- z1MsEa Soar EVALUATION / QUALIFICATION l STATUS REPORT I

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l Prepared by:

Nt! TECH 145 Martinvale Lane San Jose, California I

ll Prepared by: Issued by:

l 1//Q. S.s ap./eo p%9 M% i2kl@

Assistant Project Manager Project Manager I

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1 l TABLE OF CONTENTS PAGE l

1.0 INTRODUCTION

1 2.0 REQUALIFICATION OF ELECTRICAL EQUIPMENT 5

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3.0 REQUALIFICATION OF MECHANICAL EQUIPMENT 12 4.0 SCHEDULE 17 TABLE 1 QUALIFICATION STATUS

SUMMARY

l FIGURE 1 ZIMMER REQUALIFICATION SCHEDULE APPENDIX A - ZIMMER NUCLEAR SAFETY RELATED EQUIPMENT LIST I

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1.0 INTRODUCTION

NUTECH has completed a thorough review of all of the nuclear safety related Zimmer equipment which is in the NSSS vendor's scope of supply. This review was conducted to determine whether the equipment was qualified in accordance with the current U.S.

Nuclear Regulatory Commission (NRC) Seismic Qualification Review Team (SQRT) requirements. The following standards were used as the basis for the SQRT resvaluation:

Standard Review Plans 3.9.2 and 3.10 I -

USNRC Regulatory Guides 1.92 and 1.100 IEEE 344 (1975)

BWR Hydrodynamic Load Feedback

.I Before the actual evaluation of the qualification documentation I began, NUTECH prepared a list of the nuclear safety related Zimmer equipment in order to satisfy the first of the NRC SQRT requirements. This list is included with this report as Appendix A and it contains the following information:

a) General Electric Company (GE) Master Parts List Number b) Equipment Description c) Vendor and Model Number CGC-03-144 1

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I d) Active or Passive Classification e) Original Qualification Method f) Safety Function I

The list was prepared by reviewing several GE equipment lists and system drawings, and by contacting cognizant engineers at the plant site and at GE.

.I During the evaluation phase of the work, GE transmitted analyt-ical resulta, test reports, and recirculation and mainsteam pip-ing loads to NUTECH. Sargent & Lundy (S&L), who is the architect engineer, provided building response spectra and balance of plant piping loads. In addition, NUTECH received instrument specifica-tions and qualification documentation from several equipment l vendors. The information which was received from GE, S&L, and the equipment vendors was reviewed in light of the current NRC i

SQRT requirements. Careful consideration was given to the effects of the high frequency loads and the multi-modal response of the equipment.

l SORT Summary Forms were completed by the NUTECH engineers for the equipment items. These forms contain information concerning the equipment function, dimensions, and location, as well as the results of tests and analyses which were performed.

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The evaluation was divided into four (4) phases. During the I .

first phase, the locally mounted racks and instruments were eval-I I

i uated. The second phase of the work addressed the qualification l of the control room panels and instruraents. The floor mounted I mechanical equipment was' evaluated in the next phase. Lastly, the pipe mounted mechanical equipment was evaluated.

l I The results of the evaluation are provided below. The percen-tages refer to the percent of the equipment in each category

( which met the current NRC SQRT requirements.

Locally mounted instruments - 15% - - - ~ = l I

I Locally mounted racks - 0%

Control room instruraents .70%

( Control room panels - 40%

Floor mounted mechanical equipiaent - 30%

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Pipe mount'ed mechan'isal equipment - 65%

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l It should be not'ed that the mechanical equipraent which was found to be qualified'will be' reevaluated by NUTECH when the final GE p

l T-quenche,r and LOCA loads analyses are corap,lebed.

NUTECH -

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reviewed the current qualification results for the mechanical t

. .ss T' equipment by considering the methodology which was used to per-

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form the analyses and tests. It was as'sumed'that the same l.'

- .- - . t l methodology will be used when perfor' ming'the new 16 ads -

l (T-Quencher and LOCA) analyses since this methodology was found ,

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E acceptable during the reevaluation. This will be verified during

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NUTECH's final review.

E In order to bring all of the nuclear safety related Zimmer equip-I I ment into compliance with the current NRC SQRT requirements, NUTECH is developing and administering several requalification l

programs using state-of-the-art analytical and testing tech-niques. The locally mounted and control room instruments and l.

racks are being qualified by multi-axial, multifrequency tests.

l Several of the small mechanical equipment items are also being qualified by test. These tests will account for the effects of l' hydrodynamic and seismic loads on the equipment. The large mechanical equipment items are being qualified by complex modal analyses which use.the current hydrodynamic and seismic response

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l spectra. The following sections describe the ongoing tests and analyses in greater detail.

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l 2.0 ELECTRICAL EQUIPMENT REQUALIFICATION TEST PROGRAMS I The SQRT reevaluation revealed that due to the changes in state-of-the-art testing requirements there is not sufficient seismic test data to demonstrate conformance to SQRT Requirements for much of the Class lE equipment in the William H. Zimmer Electri-cal Power Station. Therefore, additional tests have been and will be conducted in order to provide additional required infor-mation. The following four groups of Class lE equipment will be tested in four separate test programs:

j 1. Local Panels

2. Locally Mounted Instruments and Electrical Devices

3. Control Room Panels

4. Control Room Instruments.

I The primary purpose of these test programs is to demonstrate that this equipment will meet SQRT requirements per IEEE 344-1975.

Each test will utilize multi-axis, random multi-frequency excita-l tion. In addition, results from local and control room panel tests will be used in determining Required Response Spectra for i

l panel mounted instruments. Resonance search tests will be con-I ducted. Representative instrument mounting locations on the panels will be monitored with accelerometers during testing.

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I I Equipment covered by this requalification program is presently installed in the Zimmer Station. Test specimens have been pro-cured from the original manufacturer and from spare parts at the Zimmer Station. Also, several panel mockups have been manufac-tured especially for this test program. In all cases much care has been taken to ensure that the test specimens are structurally identical to equipment installed in the Zimmer Station, Test

I specimens from spare parts or from original manufacturers often have the same model numbers as original parts. The Equipment Manufacturers have been requested to certify that procured items are structurally identical to installed items. When this certif-ication was not possible, product drawings and materials lists

I were reviewed to verify similarity.

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!I A brief description of the actual test procedures (as presently planned) for Seismic Category I electrical equipment is presented i

l below. The status of the requalification programs appears in l Table 1 of this section.

2.1 Local Panel Testing l

Essential local panels installed in Zimmer are constructed in l three basic widths of 30", 48", and 72". These basic sizes are

! sometimes combined to form the following panel sizes:

l lI 96" panel (two 48" panels) 102" panel (one 72" panel plus one 30" panel)

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I 120" panel (one 72" panel plus one 48" panel) 144" panel (two 72" panels)

Additional qualification information is required for all local panels. Three local panel mockups will be tested. Mockups have been constructed using the same methods and materials as were the original panels. Each mockup is designed and constructed in one of the three basic widths and represents the worst case panel configuration. Weights are installed to simulate mass of instru-ments, valves, piping and conduit. To ensure that these tests are representative for seismic responses of all similar panels, the mass configurations of each mockup was patterned after the most heavily loaded panel of similar width.

I Functional criteria for panel tests are limited to structural integrity as determined by visual inspection. However, acce'.er-ometers will be mounted in selected locations to monitor panel I responses. This information is used to determine the panel modes of vibration and to determine Required Response Spectra for panel mounted instruments.

I Testing will be conducted in the following phases:

1. Exploratory Sine Sweep Testing: To determine the panel resonant frequencies and cross-coupling effects. Test frequency will range from 1 to 100 Hz in each orthogonal axis.

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2. Fatigue Testing: To account for loads due to 40 l years of anticipated Safety Relief Valve (SRV) dis-charge events and Loss of Coolant Accident (LOCA) ever.ts . Test frequency will range from 1 to 200 Hz.

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3. Emergency Testing: To account for five (5) OBE level earthquakes combined with LC and SRV discharge loads. Test frequency wil3 a 'e from 1 to 200 Hz.

4. Upset Testing: To verify pane >perability during one DBE level earthquake combined with LOCA and SRV discharge loads. Test frequency will range from 1 to 200 Hz. All testing will be in accordance with IEEE 344-1975.

2.2 Local Instruments Testing A variety of Seismic Category I electrical equipment is mounted locally in the reactor building of the Zimmer Station. A total of 31 instrument models from 12 different vendors are presently scheduled for seismic qualification testing per the SORT require-ments. Instrument test specimens of all models can be procured from the manufacturers. Instrument test specimens will be tested separately from panel tests. Test fixtures will be designed and manufactured to simulate actual instrument mounting conditions during the test.

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l Functional criteria varies with the instrument being tested.

Operating conditions will be simulated and equipment operation, including critical functions, will be monitored during each instrument test. Required Response Spectra for panel mounted instruments will be produced from the results of the Local Panel l

Tests.

Testing will be conducted in the same four phases as listed for local panel testing. Details of local instrument testing are yet to be specified pending review of local panel test results, but will account for LOCA, SRV discharge, and seismic loading over the life of the equipment being qualified.

I 2.3 Control Room Panel Tests I Of the 13 Control Room Panel configurations at the Zimmer Sta-tion, eight configurations require additional seismic qualifica-tion information. The following eight (8) types and sizes of Zimmer Control Room Panels have been selected for additional testing:

I Vertical Panel L=96" W=36" H=90" Vertical Panel L=72" W=36" H=90" Vertical Panel L=48" W=36" H=90" Vertical Panel L=24" W=36" H=90" Instrument Rack L=60" W=36" H=90" I CGE-03-144 9 l nutech

4 I Instrument Rack L=48" W=36" H=90" Instrument Rack L=30" W=36" H=90" Vertical Panel L=30" W=36" H=90" I

f One of these panels, a 30" Vertical Panel, can be obtained from Zimmer Spare Parts stocks. The remaining seven (7) panels will I

be constructed using the same methods and materials as were the I original panels. Each test specimen represents all similarly I

sized Zimmer Control Room panels. Weights will be installed to simulate mass of instruments. Functional criteria for panel tests are limited to structural integrity as determined by visual l

l inspection. However, accelerometers will be mounted in selected I locations to monitor panel responses. This information is used to determine panel modes of vibration and to determine Required l Response Spectra for panel mounted instruments.

l Testing will be in accordance with IEEE 344-1975. The inital I test phase will be exploratory sine sweep testing to determine panel resonance frequencies and cross-coupling effects. Although SRV discharge and LOCA events are expected to have only negli-gible effects on control room equipment, these effects will be considered in the dynamic testing of the equipment.

2.4 Control Room Instruments Testing For several of the Control Room mounted instruments, existing test data does not adequately demonstrate seismic qualification I CGE-03-144 10 g nutech l

I per SQRT requirements. Instrument test specimens will be obtained from instrument vendors and from Zimmer spare parts.

Instrument tests will be run separately from panel tests. Test fixtures will be designed and manufactured to simulate actual instrument mounting locations during the test.

Functional criteria varies with the instrument being tested.

Operating conditions will be simulated and equipment operation, including critical function (s), will be monitored during each instrument test. Required Response Spectra for panel mounted instruments will be produced from the results of the Control Room

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344-1975.

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i 3.0 REQUALIFICATION OF MECHANICAL EQUIPMENT 1

I This section describes the mechanical equipment seismic requal-ification work that is either in progress or about to begin. The f technical approaches include analytical and testing techniques as well as a combination of both techniques.

1 1 3.1 Requalification by Analysis -- NUTECH I

3.1.1 ECCS Pumps The Residual Heat Removal, Low Pressure Core Spray, and High Pressure Core Spray pumps are being reanalyzed for new load spec-trums in accordance with the SQRT Program requirements. The input acceleration response spectrum for these analyses is an envelope of the absolute sum of the Safe Shutdown Earthquake (SSE), Safety Relief Valve (SRV) Chugging, and Condensation oscillation (CO) response spectra. The methodology being utilized is an elastic linear analysis using normal mcde super-position.

A detailed finite element model using beam elements is used for representing a composite model of the pump and motor. The dynamic response of this model is checked agairest the equipment allowable tolerances to determine system operability.

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A more detailed finite element shell model is generated, using triangles and quadrilaterals, to determine the adequacy of the nozzles under the new loading conditions.

11 3.1.2 New Fuel Storage Rack The design adequacy of the New Fuel Storage Racks is being accom-plished by a detailed finite element analysis using the STARDYNE computer program. As with the ECCS pumps , the input acceleration response spectrum envelopes the absolute sum combination of SSE, SRV, and CO response spectra. The results of the dynamic analysis (i.e. shears and moments) are then used to calculate the stresses at critical joints and locations of geometric discon-tinuity.

l 3.1.3 In-Vessel Rack A modal superposition response spectrum method is used to dynam-ically analyze the In-Vessel Rack when subjected to the design loads. A linear elastic beam model is used to represent the system. The stresses for these different loading conditions are calculated to ensure structural integrity during a SSE eve.7t.

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I 3.1.4 Hiilh Pressure Core Spray Valves The valves for this system were supplied by two branches of the l

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The vendcr will be undertaking the

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Anchor / Darling Valve Company. ,

l reanalyses and operability evaluation under contr Ot to NUTECH l

since they have performed dynamic analysis of many of their l

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I I valves and they are most qualified to certify operability based upon their knowledge of critical elements and permitted deflections.

I The vendor will calculate the valve resonant frequencies. A static analysis will then be performed which will consider the maximum combined stresses due to SSE, SRV, CO, gravity, pressure r.nd pipe reaction loads. For any valve having fundamental resonance (s) below 60 Hz, an amplificntion factor will be applied to the SSE+SRV+CO load combination.

!I The vendor will then make an engineering judgement regarding valve operability, taking into consideration the stress analysis and any previous test or performance data. A certification of operability will be provided for those valve designs judged to be adequate for the new loads criteria.

I 3.2 Requalification by NUTECH -- Test A test program will be conducted to verify acceptability of the scrara discharge volume vent and drain valves, as well as the ASCO four-way solenoid valve used in the CRD system. The test program will include resonance searches and multi-axis, raulti f requency, seismic vibration testing as well as appropriate operability I

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3.3 Requalification by Analysis -- Sargent & Lundy J

The following equipment is being requalified analytically by Sargent and Lundy:

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1. Refueling Platform Equipment

2. Fuel Prep Machine 1

3. Main Steam Isolation Valve Leakage Control System Blower The equipment will be represented by detailed finite element )

models. The adequacy of the equipment designs will be evaluated utilizing dynamic analysis methods with appropriate acceleration response spectra inputs.

I 3.4 Requalification by Test and Analysis -- Sargent and Lundy The Standby Liquid Control Pump and the Reactor Core Isolation Cooling Pump are being requalified by impedance testing and analysis. Impedance tests have been performed to identify any equipment resonances below 60 Hz. These results will be included in dynamic analyses of the equipment utilizing response spectra inputs.

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l 3.5 General Electric New Loads Program l

For the following equipment General Electric Company will provide l additional information for the effects of the T-Quencher and LOCA loads as part of the New Loads Program:

I 1. Recirculation Pump and Valves

2. Residual Heat Removal Heat Exchangeer

3. RCIC Turbine

4. Main Steam Isolation Valves

5. Safety-Relief Valves

6. Control Rod Drive Hydraulic Control Units I The equipment listed in 1 and 2, above, will be reviewed by NUTECH based on GE's analytical results. NUTECH found these items (except the RCIC nurbine) to be qualified dynamically to ramshead loads during the SORT Re-evaluation Program.

I For the RCIC turbine a similarity study is being performed by GE to determine what, if any, dynamically significant similarities exist between the Terry Model GS-1, installed at Zimmer, and the Model GS-2, which was satisfactorily tested.

I NUTECH will evaluate the results of the GE new loads (T-Quencher and LOCA) program and the RCIC turbine similarity study in order to ensure that the Zimmer equipment has been qualified in accor-dance with the current NRC SORT requirements.

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4.0 SCHEDULE The schedule for NUTECH's ongoing qualification program is de-picted in Figure 1. This figure provides the key milestones for the qualification of all of the major equipment groups. The major equipment groups are identified below:

1. Locally Mounted Racks

2. Locally Mounted Instruments

( 3. Control Room Panels

4. Control Room Instruments

5. Small Valves in CRD System

6. Fuel Racks

7. ECCS Pumps

8. HPCS Valves

9. MSIV LCS Heater E

The equipment which is specified below will be reviewed by NUTECH af ter GE completes the new loads (T-Quencher and LOCA) program.

Control Rod Grapple General Purpose Grapple RPV Head Strongback Dryer / Separator Sling Flammability Control Unit RCIC Turbine l I

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I I Standby Liquid Control Storage Tank RHR Heat Exchanger Main Steam Isolation Valves  ;

Safety Relief Valves l

Recirculation System Valves Recirculation Pump I The following equipment is being analyzed by S&L using the impedance test program results and already existing models in some cases, for the following equipment items:

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RCIC Pump Fuel Prep Machine Refueling Platform Equipment Standby Liquid Control Pump MSIV LCS Blower E The schedule for items being requalified by NUTECH is shown in Figure 1.

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FK3URE 1 ZIMMER REQUALIFICATION SCHEDULE i 1980 1981 PROJECT TASK SEP OCT NOV DEC JAN FEB MAR APR MAY JUN 1 8 1522296 1320273 10 17 24 1 8 1522295 1219262 9 16 23 2 9 1623306 13 2027 4 11 18 25 1 8 15 22 29 R A 1 h 1 1 1 i a I E a d A a a a I a a A I e 0 1 1 a i a E A 1 i R R G 1 1 a a e LOCAL PANEL TESTING ,

LOCAL INSTRUMENT ' '

TESTING CONTROL ROOM

PANEL CONSTRUCTION i

! CONTROL R00H

] PANEL TESTING CONTROL ROOM INSTRUMENT TESTING CRD VALVE TESTING i 1

I FUEL RACK ANALYSES I

I ECCS PUMP ANALYSES ,. ,.

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i HPCS VALVE ANALYSES 3

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m m m m m m m m m m M M M M M M M M m Table 1 QUALIFICATION STATUS TABLE REQUALIPICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE

• Condensing Chamber GE/136B2798G003 Qualified NA 2 Safety / Relief Valve Crosby /6R10-IIB-BP Qualified NA 2 .

Main Steam Isolation Rockwell/ Qualified NA 2 Valve and 24"x20"x24" Actuator Fig. 1612JMMNTY Press. Switch Barksdale/ BIT-M12SS To Be Requal. Test 2,3,15,19 w Level Switch Barton/288A Qualified NA 2,3 Barton/384 2 Level Ind. Switch To Be Requal. Test AP Xmtr. Bailey /555 To Be Requal. Test 2,9,19,22,24,28 Level Ind. Switch Yarway/4418C To Be Requal. Test 2 Level Switch Barton/760 To Be Requal. Test 3 Press. Switch Static-O-Ring / Qualified NA 3,15 12-N-AA4-TT Press. Xmtr. Bailey /556 Qualified NA 3,9,11,19,20,24,33, (Rx Press. 34 Vacuum Switch (Main Barksdale D1T-H18SS To Be Requal. Test 3 Condenser Press.)

Press. Ind. Robe ghaw/613B Qualified NA 3,11,22,25,33 (RPV Press)

AP Ind. Barton/227 To Be Requal. Test 3 Recirc Pump Bingham-Williamette/ Qualified NA 5 20x20x33 RV Recire. Suction Valve Anchor-Darling / Qualified NA 5 94-13223

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l REQUALIFICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE

• Recirc. Control Valve llammel-Dahl/ Qualified NA 5 V999L-26 Recirc. Discharge Anchor-Darling / Qualified NA 5 Valve 95-13225 AP Xmtr. P.;;&mJunt/1151 Qualified NA 5,9,31, 34,48,49 Press Switch Static-0-Ring / Qualified NA 5,20 SN-AA3-SITT Press Switch Barksdale/ To Be Requal. Teet 5,22,25 Pill-M340SS-V Temp Element Rosemount/535E To Be Requal. Test. 5,48 Temp Element Pyco/ll7C3485P40 To Be Requal. Analysis 5,19,46 Hydraulic Control GE/761E500G1 Qualified NA 7 Unit Solenoid Valve Automatic Switch To Be Requal. Test 7 Company /832322 Scram Discharge Vol. Ilammel-Dahl/ To Be Requal. 7 Vent valve SN 71/2006/001-009 Scram Discharge Vol. Ilammel-Dahl/ To Be Requal. Test 7 Drain Valve SN 71/2006/017-025 Pressure Relief Valve Crosby / To Be Requal. 7 3/4x1 JMAK Spec. B Level Switch Magnetrol/5.0-751 Qualified NA 7,33 AP Xmtr Statham (Gould)/ To Be Requal. Replacement 9 PD2000-0400 SLC Storage Tank General Electric / Qualified NA 11 283x551G993 SLC Pump Union Pump Co./ To Be Requal. Analysis (S&L) 11 g 2x3 TD-60 o

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V) No. in Nuclear Safety Related Equipment List (Appendix A).

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W W W W W W W W 5 W G h M M M M M CW REQUALIFICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE

• SLC Explosive Valve Conax/ To Be Requal. Test 11 1832-159-01 Temp Switch Fenwal/22810 To De Requal. Test 11 Temp Element Fenwal/158B7072P7 GE New Loacio NUTECH Evaluation 11 Thermowell only ,

IRM Detector GE/112 C 3144 GE New Loads NCTECH Evaluation 13 Voltage Preamp GE/163C1263 To Be Requal. Test 13 Tip Guide Tube Valve Assembly Shear Valve NECI/886D393 Qualified NA 13 Solenoid Ball Valve NECI/112C2391 Qualified NA 13 Press Switch Barton/288 Qualified NA 15,19, 22,25,27,28,48 Sens. & Conv. GE/194 X 927 To Be Requal. Test 17 Gamma Detector GE/237 X 731 To Be Requal. Test 17 RilR lit. Exchgr. Delta Southern /NA Qualified NA 19 Ri!R Pump / Motor Ingersol-Rand /27-APKD To Be Requal. Analysis (NUTECll) 19 Level Xmtr Barton 352/368 To Be Requal. Test 19 AP Switch Barton/289 To Be Requal. Test 19,22,24,34 Press. Switch Robertshaw / To Be Requal. Test 20,22,24 SP-222-C LPCS Pump / Motor Ingersol-Rand /27APKD-5 To Be Requal. Analysis (NUTECil) 22 HPCS Pump / Motor Ingersol-Rand / To Be Requal. Analysis (NUTECil) 24 IIPCS Suction Valve Anchor-Darling / To Be Requal. Analysis (NUTECil) 24 94-13266 1

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l W W W W W W W M M M M M M M M M M M REQUALIFICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE *

. HPCS Injection Valve Anchor-Darling / To Be Requal. Analysis (NUTECH) 24 10"C 900 Gate HPCS Test Valve Anchor-Darling / Not qualified Analysis (NUTECit) 24 M

HPCS Bypass Valve Anchor-Darling / To Be Requal. Analysis (NUTECil) 24 94-13329 IIPCS Suction Valve Anchor-Darling / To Be Requal. Analysis (NUTECH) 24 94-13294 HPCS Test Return Valve Anchor-Darling / To Be Requal. Analysis (NUTECH) 24 IS-1751-3 Level Switch Magnetrol/ Qualified NA 24 3.5-751-lX-MPG-M1411Y Damper Republic Qualified NA Press Switch Barksdale/ To Be Requal. Test 27 Pill-M85SS-V Thermocouple Pyco/145C3224P1 To Be Requal. Test 27,28,29 MSIV-LCS Ileater GE/21A3581 To Be Requal. Analysis (NUTECII) 31 MSIV-LCS Blower GE/21A3762 To Be Requal. Analysis (SLL) 31 Flow Meter Schutte & Koerting/ To Be Requal. Test 31 20-9651-8550 Flow Xmtr. Schutte & Koerting/ To Be Requal. Test 31 91X-16-4-20 RCIC Pump Bingham / To Be Requal. Analysis (S&L) 33 4x6x9 CP RCIC Turbinc Terry /GS-1 GE New Loads Similarity Stt.dy 33 Pressure Switch Static-0-Ring / Qualified NA 33 6N-AA21-VSITT Press Switch Barksdale/ To Be Requal. Test 33 D211-M80SS rw

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g *Pg. No. in Nuclear Safety Related Equipment birt (Appendix A).

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W M M M M M M M M M M M M M M M M M REQUALIFICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE

• Fuel Prep Machine General Electric / To Be Requal. Analysis (SEL) 36 729E716G001 General Purpose General Electric / Qualified NA 35 Grapple Dryer / Separator General Electric / Qualified NA 38 Sling 752E984P001 RPV 11ead General Electric / Qualified NA 3 Strongback 762E985P001 Control Rod General Electric / Qualified NA 40 Grapple 767E593G002 Refuel Platfccm General Electric / To Be Requal. Analysis (S&L) 42 Equipment 762E892G002 Spent Fuel Storage General Electric / Qualified NA 44 Rack 762E210G001 CR and Defective Fuel General Electric To Be Requal. Replacement Storage Rack 731E670 GOO 4 44 Defective Fuel Storage General Electric To Be Requal. Replacement 44 container 1172072G004 In-Vessel Rack General Electric To Be Requal. Analysis (NUTECH) 44 7298269014 New Fuel Storage Rack General Electric To Be Requal. Analysis (NUTECH) 44 729E943G003 Flammability GE/762E933G002 GE New Loads NUTECH Evaluation 48 Control finit Gate Valve liepry Vogt/ Qualified NA 48 B42315 Motor Operator Limitorque Qualified NA 48 SB000 Strip ileaters W.B. Driver Co./ Qualified NA 48 Core Cooling 29905

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SCR Control Cabinet CTI/ Qualified NA 48 69 *Pg. No. in Nuclear Safety Related Equipment List (Appendix A).

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REQUALIFICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE

• Control Room GE/17' Qualified NA 51 Benchboard control Room GE/14-1/2' Qualified NA 51 Benchboard Control Room GE/12-1/2' Qualified NA 51 Cabinet Control Room G*/8' To Be Requal. Test 51 Vertical Board Control Room GE/6' To Be Requal. Test 53 Vertical Board Control Room GE/5' Qualified NA 53 Vertical Board Control Room GE/4' To Be Requal. Test 51,52 Vertical Board Control Room GE/3* Qualified NA 52 Vertical Board Control Room GE/2-1/1' To Be Requal. Test 52,53 Vertical Board Control Room GE/2' To Be Requal. Test 51,52 Vertical Board Control Room GE/5' To Be Requal. Test 51 Instrument Panel Control Room GE/4' To Be Requal. Test 53 Instrument Panel Control Room GE/2-1/2' To Be Requal. Test 51 Instrument Panel Indicator and Trip Unit GE/N1D To Be Requal. Test 54 3

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mm m m emM M M M M M M M M W REQUALIFICATION DESCRIPTION VENDOR /MODEL STATUS PLANS CROSS REFERENCE

• Relay, Panel Auxiliary GE/liFA Qualified NA 54 Inverter Topaz / Qualified NA 54 N250GWR-125-60 Relay, Time Delay GE/CR2820B To Be Requal. Test 54 Switch GE/CR2940 Qualified NA 54 Timer, Motor Driven Eagle Signal Co./ To Be Requal. Test 54 IIP 50 Series Contactor GE/CR105/CR205 To Be Requal. Test 54 Switch, Pushbutton Cutler-Ilammer/ To Be Requal. Test 54 10250T1 Relay, GPI Agastat To Be Requal. Test 55 Relay, Panel Auxiliary GE-PSMP/11MA To Be Requal. Test 55 Square Root Converter Bailey Meter /7000 To Be Requal. Test 55 Series Power Supply GE/9T66Y987G03 To Be Requal. Test 55 Sunener Bailey /7000 Series Qualified NA 55 Alarm Bailey /7000 Series Qualified NA 55 Temperature Monitor Riley Inst./Model 86 Qualified NA 55 Controller Bailey /7000 Series Qualified NA 55 Switch Electro Switch / Qualified NA 55 Series 40 Filter, Inverter Powermark/3174 Qualified NA 56 Sq. Root Extractor Bailey /7000 Series To Be Requal. Test 56 Millivolt Converter Bailey /7000 Series Qualified NA 56 GE/ Assembly (SB-9) NA 56 g Switch Qualified C

r+

(;)

• Pg. No. in Nuclear Safety Related Equipment List (Appendix A).

mm m M M M M M M REQUALIFICATION STATUS PLANS CROSS REFERENCE

• DESCRIPTION VENDOR /MODEL MeterMaster/180 type To Be Requal. Test 56 Meter Range Switch GE/ Assembly To Be Requal. Test 56 Log. Radiation Monitor GE-NID/ To Be Requal. Test 56 Trip Auxiliary Units GE-NID/ To Be Requal. Test 56 Switch Electroswitch/ Series 40 Qualified NA 56 Switch, SBM Control Qualified NA 56,57 GE/SBN Wide Range Monitor-MSV GE-NID/ To Be Requal. Test 57 Local Panel GE/72" Qualified Test Completed 12/4/80 NA Local Panel GE/48" Qualified Test Completed 12/4/80 NA Local Panel GE/30" To Be Requal. Test NA C

e+

ff) *Pg. No. in Nuclear Safety Related Equipment List (Appendix A).

g

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