ML18283B547

Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A

ML18283B547
Person / Time
Site:	Browns Ferry
Issue date:	10/10/2018
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML18283B547 (70)

Text

RESPONSE TO NOVEMBER 18, 1977, LETTER FROM EDSON G. CASE TO GODWIN WILLIAMS, JR.

"ELECTRICAL CONNECTOR ASSEMBLIES" This response provides the environmental qualification information for the electrical connectors used in the Browns Ferry Nuclear Plant, as requested by the November 18, 1977, letter from Edson G. Case to Godwin Williams, Jr., which references IE Bulletins 77-05 and 77-05A, dated November 8 and November 15, 1977, respectively. Also, this response includes TVA's justification for continued operation of the facilities without creating undue risk to the health and safety of the

.pub3.ic, This response is divided into the following:

Part I Identification of Systems, Components, and Associated Electrical Connectors Required to Function to Mitigate Design Basis Events.

Part II Environmental Qualification of Electrical Connectors Part III Justification for Continued Operation

Part I Identification of Systems, Components, and Associated Electrical Connectors Required to Function to M.tigate Design Basis Events, Table 1 lists the- safety systems and components required to function to mitigate a postulated design basis event or accident outside containment.

Those systems containing electrical connectors are so designated in this table. These systems or portions of systems and components have been categorized as being either inside primary containment or outside primary conta'inment. Table 2 lists those:electrical connectors for each Browns Ferry unit that are inside the primary containment and are a part of a safety system as listed in Table 1. Table 2 identifies the electrical penetration through the primary containment that each electrical connector is located on, the type of connector, the number of wires to the connector, the system whose circuits pass through the connector, the system component associated with the circuits, and the function of the circuits. Table 3 lists those electrical connectors for all three Browns Ferry units that are outside the primary containment and are a part of a safety system circuit.

Only those safety systems which are required to function to mitigate a postulated design basis event or accident outside containment where the event itself could adversely affect the ability of the system to perform its safety function have been considered and listed in Tables 2 and 3.

For units 1 and 2, only one type of connector is used inside the primary containment in the identified safety circuits. This connector was supplied by Physical Sciences Corporation and is an integral part of the penetration.

It has '.g8 pins, has gold-plated surfaces on both the pins and the female receptacles, utilizes a Neoprene '0'ing as a sealing surface where the plug shell and 'receptacle shell interface, and has the insulated conductors potted in the shell. Both the plug shell and the receptacle shell are metallic.

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For unit 3, two types of connectors are used inside the primary containment in identified safety circuits. These were supplied by Bendix and are similar to each other in design:

Part No. 10-214636-78S or P, 14 contacts (2Nos.l6, 12Nos.8);

and Part No. 10-214628-51S or P, 12 contacts (Nos.12).

The types of connectors used outside of the primary containment in identified safety circuits are of various types as shown in Table 3.

Page 1 of 3 t

TABLE 1 SYSTEMS AND COMPONENTS REQUIRED TO FUNCTION TO MITIGATE DESIGN BASIS EVENTS X., INSIDE PRIMARY COMTAINMEiVZ (+ Denotes Systems, with Connectors)..

, inboard Main Steam Isolation Valve Circuits

,~Automatic Depressurization Relief Valve Circuits

<nboard Containmeht Isolation Valve Circuits (See note 1)

~Oxygen and Hydrogen Monitoring Systems

%uppression Pool to Drywell Vacuum Breakers

.Wecirculation System Suction and. Dis'ahaxge Valves (See Note 1)

Residual Heat Removal System Head. Spxay Plow'ontrol.. Valves (See Note 1)

"High Pressure Coolant Injection System Steam Supply Va1ve (See Note 1) reactor Core Isolation Cooling System Steam Supp+ Valve (See Note 1)

XX. OUTSIDE PRIMARY CONTAINMENT

.A. Xnside Secondary Containment (~ Denotes Systems with Connectors)

%fain Steam Xsolation Va1ve Cixcuits (See Note 2)

'"Automatic.Depressurization Relief Va1ve Circuits (See Note 2)

'".Containment Xsolation'alve Circuits (See Note 2)

• Oxygen and. Hy'drogen Monitoring Systems (See Note 2) 4 IQf and. 480 V Boards (See Note 3)

Diesel Generations and. Process Auxiliaries (See Note Q) 4 le and. 480 V System Circuits ll 250 VDC.System Circuits Control Bay Ventilation System Circuits (See Note 4)

Coxner Room'(Elev 519) Ievel Switch Circuits (See Note p)

'%adiation Monitoring Systems

~- Main Steam Vault

~- HIE SH Efl'lucnt

+- ROCCL'I

"- RON 1>JTlucnt

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TABLE 1 CONT.)

Diesel-Generator Shutdown Board. Room Ventilation Sysbem Circuits

',(See Mote 4)

• RCIC Cix'cuits (See Mote 6)

Circuits for 0thex Essential Systems (See Note 7)

Automatic Depressurization System Primary Containment Isolation

-Containment Inerbing Reacbor Build.ing Isolation Reactor Building Vacuum Relief Standby Gas Treatment RE1R

- R1BSW

- RHR Room Coolers

- RECT

- CS

- CS Room Coolex's HPCI Reactox Protection System (Excluding Neutron Monitoring System, Control Rod Drive and Position Indicating Systems)

Reactor Building Closed Cooling Mater Fuel Pool Cooling Reactor Water Cleanup (Isolation Punction Only)

Torus Water Level and. Temperatuxe

'. Control Bay The control bay environment is controlled. by the control bay ventilation system. The environment for ecLuipment within the control bay is no more severe during design basis events than that to which. it is exposed. hurri.ng normal unit operations.

~ C. Unit 1, 2, and. 3 Diesel-Generator Shutdown Board. Rooms The diesel-generator shutdown board. room envixonments are control.ed.

by the board. room ventilation sysbems. The envixonment for equipment within these board. rooms is no more severe during design basis events than that to which they are exposed. during normal unit operation.

i'age 3 oi TABLE 1 (CONT.)

Notes:

1 ~ 'onnections at motor operated valves were excluded since these connections were qualified. in conjunction with qua1ification of the valves and.

associated. motor operators.

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2. Circuits for any safety-related. components outside containment were investigated.. Xn addition, circuits outside containment serving safety-relatecL components which are located. insi.de containment were investigated..

Pailure of these components that are requixed. for onsi<<power distribution was analyzecL previous. See "Concluding Reporb on the Effects of Postulated. Pipe Pailure OutsicLe of Containment for Unit 1

,of the Browns Perry Nuclear Plant" BED-TM-PZ1 (Octobex 1$ , 1973) ancL "Concluding Reporb on the Effects of Postulated. Pipe Pailure Outside of Containment for the Browns Perry Nuclear Plant Units 2 and. 3" DED-TM-PZ2 (March 1, 3.974).

These circuits were investigated. for any exbensions outsicLe of the control bay or shutcLown board. rooms into the boundari.es of secondary containment.

5. These rooms contain vital HPCX, RCXC, CS, and. RHR equipment. The level switch circuits investigabed. are those which waxn of floocLing internal to these rooms.

6. Xn terms of function and. objective, the RCXC system is not actu~ a safety system. However, with regard. to engineering anuses, fabrication, and. erection processes, and. quality assurance. control E

and. documerrbation, this system received. the same attention as the safety-related. systems. Por this reason, RCXC was evaluatecL using the same criteria as for the safety-related. systems.

7. The investigation includes any wall sockets or wall power ou'blets associ.ated, with these circuits.

Page 1 of 6 TABLE 2 UNIT 1

'>> PENETRATION CONNECTORS INSIDE.PRIMARY CONTAINMENT MANUFACTURER PHYSICAL SCIENCES,"48 PIN, NO. 12 PLUG NO. 6448-2 RECEPTACLE NO. 6445-2 e ~ I I~*

Penetration Connector No. of No. No.* Svstem ~Com onent Penn@ion 'Wires G2-2G Recirculation Discharge FCV-68-79. Logic 7 Recirculation Suction FCV-68-77 Logic 7 Recirculation Discharge FCV-68-79 Logic 2 G3-3G Relief Valve PSV-1-30 Power 2 Hecixculation Dischaxge FCV-68-79 Logic .2 HPCI Steam Supply FCV-73<<2 Logic 7 G4-4G RHR Head Spray FCV-74-78 Logic 7 Recirculation Sampling FCV>>43-13 Power 8; Logic 5 MS Drain FCV-1-55 Logic 7 X57CU Letdown FCV-69-1 Logic 7 G5-5G Relief Valve PSV-1-5 Sol Valve Powex e

G7-7G Main Steam .Xsolation FCV-1-14 Logic 2 Main Steam Xsolation FCV-1-37 Logic 2

,0 G,8-8G Main Steam Isolation Main Steam Isolation FCV>>l-14 FCV-1-26 Powex 8: Logic Power 5 Logic 9

9 Main Steam Isolation , FCV-1-37 Power 8c Logic 9 Main Steam Isolation FCV-1-51 Power 5 Logic 9 RHR Letdown Supply FCV-74-48 power 8c Logic 11 G9-99 RNCU Letdown KS-69>>1 Logic EC G4-4G . Relief Valve PSV-1-19 Power 2 Relief Valve PSV-1-33.,- Power 2 G9-9G Main Steam Xsolation FCV-1-14 'ogic. 2 Main Steam Xsolation FCV>>1>>26 Logic 2 Relief Valve PSV-1-22 Power 2 Relief Valve PSV-1-34 Power 2 ED H2E EK 76-39 Xnstx umentat ion 4 02E OE 76-43 . Xnstrumentation G4-4G RHR Letdown Supply FCV-74-48 Logic HCIC Steam Suoply FCV-71<<2 Logic 7 G6-6G Drywell Equipment Sump FCV-77-143 Powex &: Logic G7-7G Main Steam Isolation FCV-1-26'CV-1-51 Logic 2 Main Steam Xsolation Logic 2

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Page 2 of 6 TABLE 2 (CONT. )

'UNIT l >> CONNECTORS INSIDE CONTAINMENT Penetration Connector No.

No. No.* ~Sseem Comoonent Punction 0

oX'13.res

. a8-8G Main Steam Isolation PCV>>1-37 Logic 2 Main Steam Isolation PCV-1<<51 Logic 2 G9-gG Recirculation Suction PCV-68-1 Logic Recirculation Discharge PCV-68-3 Logic ll7

• The penetrations have connectors on both ends, only 'the inboard connectors are listed since they experience the worst environment.

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Page 3 of 6 TABLE 2 "(CONT.)

UNIT 2 PENETRATION CONNECTORS INSIDE PRIMARY CONTAINMENT MANUFACTURER - PlESXCAL SCXENCES, 48 PIN~ NO. 12 PLUG NO. 6440-2 RECEPTACLE NO.'445-2 Penetration 'Connector -No. of

'o. No.* System ~Com onenb Function 'I(ines EB G2-2G Recix culation Discharge FCV-60-79 Logic 7 Recirculation Suction FCV-68-77 Logic 7.

Recix culation Discharge FCV-68-79 Logic 2 Relief Valve PSV-1-30 Power HPCI Steam Supply FCV-73>>2 Logic G4-4G RHR Head Spray FCV-74-78 Logic 7 Recirculation Sampling FCV-43-13 Pointer 5 Logic Main Steam Drain FCV-1-55 Logic RWCU Letdown FCV>>69-3., Logic '7 Relief Valve PSV-1-5 Powex Main Steam Isolation FCV-1-14 Logic 2 Main Steam Isolation FCV-1-37 Logic 2 G8-8G Main Steam Isolation F CV-3.>>14 Logic 9 Main Steam Xsolat'ion FCV-1-26 Logic 9 Main Steam Isolation FCV-1-37 Logic 9 Main Steam Isolation FCV-1-51 Logic RHR Letdown Supply FCV-74-48 Logic ll9 G9-9G RHCU Letdown ZS-69-1 Logic EC G4-4G Relief Valve PSV-1-19 Power 2 Relief Valve PSV-1-31. Power 2 G9-9G Main Steam Isolation FCV>>1-lip Logic 2 Main Steam Xsolation FCV-1>>26 Logic 2 Relief Valve PSV-1-22 Power 2

'elief Valve PSV-1-34 Power 2 J3-3J H2E H2E-76-j9 Instrumentation 02E 0, 3 Xnstrumentation G4-4G RHR Letdown Supply FCV-74-48 Logic 4 RCE Steam Supply FCV-71-2 Logic 7 G5-5G Recirculation Discharge FCV-68-3 Logic 2 G6-6G Dxywell Equipment Sump FCV-77-14B Power 8c Logic .

Page 4 of 6 TABLE 2 (CONT.)

I UNIT 2 - PENETRATION CONNECTORS INSIDE URINARY CONTAINMENT penetration Connector No.

No. No. * ~Sseem ~Com onen5 pnnceion oi'i'res G7-7G Jfain Steam Xsolation rCV-1-26 Logic 2 Main Steam Isolation I'CV-1-51 Logic 2 G8-8G Main Steam Isolation PCV-1-37 Logic Main Steam Xsolation 1'CV-1-51 . Logic G9-9G Recirculation Suction FCV-68-1 Logic Recirculation Discharge PCV-68-3 Logic

• The penetrations have connectors on both ends, only the inboard connectors are listed since they experience the worst environment.

I Page 5 of 6 TABLE 2 (CONT.)

UNIT 3 CONNECTORS INSIDE PRIMARY CONTAINMENT MANUFACTURER - BENDIX penetration Connector '2 No.

No. No. ~l e ~S stem ~Com onent Punction of'ires ZA Jl 1 HPCX Steam Supply PCV-73-2 power J6 1 Recirculation Dischaxge PCV-68-79 Logic J7 . 1 Recirculation Discharge PCV-68-79 Power 3

. Recirculation Suction PCV-68-77 Power 3 Main Steam Drain PCV-1-55 Power 3 J8 RWCU Letdown PCV<<69-1 Power J9 1 RHR Head. Spray "PCV-74-78 Power RHR Letdown Supply 'Pcv-74-48 Powex Jl 2 Relief Valve PSV-1-18 Powex J2 2 Relief Valve PSV-1-41 Power J3 2 . Relief Valve PSV-1<<5 Power J7 2 Recix culat ion Discharge PCV-68-79 Logic J8 2 Recirculation II Discharge Pcv-68-79 Logic 2 Suction Pcv-68-77 7 2 HHCU Letdown PCV>>69-1 Logic 7 E5?CU Letdown. ZS-69>>1 Logic l)

J12 2 HPCX Steam Supply PCV<<73-2 Logic 2 RHR Head. Spxay Pcv-74-78 Logic Recirculation Sampling PCV-43-13 Powex &; Logic J19 2 RHR Letdo~rn Supply Pcv-74-48 Logic J20 2 Main Steam Xsolation PCV-1-14 Power 8 Logic J21 2 Main Steam Xsolation PCV-1"26 Power h Logic I

J22 2 Main Steam Isolation -

PCV-1-37 Power &, Logic 2 Main Steam Xsolation PCV-1-51 Power 8o Logic J29 . 2 Main Steam Drain PCV-1-55 Logic 2 Mai.n Steam Isolati.on PCV-1-14 Logic 2 Main Steam Isolation PCV>>1>>37 Logic 2

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UNIT 3 - CONNL'CmI.'Ott'NSII)V. I'I<'EIIAIIY.

CONTAXHIILEN'I,'cnetxation Connector No.

No No 'I'yye ~SS3i oil>> ~Com onent I"unction of'lire!>

>> ZC J16 2 Relief Valve PSV-1-3.9 Power J18 2 . Relief Valve PSV-1-22 Powex 2 Relief Va3.ve PSV-1-34 2 Power'CV-1-14 25 2- .Main Steam Xsolation Logic 2

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Main'team Xsolation I"CV-3.-26 Logic 2

'l J3.3 2 HP-"(6-39 Xnstx umentation 4 042 02L'-76-43 Xnstrumentation 3 Logic,

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>>I Ii 16 Main Steam Xsolation 13CV-1-26 2 Main Steam Xso3.ation I'CV-3.-53. Logic 2

<<>>3 ~1 J3.. 2, Recirculation Dischar ge PCV-68-3. Logic J2 2 Recirculation Discharge I'CV-68-3 Logic

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t3 J9 2 HEIR Letdown Supply .- I'CV-74-48 logic

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l J10;2 RCXC Steam Supply I"CV-71-2 Logic, Recirculation Discharge PCV-68-3 Power h Logic Drywel3. ZtIuipment Sump I3'CV-77-14B Power 8 Logic 25 Main Steam Xso3.ation I3'CV-1-37 Logic Main Steam Xsolation I'CV-1<<51 Logic 2

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>>

.J4 Recirculation .Dischar'ge rCV-68-1 Power Recirculation Discharge 13CV-68-3 Power

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HCXC Steam Supp3.y Power I'

J7 1 Recirculation Discharge I"CV-68-3 -

Logic

1. NOTE: Type 3. >> Bendix Part No. 10-214636-78S ox P, 14 Contacts (2Nos.J6  : 12Nos.8),

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Type 2 - 13endix Part No. 10-214628-51S or P, 12 Contacts (Nos'.12)',

NOTE: The penetrations have connectors on both ends that: are not: part of the pressure boundary, only the'inboard connect:ors are listed 'since they experience the worst environment.

4 Page 1 of TABLE 3

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CONNECTORS OUTSIDE OF CONTAINMENT No. of Temperature 0 F Devices/ Environ-tern Function Unit Unit Manufacturer ~Dee1 n ment Main Steam 'nstrumentation .',2,3 Amphenol B2-816 350 300 Line Rad Mon Reactor Water Isolation 1,2,3 2 Amphenol MS3106-A-20-4P 257 170 Cleanup and MS3102-A-20-4S Primary Containment Main Steam Isolation 1,2,3 16 Amphenol MS3102-A-20-4F 257* 550 Line Leak 16 Amphenol MS3102-A-20-4S Detectors & Pri Containment

'

RHR Heat Exch Instrumentation 1,2,3 6 Amphenol UG1213/U 185 150 Disch Rad'on Amphenol UG932/U

'50 2 150'85 2 Amphenol UG260/U 150 Raw .Water 'Znstrumentation 1,2,3 Amphenol UG1213/U 185 150

-Effluent Amphenol UG260/U 185 150

';Red Mon Amphenol UG932/U 350 150

,.Reac Bldg Instrumentation 1,2,3 Amphenol UG1213/U 185 115

'Closed Cool Amphenol UG932/U 350 115 r Effluent Amphenol UG260/U 185 115, t

HPCI Steam :Instrumentation 1,2,3 16 Amphenol 3106A-20-4P 257 550

~ Leak Detectors 16 Amphenol- 3102A-20-4S

'.RCIC Leak s'~Instrumentation 1,2,3 16 Amphenol 3106A-20-14P 257* 550 Detectors 16 Amphenol 3102A-20-4S RCIC Backup Control Center Test 1,2,3 '1 Amphenol 69-OB-18-15 '57+'15 Fuel Pool Instrumentation 1,2,3 1 Amphenol Rept 69-OR16-105-C100 257 115 Cooling Plug 69-6R-16-10P

+See Part II, Section C

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Part II Environmental Qualification of Electrical Connectors A. Ori inal Testin The original'qualification tests (i.e., pressure, temperature) conducted on the Browns Ferry penetrations and associated connectors were described during a meeting with NRC representatives on November 16, 1977. These tests did not include qualification for the electrical connectors for the environment resulting from a postulated design basis event or accident outside~containment.

B. Steam Environment Test Based on the discussions held during the November 16, 1977, meeting and on the November 18, 1977, letter, TVA decided to conduct a preliminary environmental test on selected samples of the electrical connector types used in containment in identified safety systems to determine if they could continue to function in a steam environment of a design basis event.

These samples were taken.,from the plant stock of spares and were not thermally or radiation preaged. Attachment 1 describes the test proce-dures used, the connector samples tested, I the test facility, the environmental conditions used in the test, the electrical loadings used, and the test results. The actual test conditions exceeded those that would be expected in the case of an actual design basis event for Browns Ferry Nuclear Plant. The electrical connectors satisfactorily passed the steam environment test.

The purpose of this test was to provide a rapid assessment of the performance in a steam environment of the electrical connectors within primary containment.

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C. Evaluation of Connectors Outside Primar Containment The critical electrical connectors outside containment are those that are associated with the main steam, HPCI, and RCIC leak detectors. The postulated accident environment temperature can exceed the design temperature of these connectors. These are identified in Table 3 with an asterisk (*). These circuits are provided to detect and initiate isolation signals in the event of a pipe break. Since the signal to initiate isolation is set at 200 F and is well below the design temperature of 257o F for the electrical connectors, these connectors will have performed their safety function before any potential environmental degradation.

These sensors and associated electrical connectors are not required to function following the initiation of the isolation signal.

D. Evaluation of Radiation Effects The Physical Science and Bendix connectors were specified to withstand a nuclear radiation of 10 R. In actuality, the threshold for damage of organic materials generally is greater than 10 R, with embrittlement beginning above approximately five times this value. The integrated dose to affected connectors would not be expected to exceed 10 R during the time interval in which they are needed following an LOCA, and the exposure from operation to the present time is extremely small by comparison. Therefore, radiation damage to these connectors is not a concern related to operation during the next few months. (See Item E).

E. Tests to .Determine uglified Life Future Additional Tests)

TVA intends to establish the qualified life of all electrical connectors both inside and'utside p'rimary containment used in safety-related

circuits at Bxowns Ferry using the requirements of IEEE Standard 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations." Type testing will be used to establish qualified life with the effects of thermal and radiation aging included. It is anticipated that this portion of the program will be completed within 90 days.

BPS 22 7/25/7>>

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I Attachment 1 Date November 22 1977Unit 0 BFSTER No. 22 Ori piriator J, E. Gibbs Title: TEST X'ROCEDURE POR BROGANS PERRY Cognizant Section Outage CONiNECTORS I ~

Reason for Tes or Exp rim nt':

~ I II iI To test Bendix Corporation type and Phys'ical Science type connectors used in electrical penetrations at Brogans Ferry Nuclear Plant.

Safet Related Non-Safety-Related X

'ransmitted to NGB: Date . ~ PORC Review:

November 22, 1977.

'equired safety review and safe+y Date analyses (10 CFH 50.59) have been 'pproved:

completed for Plant Su" erin- encent A. Unreviewed safety oucstion B. Technical specification limits ~ Authorization to Per.o..:

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November 22, 1977 Date Plant Superintendent Date

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Page 1 1

BF STER 22 ll/25/77 TEST PROCEDURE FOR BROWNS FERRY CONNECTORS V

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1. ,Scope s To test connectors: used in electrical pene'trations for units 1 and 2 at Browns Ferry and to test typical connectors used for unit 3 at Browns Ferry for ability to withstand the steam temperature pressure- profile resulting from a LOCA or a pipe break.

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2. Material to be tested shall be:

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' 48-pin connector Physical Science type contained in electrical penetration type used for Browns Ferry units 1 and 2

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1 12-pin connector Bendix Corporation type 10-214-628-515 used on pigtails out of Browns Ferry unit 3 penetration

3. Test Setup Provide an environmental test chamber with dimensions capable of containing the test specimens (see figure 1). The chambei shall be provided with a pressure gauge and temperature sensors for measuring the temperature inside the test: chamber.

3.1 Connect the pins of the connectors with wires so as to form a sexies parallel circuit which will give a voltage

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~ gradient within the connector as well as simulate a load (see figure 2)

The circuit, shall be loaded to approximately 5 amperes and a voltmeter and ammeter shal'1 be connected to the load.

4. Test Procedure

-4.1 Verify the initial status of the penetration connector and the separate connector for voltage integrity. Megger

'pin to all other pins and shell combined. Check for current continuity through the connector.

4.2 Energize the connectors from a 250 V dc source. Bring the environmental chamber to the initial condition of 150 'F.

4..3 Admit steam into the environmental chamber at flow condition so as to achieve a stabilized temperature of 322 F. Hold this condition for 5 minutes. Record all voltmeter-, ammeter, pressure and temperature readin'gs at each major change in profile and each hour.

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Page 2 BF STER 22

'.11/2S/77 TEST PROCEDURE FOR BRONNS FERRZ CONNECTORS 4 ' Reduce pressure at 0.7 lb/minute to reach 36 psig and 282F in 6P minutes. Then drop the pressure imme-diately to 15 psig (apprximately 250F). Thereafter reduce the pressure at 1.0 lb/hour until atmospheric pressure. is reached at 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> into the test (212F).

4.5 %hereafter drop the temperature at 7Q 0 F/hr pressure until 150oF is reached after at'tmospheric 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sinto the test. The profile curve is figure 3>>

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5. Criteria 5.1 The connector shall carry the required load at not more than 10-o reduction in voltage 'after the full duration of the test.

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~ l tl t

~ 0 3 I I<

i> (

~ g 0~

~,

4

C ldi

~ ~

~, 4 t

)

B22 I= 7+~Jcc ll, t C Kmina4e

. 7~z+f 'ckcrelse For QO~cnufes

/mI n

~

-. J00~

~ZZZF ~ B6psrjr

~

PJ I 25DF 2~~0+ ~ /5pscg drop )I'ps'/g,r" t ~

Z/2F M ~Pm

---= 200F

~ t A'TS / 2 9 < H 6' 8 9-/d // /2 /0 w'/5'C /i'-~~ /'/ ~~ >/ g 'cg gc/ ~ \

1 ~ .

jme-.Pours .. ~ ~

't Il

Page 6 BF STER 22 ll/25/77 h

y ~

THIS PAGE DELETED

~ ~

Page 7 BF STER 22 ll/2Z/77 DATA COVER SHEET 8E~IOI This data package includes test data sheets.

j

'Instrument Calibrated .8anr. ~/ 8 Wi5 X7 Veri.fied By Acceptance Criteria Net

..Yes No Data Takers/Organization e

'e

/ v P1yye~~g O'>i~ Ctp>o)

Qrzi Jla g<

Dates Test Performed Reviewed by Cognizant Engineer Reviewerl by Re"cite Section Snperv or 4/< 6 Iy zy/pp Reviewed by Quality Assurance Supervisor tt ~g 7)

OFT( IlGL<L COR'

Page 8 BF STER 22 la -~5/77

!'Q STER 22 TEST DATA/BROWS FERRY Co~iCTORS

/ pin Connocton STEP "'TEM RESULTS BY/DATE 4.l.a Verify propeZ i

hook up for connector (tes t tern Ii2, figure 2, for 48- pin OK 'i.~/~

Verified connector; "test item fr'1, figure 2, for 12-pin connector) 4.1.b Meggor: pin combined o all pins and shell 5'hms

'1 pin to shell 4.1.c Verify current I n continuity OK 4.2.a Energize connector from nominal 250 VDC source (verify) OK Veri fiedc~j 4.2.b Load voltage Q 4'7. 0 Volts Set load for connector so as to give pggi load current of 5.0 + 0.5 amps (initial Values) Amps QC 4.2.d Initial test chamber pressure psig

• L erif-'ed and temperature OF 4.3.a Admit steam,'bringing temperature to W 8'sig 4 /

322 + 5'.

AIso note start time of the test Ve 'fied (to).

i:4S: 4-4.3.b Stabilize temperature and pressure at ~>> .kl /u 322 + 5 F. Vgrified '

• "

4.3.c >Ihen stabilized, record load current and voltage. Load'mps volts Input volts /~/'FFI'GtlAL COPV

Page 9 I \ ~ ~ BF STER 22 11/'25/77 Connector /gwvÃ~tg STEP TTEM ~

RESULTS BY/DATE 4.3 (Continued) '

4.3.d Maintain in stabilized condition for . 9'7 Amps /rz r 5 minutes; record load current and voltage at end. Load N 4-7 Volts Tnput OFF'CtlkII. CGA I

~ II It I I

I II Ik ~

~ ~

'

Page 10 BF STER 22 11/25/77 Connector STEP ITEN RESULTS BY/DATE.'

' (4

!

4.4.a Reduce pressure at o.7 psig/

minute to,"282 F at 36 psig

'in one hour; record initial gcstamps

'~l 1

~ 4 load current and voltage. /o~s',o4'time . '7 verif'ed load g<-7~volts I

Repeat, at three 5 input . ~~ volts minute inter'vals /r~c"- s time 7/ 7 /,

amps verif ed load ~QLvolts input g~d . volts

/>~os: s'ime

p. q 4-amps veri ied load pg j-. lavolta input ~~ volts rr gq:ps'time

~~~gamps veri ied load ~S' volts s input a.s.O volts

.. 4.4.b Drop pressure immediately to 150 sig. Record load current and oltage.

SAa</J hZ NS'0 ~ //SPSsy

~z: ol time '7>1 / i'd&

/K'. ct/zP/zv veri ied

'oad ~pampa~gb~volts input >~ volts 4.4.c At hourly intervals; +reduce 4 the pressure by 1.0 0.5psig

. Record time of pressure reduction, new pressure (psig),

load current and voltage. Repeat

'for 15 hours until 212 F at atmospheric piessure is obtained.

OFRGIIAL CGPV t 4

4

4

~

J skye BF STER 22 Connec tor 11/2S /77

~ STEP RESULTS BY/DATE 4.4.c (Continued)

Loqd 2 4'F' V

/z~0

'OZ ~ T gg g la p 4.'l Load 2 O'-K 4'7 V

/~z':/

Load 2'tI 9'. 3 V

~RO T

A

</

Load -i g,j

~

~

l7'05 '<9 T

/&. C'p W<~ A Load

'tput ~>MDIV gg.'og,'.

~

%E7 I

/

A OFF~CQL CO~V ~

Load 4 ~+'+ V Input Z 6& V

r I

......., ra rr~>>

~ ~

Hl ST.jik dZ li

~ ~

~ ~

zx/2s/77

~ ~

I ~ $

STEP ITEII RES OI.TS 8 t;DATE lt,l<. c (Continued)

')r. ~ .,!Ti~

I '

4$ :. 'I Xnput

'9 7.w I

p! p5 .'gq T ~Wi' ~i~

~

(I 7

7.oad F96. 9 Xnpu t C. ~~-p 7A IC tI/~~/z r,~ r, I,jj I,

~ rr ~,C .

3'npu t pad 2!'0  ! a ~(!" ~

'/, 7 A, Xnput V P+ /( /iQ E ~

r.<<a R'/s-, ~ v

'Xnput .. 5 0 'I ~

8 d! d'K! PV p

/84 A r

i ~a ~'/<0 v

~ ~

~ 4 Input 2 5 Ir'

t Page 13

~ ~ ~ ~

BF STER 22 11/25/77 Connector&A iX

,>>, STEP T.TEN RESULTS BY/DATE

~G/.'!

A 4.4.c '(Continued) /u a),

p Load 1'npu t 6 /4 I . p

~

Load Xnpu t V $ ~

..Load N c/9 ~

'7 V Xnput Qg$ gg c((rc rr/~ 0/>

7' put 4.5 At hourly intervals, reduce  !

temperature by 7-'g F/hr. Record

'ime of temperature reduction, net temperature, load current and voltage. Repeat until 150 F is reached after 24 hours into the test.

0;"-Hc/AIL QQP";

~ ~ l)LI 6 LL,6. *E

.Connector 11/25/77 STEP TTHIf REsm:rs SY/DA1E 4.5 (Continued) 9.'O<.'~ T I

'.4" . ~

" ~

'Q,O'/ I temp

~ ~

I

~

./

~

mad P.'/S. 6 V Xnput; QS 4 V.

.5,'Oa:~V T O

temp

)II

~

/. S-G f.

jI i'/

Load ~'/R0 v I Xnput 54'

~~

i ~ ~

go temp

~,

. P Load ~ $:

'v

~ ~

Xnput II~4 v ~

~

~ temp 4 E7' 24'8; 9' i l.

Input

~ ~

/- temp 4T ~ S' Load

'Input

.2 47. 9'.

os' T emp

,F A

Page 15 BE STER 22

~ ~

~ ~

ll'25/77

'iY' Connector STHP

~g~rnO XTEM Sc'ESULTS BY/DATE 4 ~5 (Continued) 27; 0'o~ ',2 T '7w 7 br' A

Load "Xnput 2 5 d,6 V s

4 Q'7,'//, o9,,' 7 T i~lz.>(,

temp Load Xnput W ~ . V

~ a Test Data Verification: /'7 ZP yp Xnspector/Da 'est Engineer'/Date

~ ~

QFF~It;j 'I. ('Q'9~

r

'

Page T BF STER 22

.'.l/2S/VV

~1

~ '(Q DATA COVER SHEET

~'2 guL Tony This data package includes test data sheets. I i

ll Instrument Calibrated /-

Verified By Da e Acceptance Criteria Met Yes Data Takers/Organization c:/~o 2 p

,f~)

fr~)

/d~

P7,+

~~levy c<., D I~p'Cu(.@ gc)

~~an~ >I.< (j~e)

.

~~@ y a Dates Test Performed Reviewed by Cognizant'Engineer Reviewed by Results Section Supe sor >> Z77g Reviewed by Quality Assurance Supervisor GI"-F'IIQ<g @GPSS

)

Page 8 BF STER 22 11/25/77 STER 22 TEST DATA/BROLlNS PERRY COWiECTORS

~Z-Pin Connector'.1.a ITEM RESULTS */

• Verify proper hook up for connector (te'st item 82, figure 2, for 48-pin ~S'erified connector; test item 81, figure 2, for 12-pin connector) Mli~<Eo 4.l.b Hegger: pin, o all pins and shell J'/

combined pin to shell CS>CcCi C 4.l.c Verify current- continuity OK g;,g,~J ~/~~)

4.2.a Energize connector from nominal 250 VDC source (verify) 0K erified 4.2.b Load voltage ~ O'- Z. Volts ~ & //zc 4.2.c Set load for connector so as to give load current, of 5.0 + 0.5 amps (initial KQu values) 4- YD Amps ~~ ~74/ ///u'QC 4.2.d test chamber pressure 7g 4'9g /r.li(

I'nitial psig and temperature wO ,/ Ver fied 4.3.a Admit steam,'ringing temperature to psig

/'~s 322 + O' erified Also note start time of the test (t0). 3Z Z F.

~- 4$ ." I 4- Start time 4.3.b Stabilize temperature and pressure at time 322 .+. 5 P. erified 4.3.c 0lhen stabilized, record load current and 4 P~ amps 'Fir 4i:',,

voltage.

Load Input volts

Page 9 BP STER 22

, 13;--'25/77

'onnector ~Z 4~ rW S TEP ITEM HY/DATE 4.3 (Continued)

Mahtain in I'tabilized condition for P~ Amps '~>> i1 / Ar, 4.3.d .

5 minutes; record load current and C

~ voltage at endo Load

'Xnput ~wO Qjj~ F(Qgig QOIpp

Page l0 .

BP STER. 22 11/25//7 Connector STEP XTEN RESULTS BY/DATE '

'

.4.4.a Reduce pressure at. os7 psig/

minute toI 282 F at 36 psig

~ I 'in one hour; record initial load current and voltage. g~gz-.a&time

~

~

amps

//7.

verif ed

/ /+rz =c, load.;~cg-g~vol ts Repeat at~ three 5-input

~

.

~~q vol ts minute intervals . Z( oz;gs time //r z.a

.p/ amps veri red load'sv. 'olts

.input ~a/ vol'ts II II I

//'ov:~ time /P7 7//

~

~jc> amps veri 3.ed load ~g-~volts input zWG volts.

p gz ~~time

-. /r/ p amps veri ied load ~g-z~volts

~~n volts

~

input pjf

.. 4.4;b Drop pressure immediately to 150 ps'. Record load current:

angdoltaga. >>I/,~z" yz.. cs/:c otime

z. amps

$7 veri ied P/ /u ~

load ~g s volts input ~~ volts 4.4;c At hourly intervals, + reduce.

the pressure by 1.0 0.5psig

.Record time of pressure reduction, new pressure (psig), ~*

load current and voltage. Repeat for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> until 212 P at atmospheric pressure is obtained.

OFFIIC/AiL QQPY

gJ l BF STER 22

"

Connector j-Z ~gw pa~ 11/25 /77 STEP RESULTS B'i'./DATE 4.4.c (Continued) ~4: IG wl.-] g

. j fze

~ ~

'I

~ I Load Z4-2 'f-N$ 6 V'nput V

/4-;DR."l / T

\~

3 P Load Input ~6 0 .

V H

g. / 6c

~ ~

477 A Load g 0/ E4 V Xnput 8 S'0 V A

.Load ~

7 V Input

'

+'~7 A w~e v Load

'nput

'oad Xnput Z ~ P'

.. Connector STEP 1TEH RESULTS

'.4.c ~.'og. Z~

~ (Continued)

~ ~

I ~

Z ed >+('4 V input - P V

~c':

9'.7 / A Load AVO, 6 V Xnput A~/ / V O'S- A:.

~ - p Load 2~/Q,O V Input .. 50 V e i t

I

~ g, g '5 .'gc/ T

~~

~

end e'7 A 1/.

PVdo v

'

Input V

! d5.'Z9'

'/ 7S A Load V.

Input 7/

~' ~

f. 7'7 Load r.z.s v Input 5'C'

~

~ Page 13 BF STER 22 11'.125/77 4P" Connector c4 f>4 STEP I1TPf RESULTS BY/DATE 4.4.c (Continued) 0)

Load 9 /+ c/

Input I p A

Load Input Load

. Input A

'

Load Input I

4.5 At hourly intervals, reduce temperature by 7> F/hr. Record time oi'emperature reduction, ~II.

new temperature, load current and voltage. Repeat until 150 F is reached after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into the test.

e e  !

J) J.') x i'!!. c.c.

r

,Connector w Z ll./ZS /77 0 ~ ~

• ~

BTBP TTBH RESULTS RY/DATE 4-5 (Continued) ,'OS'C T

'".. ~

j temp 9.7@

~

mad R9P . & V

' O Xnput (I

~l'7 g

/,7'~ A T.oad ~ /Ir 7 V 0

~ 4 v'

/ temp

~ ~

d~4 Xnput, g.4 , g

/- temp

~

~

Load evv

~ ~ ~

Xnput C~ V

((

JL':eeIep./

~4<, e

\ t !

!

OIYlitl,g,g C,Qey /: temp Load ~4/ 4 v

"

Xnput

Page 15 BP STER 22 11/25/77 Connoctor~&Z cps.rr&nJ

'BTHP ITEM RESULTS BY/DATE 4.5 (Continued) 27'emp /// M7/i g A Load

Input 7+D. V gp,'((~,' 7 T temp ~~k)/)

A Load Z YC. bZ V Input v Test Data Veri.fication: b' pg

' g.~ ~r'~ ~~

2.

Engineer/Date 7P'est Q Inspector/D

0

~-

Part III Justification for Continued Operation TVA considers the tests and evaluations described in Part II sufficient to permit 'the continued operation of the facility without creating undue risk to the health and safety of the public for the period it will take to fully environmentally qualify the connectors. This position is based upon the low probability of the events that produce adverse environments, the supplemental testing that demonstrated that the connectors within containment can continue to function in a postulated steam environment, the short time required for critical connectors outside containment to function before exceeding their design temperature, and the connector resistance to a radiation environment.

~ l l 0'