ML17244A207

Responds to 780906 NRC Request for Review of Environ Qual Table for Elec Equip at Subj Facil.Forwards Requested Info & Rev Pages for Initial 780224 Environ Qual Rept.Facil Does Not Use Connectors or Junction Boxes

ML17244A207
Person / Time
Site:	Ginna
Issue date:	12/01/1978
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Ziemann D Office of Nuclear Reactor Regulation
References
TASK-03-12, TASK-3-12, TASK-RR NUDOCS 7812050187
Download: ML17244A207 (51)

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'EGULATOMMNFORMATIONDISTRIBUTION TZM DOCKET NBR: 56'-244 RE GINNA 1 DOC DATE: 781201 RECIPIENT: ZIFZtANN D.L. ACCESSION NBR: 7812050187 ORXGINATOR: WHITE L.D. COPIES RECEIVED:

COI1PANY: RPCHE'STER GAS & ELEC CP LTR 3 ENCL 40

SUBJECT:

SIZE: 31 Res onds to 780906 NRC re uest for review of environ qual table for elec equip at sub facil. Forwards re uested info 6 rev ages for initial 780224 environ 'qual re t. Facil does not use connectors or unction boxes.

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ROCHESTER GAS AHD ELECTRIC CORPORATION ~ 89 EAST AVEI((IE, ROCHESTER, M.Y. I4649 LEON D. WHITE. JR, TC<.I r rrONC VICC PRCSIIICNT ARCA CONC T~n 546-&700 December 1, 1978 Director of Nuclear Reactor Regulation Attention: Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No. 2 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Environmental Qualification of Electrical Equipment R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Ziemann:

This letter is in response to your letter dated September 6, 1978 which requested that we review and complete a table prepared by the NRC Staff summarizing environmental quali-fication of electrical equipment at Ginna. Enclosure 1 contains the information requested completing the NRC format.

In enclosure 2, we have provided revision pages for our initial environmental qualification report, which was submitted by letter dated February 24, 1978.

had not addressed In your September 6, 1978 letter, it was noted that we connectors, splices, and junction boxes.

Splices are now included in both Enclosures 1 and 2. Ginna does not utilize connectors or junction boxes in safety related cir-cuits, therefore they do not appear in our submittals.

Should you have any additional questions, please contact us.

Vexy truly yours,

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Enclosure 2 T.

.rdThe, report regarding environmental qualification of e3,gc<rical equipment which was submitted by letter dated ru>>

Fegggary 24, 1978, for L. D. White, Jr., Rochester Gas and t Electric Corporation to Mr. A. Schwencer, Chief, Operating act Reagtors Branch No. 1 should be revised as follows:

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TIE DELETE ADD Title Page Table of Contents List of Figures List of Tables 26 26 27 27 28 28 29 29 Table 3 (all pages) Table 3 (all pages)

Environmental Qualification of Electrical Equipment R.E. Ginna Nuclear Power Plant Docket No. 50-244 February 24, 1978 Rev. 1, December 1, 1978

TABLE OF CONTENTS Introduction Identification of Necessary Safety Related Equipment 2 A. Events Accompanying a Loss of Coolant Accident 2 B. Events Accompanying a Main Steam Line Break 8 C. High Energy Line Breaks Outside Containment 10 D. Flooding Outside Containment 13 III. Identification of the Limiting Service Environmental Conditions for Equipment which is Required to Function to Mitigate the Consequences of Events Identified Above 14 A. Inside Containment 14 B. Auxiliary Building 16 C. Intermediate Building 16 D. Cable Tunnel 17 E. Control Building 17 F. Diesel Generator Rooms 17 G. Turbine Building 18 H. Auxiliary Building Annex 18 I. Screen House 18 IV. Equipment Qualification Information 19 A. Auxiliary Feedwater Pumps 19 B. Valves 878 A,B,C,D 19 C. Main Steam Isolation Valves 19 D~ Main Feedwater and Bypass Isolation Valves 20 E. Containment Fan Cooler Dampers 20 F. Barton 332 Transmitter 21 G. Foxboro 611 Transmitter 21 H. Foxboro 613 Transmitter 22 I. Instrumentation Terminal Blocks 24 J ~ Cable K. Reactor Coolant System Temperature Detectors L. Safety Related Cable Splices Subject to LOCA and MSLB Effects 27 M. Aging of Equipment Prior to Qualification Testing 27 V~ Conclusions 29

LIST OF TABLES Table 1 Loss of Coolant. Accident Required Equipment List Table 2 Main Steam Line Break Required Equipment List Table 3 Equipment Qualification

LIST OF FIGURES Figure 1 Loss of Coolant, Accident Sequence of Events Diagram Figure 2 Main Steam Line Break Sequence of Events Diagram Figure 3 Plant Layout

e The highest credible temperature that, this type cable could be exposed to would be a 220'F temperature asso-ciated with a DBE in the turbine building. Thus, a failure of this type control cable is unlikely.

Instrumentation cable outside containment for all low level analog signals was supplied by Rome Cable Company, with "Synthenol" insulation covered with glass braid with an overall synthenol jacket. Test reports verify that this cable was heat aged for a temperature of 248'F for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> and the jacket heat aged at 212'F for 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />. This cable is not required for safe shutdown of the plant during a hlSLB accident in the Intermediate Building. The safety related instrumentation cable used inside containment was supplied by Coleman Cable and Wire Company. The insulation is silicone rubber with glass jacketing. Silicone rubber insulated cable was qualified for LOCA conditions as described in WCAP 7410-L.

K. Reactor Coolant S stem Tem erature Detectors The reactor coolant system temperature detectors (RTD) are not required for a loss of coolant accident. In a steam line break accident, low Tave plus high steam flow plus a safety injection signal will close the main steam line isolation valves. As described in Section IV.C above, for a break upstream of the non-return check valves, which includes all breaks inside containment, closure of the main steam isolation valves is not required.

26

For breaks downstream of the check valves, closure of the main, steam isolation valves is required, however, in this case the RTDs are not subjected to an adverse environment. Therefore, the RTDs do not require environ-mental qualification to provide their required safety function.

L. Safet Related Cable S lices Sub'ect to LOCA and MSLB Effects Cable for the safety related pressurizer instrumentation, the core deluge valves, MOV 852 A and B, and the 480V power cable for the fan coolers utilizes Raychem Thermo-fit, WCSF-N, heat shrink sleeves on the splices subject to LOCA and MSLB effects. These sleeves have been qualified in tests which exceed the worst case Ginna accident environments. Refer to Franklin Institute Research Laboratories Test Report F-C4033-3. This report has been submitted to the NRC by Raychem Corporation.

M. A in of E ui ment Prior to Qualification Testin Electrical equipment in general consists of components and materials with widely diverse physical properties.

When establishing the design lifetime for such equip-ment, a program for accelerated aging is appropriate only when there is sufficient, empirical data or a well understood aging mechanism upon which to base a quanti-27

's.

tative estimate. Such bases exist for thermally accel-erated aging of motor and cable insulation. When elec-tronic components are involved, such as in transmitters I no such bases exist and accelerated aging is not appro-priate. This type of equipment normally exhibits a failure rate of the "bathtub curve" type. That is a period of relatively high failure rate early in life, "infant mortality", followed by a long period of low, constant, random failure rate, which finally terminates at what might be called the "end of design life", charac-terized by a very rapidly increasing failure rate.

The objective of aging is to put samples in a condition equivalent to the end.-of-life condition. When the equipment or component is of the first type described above, this objective is met by a period of thermal aging, which, based on the data available, can be shown to be equivalent to the design lifetime under normal operation conditions. qualification tests for motor and cable insulation used in the Ginna Nuclear Plant were conducted using this approach as described in references.

For equipment of the second type there is a large amount of evidence to indicate that after an initial "burn in",

sufficient to eliminate components which will be subject to "infant mortality", the failure mechanisms are truly random. That is, the probability of failure, per unit time, is low and constant, and most importantly there is no particular predominant failure mechanism.

28

Under these conditions there is no coupling between the design basis event for which the equipment is to be qualified and the age of the equipment. For such equip-ment, the "end-of-life condition" is identical with the condition immediately after "burn in". At the Ginna Nuclear Plant the period of operation of such equipment has been long enough to assure that "burn in" has been accomplished. In addition periodic testing and mainte-nance assures that any equipment degradation is detected and thoroughly investigated for corrective action.-

V. CONCLUSIONS It has been determined that the facility will adequately respond to the design basis events as presented in this report and is acceptable for continued opeiation.

29

0 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR & MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

1. Mechanical lA, 1B Diesel Generators Area 04 Diesel: ALCO 251F *110'F Atm Arab Not exposed to DBE and Auxiliaries Elev. 253 Generator: Westinghouse 40C Max. Amb. Environment 1900 KW 70C Rise Gilbert Spec RO-2239 DEMA Standard Vendor Data 1B, 1C Safety Injec- Area f2236'ump: Worthington 3-NTS- 104 F Atm Amb Not exposed to DBE tion Pumps Elev. 811 40F Max. Amb. Environment Motor: Westinghouse SOC Rise Westinghouse Spec 509-US AFDP, 676370 & 676427 "

Thermal Epoxy lA, 1B Containment Spray Area 62 Pump: Ingersoll Rand 104'F Atm Amb Not Exposed to DBE Pumps Elev. 4xllA 40C Max. Amb. Environment Motor: Westinghouse 444TS SOC Rise Westinghouse Spec TBDP, Class B Insul 236'A, 676370 & 676427 1B Residual Heat Area 42 Pump: Pacific SVC-6L 104'F Atm Amb Not Exposed to DBE Removal Pumps Elev.

253'A, Motor: Westinghouse 445TS 40C Max.Amb. Environment 219'A, TBDP, Class B Insul SOC Rise Westinghouse Spec 676370 & 676427 1B, 1C, 1D Service Area 45 Pump: Worthington 20H- 104'F Atra Amb Not Exposed to DB Water Pumps Elev. 500-WZ 40C Max.Amb. Environment Motor: Westinghouse 509- 105C Rise Westinghouse Spec UPH ABDP, Class F 676370 & 676427 Insul lA, 1B, lC, 1D Contain- Area Ol252'an: Sturtevant 8530-D 80 pmig, 320F NCAP-7343-June, 1969 Motor: Westinghouse 588.5-IIII ment Recirc. Units Elev. 2x10 RADS, WCAP-7410-L-Vol.

CSP, Thermal Epoxy 100% RH WCAP-7744-Vol.

WCAP-9003-January, 196!

• ATM Atmospheric Pressure, AMB Ambient Relative Humidity'

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR & MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

1. Mechanical Cont'd lA, 1B Motor Driven Area N3 Worthington 2-WTF-87 104'F Atm Amb Gilbert Spec RO-2267 Auxiliary Feedwater Elev. Motor:Westinghouse 505-US 40C Max.Amb. Westinghouse Spec Pumps ABDP, Thermal Epoxy 80C Rise 676427 272'ump:

253'A, See Text, Section -A lB Component Cooling Area f2 Pump: Ingersoll Rand 8SD 104'F Atm Amb Not Exposed to DBE Water Pumps Elev. Motor: Westinghouse 444TS 40C Max.Amb. Environment TBDP, Class B Insul 80C Rise Westinghouse Spec 676370 & 676427 1C, 1D Standby Auxiliary Area 56 Pump: Ingersoll Rand 120'F Atm Amb Not Exposed to DBE Feedwater Pumps Elev. Motor: General Electric 50C Max.Amb. Environment 272'.

Type K'Class B Insul 80C Rise Gilbert Spec 520 & 711 Valves MOV 825A, B Safety In- Area 42 Limitorgue Smb-00 90 prig, 320F Not Exposed to DBE jection Suction from Elev. Reliance, Class B Insul 2xlo RADS Environment 236'WST 100 o RH WCAP 7410-L Vol. I WCAP 7744 Volume I MOV 826A,B,C,D Safety Area 52 Limitorque Smb-00 120'F Atm Amb Not Exposed to DBE Injection Suction from .Elev.'253'eerless, Class B Insul Environment BAST Westinghouse Spec 676258 AOV 836A,B NaOH Addition Area 42 Copes Vulcan 150'F Atm Amb Not Exposed to DBE to CS Pumps Discharge Elev. 236'-100-60 Environment Westinghouse Spec 676270 Vendor Data

0 0 4 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR & MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

2. Valves Cont'd MOV 841, 865 Accumulator Area gl 236'imitorque Smb-2 90 prig, 320'F WCAP 7410-L Vol. I Discharge Valves Elev. Reliance, Class B Insul 2xl0 RADS WCAP 7744 Volume I 100% RH WCAP 7153, June 16, 1975 Letter to Pu e from White MOV 850A,B Containment Area 51 Limitorque Smb-00 90 prig, 320'F WCAP 7410-L Volume I Sump B Isolation Valves Elev. 219'eliance, Class B Insul 2xl0 RADS, WCAP 7744 Volume I 1008 RH WCAP 7153 MOV 851A,B RHR Pump Area 02 Smb-00 120'F Atm Amb Westinghouse Spec Suction From Sump B Elev. 236'imitorgue Limitorque, Class B Insul 676258 MOV 852A,B RHR Core 230'rea 51 Limitorgue Smb-l 90 prig, 320 F WCAP 7410-L Volume I Deluge Valves Elev. Reliance, Class B Insul 2xl0 RADS, WCAP 7744 Volume I 100% RH WCAP 7153 June 16, 1975 Letter to Purple from White MOV 856 RWST to RHR Area $2 Limitorque Smb-00 90 prig, 320 F Not Exposed to DBE Pumps Suction Elev. 236'eliance, Class B Insul 2xl0 RADS, Environment WCAP 7410-L Volum~

100% RH WCAP WCAP 7744 Volume 7153

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MOV 857A,B,C RHR Pump Area 52 Limitorque Smb-00 90 prig, 320 F Not Exposed to DBE Discharge to SI and CS Elev. 236 Reliance, Class B Insul 2xl0 RADS, Environment Pumps 100% RH WCAP 7410-L Volume I WCAP 7410 .Volume I WCAP 7153

0 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR Sc MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

2. Valves Cont'd MOV 860A,B,C,D CS Pumps Area 52 'imitorque Class Smb-00 Insul 90 prig, 2xl0 320 F Not Exposed Environment to DBE Discharge Valves Elev. 236 Reliance, B RADS, 100% RH WCAP 74l0-L Volume I WCAP 7744 Volume WCAP 7153 MOV 878B,D High Head Area gl Limitorque Smb-00 120'F Atm Amb Westinghouse Spec SI to RCS Cold Legs Elev. 236'eerless, Class B Insul 676258 See Text, Section IV-B MOV 896A,B RWST Isola- Area 52 Limitorque Smb-00 120F Max.Amb. Not Exposed to DBE tion Valves Elev. 236'eerless, Class B Insul Environment Westinghouse Spec 676258 AOV 3516, 3517 Main Area 03 Attwood Morrill See Text, Section IV-C Steam Isolation Valves Elev. Operator: Chicago Fluid Power A3I 253'alve:

278'rea Solenoids: Laurence 250'F, Atm Amb Vendor Data 110114W, 125434W Volum~

MOV 4007 g 4008 lA/

MDAFW Pumps Discharge Valve lB Elev.

53 Limitorque Smb-00 Reliance, Class B Insul 90 pgxg, 320'F 2xl0 RADS, 100% RH WCAP WCAP WCAP 7410-L 7744 Volume 7153

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MOV 4027, 4028 SW Supply Area 253'imitorque 53 Smb-00 90 prig, 320'F WCAP 7410-L Volume I Valve to MDAFW Pumps Elev. Reliance Class B Insul 2xl0 RADS, WCAP 7744 Volume I 100% RH WCAP 7153 AOV 4269, 4270 Main Area 57 Feedwater Control Valves Elev. 272'-5 Operator:

Solenoids:

=-

Fisher 473 ASCO-LD830061U 130'F, Atm Amb See Text, Section IV-D Vendor Data

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR Ec MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

2. Valves Cont'd AOV 4271, 4272 Main Area 57272'perator: Copes Vulcan See Text, Section IV-D Feedwater Bypass Valves Elev. D-100-160 Solenoids: ASCO LB8300B64BU 130'F, Atm Amb Vendor Data 587 1 ~ 5872 i 5873 Area gl Operator: Henry Pratt RIA See Text, Section -E AOV 5874, 5875, 5876 Elev. 248'OV Solenoids: VERSA VSG 200'F, Atm Amb Vendor Data, WCAP 7153

3. Electrical The controls, power, and protection circuitry for mechanical equipment previously .listed as well as:

Reactor Trip Breakers Area N3 Westinghouse DB-50 NEMA Standard SG-3

.Elev. 253) 1600A Frame Reactor Instrumentation Area 48 Foxboro FSAR Section Not Exposed to DBE and Control Cabinets Elev. 9.9 Environment See Text, Section III-}

lA, 1B Batteries Area 48 Gould FTA-19 110'F Atm Amb Not Exposed to DB~

Elev. Environment 253'.

Gilbert Spec RO-2400 Gould Instruction Manu<

Instrumentation Pressurizer Pressure Area gl236'oxboro 611GM-DSI 60 prig, 286'F WCAP 7410-L Volume I PT 429, 430, 431, 449 Elev. 3x10 RADS, WCAP 7744 Volume I 100% RH See Text, Section IV-G WCAP 7153

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* -VENDOR 6 MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

4. Instrumentation (Cont'd)

Pressurizer Level Area Nl 613M-MDL Modified 318'g, 90 psig WCAP 7410-L Volume I Elev. 236' 3x10 Rads, WCAP 7744 Volume I 100% RH See Text, Section IV-H WCAP 7153 Westinghouse Spec t Coolant System Area 278'oxboro

$1 Rosemount Engineering 200'F, Atm Amg See Text, Section IV-Loop Temperature Elev. Company 176JA Vendor Spec 247'lements WCAP 7153 TE 401A,B, 402AiBg 403AiB 404AiBi 405AiBi 406AIB 407AiBi 408AIB i 409AiB 410A,B A Steam Line Flow Area Nl Barton 332, NEMA IV 320'F, Atm Amb See Text, Section IV-FT 464, 465 Elev. Enclosure WCAP 7354-L 236'eactor WCAP 7153 Steam Line Flow Area Nl Barton 332, NEMA IV 320'F, Atm Amb See Text, Section IV-F FT 474, 475 Elev. Enclosure WCAP 7354-L 278'AST WCAP 7153 Level Area $2 Foxboro 631DM-MSI 318'g, 90 psig Not Exposed to DB LT 102, 106, 171, 172 Elev. 3x10 RADS, Environment 100% RH WCAP 7153 Westinghouse Spec Sht Not Exposed to Contain 272'ontainment Vessel Area N3 Barton 332, NEMA IV 320'F, Atm Amb Pressure PT 945I 946/ Elev. Enclosure ment DBE Environment hCAP 7354 L 253'47 i PT 948 ~ 949 I 950 4

'RWST Level Area 52 920: Foxboro 611GM-ASI 3x10 RADS, Not Exposed to DBE LT 920 Elev. 100% RH Environment 60 psig, 286'F WCAP 7410-L Volume I WCAP 7744 Volume I

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR 6 MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

4. Instrumentation Cont'd LIC 921 Barton 289 200 F I Atmi Amb Vendor Data A Steam Line Pressure Area g3 Foxboro 611GM-DSI 60 pmig, 286 F 7 jCAP 7410-L Volume I PT 468, 469, 482 Elev. 253 3xl0 RADS, WCAP 7744 Volume I 253'21: 100$ RH WCAP 7153 B Steam Line Pressure Area 03 Foxboro 611GM-DSI 60 prig, 286'F WCAP 7410-L Volume I PT 478, 479, 483 Elev. 3x10 RADS, WCAP 7744 Volume I 100% RH WCAP 7153 Control Building Air Area NS Handling Unit: Westing- 122'F, Atm Amb Not Exposed to DBE Conditioning G Chilled Elev. house 8162 Environment Water System Return Fan: Sturtevant 8015 Gilbert Spec 5201 A-16208 W/WAV-40 Gilbert Spec 5542 Emergency Fan: Sturtevant 253'rea 8015 A-16216 W/WAV-40 RHR Pump Cooling Syst: em N2 Sturtevant A-16208 with 122'F Max.Amb. Not Exposed to DBE Elev. 236'ir WAV-4D Coil 2HP Motor, Class A Insula-40'C Max.Amb. Environment 40'C Rise Gilbert Spec 5342 236'rea tion 5201 SI/CS Pump Cooling 42 Sturtevant A-16216 with 122'F Max.Amb. Not Exposed to DB System Elev. WAVF-4D Coil 3 HP Motor, 40'C Max.Amb. Environment Class A Insulation 40'C Rise Gilbert Spec 5342,5201

6. Miscellaneous E ui ment Residual Heat Removal Area 52 N/A Not Exposed to DBE System Environment Service Water System Area N2,3 N/A Not Exposed to DBE Environment

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR 6 MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

6. Miscellaneous E ui ment Cont'd Component Cooling Area I2 N/A Not Exposed to DBE Water System Environment

7. Cables-Safe uard Circuits Power Circuits Area gl

• Kerite HT Insulation 60 pnig, 318'F Kerite Memo 7/22/68 FR Jacket 2xl0 RADS, WCAP 7410-L Volume I 100% RH WCAP 7744 Volume I Gilbert Spec 5313, WCAP 7153 Control Circuits Area gl

• Kerite HT Insulation 60 pnig, 318'F Kerite Momo 7/22/68 FR Jacket 2x10 RADS, WCAP 7410-L Volume I 100$ RH WCAP 7744 Volume I Gilbert Spec 5314, WCAP 7153 Instrumentation Circuits Area Ol

• Coleman Cable 60 pnig, 287'F WCAP 7410-L Volume I Silicone Rubber Insulation 2x10 RADS, WCAP 7744 Volume I Glass Braid Jacket 100% RH IPCEA S-19-81-P-3.17 Aluminum Mylar Shield P 5.2 WCAP 7153 Power Circuits All Areas Kerite HT Insulation 60 pnig, 318F Ketite Mome 7/22/

except gl FR Jacket 2xlo RADS WCAP 7410-L Volume I WCAP 7744 Volume I Gilbert Spec 5312 WCAP 7153

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR & MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION

7. Cables-Safe uard Circuits Cont'd Control Circuits All Areas General Cable Rated for con- Gilbert Spec 5315 except 51 PVC Insulation tinuous opera- IPCEA Standard S Glass Braid Jacket with tion at 75'C 402 Section 3.8 overall Jacket (167oF)

Instrumentation Circuits All Areas Rome Cable & Coleman Cable Rated for con- Gilbert Spec 5324 Insulation tinuous opera- IPCEA Standard S-6l-except Ol PVC Glass Braic Jacket with overall PVC Jacket tion at (167~F) 75'02 Section 3.8

8. Penetrations Electrical Area il Crouse Hinds 90 psig> 320'F 1.17x10 RADS, NCAP 7153, Letter White to niemann 100% RH 5/21/78 NRP Penetration Steam Incident Test Report, Crouse Hinds Westinghouse letter to CPL CPL-77-550 11/29/7 westinghouse: 60 psig, 340'F WCAP 7153 100% Rg, Gilbert Spec 504 2.1x10 RADS Westinghouse Penetra.

Proposal Sept. 4, 1974

9. Terminations Terminal Blocks Area gl Nestinghouse: 542247 106 psig, See Text, Section IV-1 340~$ Westinghouse letter to 2x10 RADS, E.E. Hoellen from 100% RH A.P. Colaiaco, Manager of Swgr Developments, NCAP 7153

Cg ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TABLE 3 QUALIFICATION QUALIFICATION EQUIPMENT LOCATION* VENDOR 6 MODEL DESIGN PROCEDURES/

PARAMETERS DOCUMENTATION 10.~S lices Area N1 Raychem HCSF-N 350'g, 70 psig Some Typical Splices 2xl0 RADS, are Presently Unaer 100% RH Test

• For Location Drawing See Figure 3.