ML17244A207
| 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) | |
Text
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'EGULATOMMNFORMATION DOCKET NBR: 56'-244 RE GINNA 1 RECIPIENT:
ZIFZtANN D.L.
ORXGINATOR:
WHITE L.D.
COI1PANY: RPCHE'STER GAS
& ELEC CP
SUBJECT:
Res onds to 780906 NRC re uest for review DISTRIBUTION TZM DOC DATE:
781201 ACCESSION NBR: 7812050187 COPIES RECEIVED:
LTR 3
ENCL 40 SIZE:
31 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.
DISTRIBUTION CODE t A001 NOTARIZED '
DISTRTRUTIOt'ITLE 1 l'FNERAL DISTRIBUTION FQR AFTER ISSUANCE OF OPERATING LICENSE ~
NAHE BR F
I LE GELD MANAUFR CORE PFRFflRi4ANCE BR AD FQR SYS L PRQJ ENGINFFRING HR REACTnp SAFFTY BR PLANT SYSTEMS BR EER
'FFLUENT TREAT SYS D BRImmAN LPDR TERA "NSIC ACRS
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89 EAST AVEI((IE, ROCHESTER, M.Y. I4649 LEON D. WHITE. JR, VICC PRCSIIICNT TC<.I r rrONC 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.
In your September 6,
1978 letter, it was noted that we had not addressed 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,
~~@
Enclosures g 8120 50 1f7 ULATORy DOCK@ F())
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Enclosure 2
,.rdThe, report regarding environmental qualification of e3,gc<rical equipment which was submitted by letter dated Fegggary 24, 1978, for L. D. White, Jr.,
Rochester Gas and Electric Corporation to Mr. A. Schwencer, Chief, Operating Reagtors Branch No.
1 should be revised as follows:
T.
ru>>t act
~ TIE DELETE 26 27 28 29 Table 3 (all pages)
ADD Title Page Table of Contents List of Figures List of Tables 26 27 28 29 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 B.
Events Accompanying a Main Steam Line Break C.
High Energy Line Breaks Outside Containment D.
Flooding Outside Containment III.
Identification of the Limiting Service 2
8 10 13 Environmental Conditions for Equipment which is Required to Function to Mitigate the Consequences of Events Identified Above 14 IV.
A.
Inside Containment B.
Auxiliary Building C.
Intermediate Building D.
Cable Tunnel E.
Control Building F.
Diesel Generator Rooms G.
Turbine Building H.
Auxiliary Building Annex I.
Screen House Equipment Qualification Information 14 16 16 17 17 17 18 18 18 19 A.
B.
C.
D ~
E.
F.
G.
H.I.
J ~
K.
L.
M.
Auxiliary Feedwater Pumps Valves 878 A,B,C,D Main Steam Isolation Valves Main Feedwater and Bypass Isolation Valves Containment Fan Cooler Dampers Barton 332 Transmitter Foxboro 611 Transmitter Foxboro 613 Transmitter Instrumentation Terminal Blocks Cable Reactor Coolant System Temperature Detectors Safety Related Cable Splices Subject to LOCA and MSLB Effects Aging of Equipment Prior to Qualification Testing 19 19 19 20 20 21 21 22 24 27 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
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR
& MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION
- 1. Mechanical lA, 1B Diesel Generators Area 04 and Auxiliaries Elev.
253 Diesel:
ALCO 251F Generator:
Westinghouse 1900 KW
- 110'F Atm Arab 40C Max.
Amb.
70C Rise Not exposed to DBE Environment Gilbert Spec RO-2239 DEMA Standard Vendor Data lA, 1B Containment Spray Area 62 Pumps Elev.
236'A, 1B Residual Heat Removal Pumps Area 42 Elev.
219'A, 1B, 1C, 1D Service Water Pumps Area 45 Elev.
253'A, 1B, 1C Safety Injec-Area f2 tion Pumps Elev. 236'ump:
Motor:
Pump:
Motor:
Pump:
Motor:
Pump:
Motor:
Worthington 3-NTS-811 Westinghouse 509-US
- AFDP, Thermal Epoxy Ingersoll Rand 4xllA Westinghouse 444TS TBDP, Class B Insul Pacific SVC-6L Westinghouse 445TS TBDP, Class B Insul Worthington 20H-500-WZ Westinghouse 509-UPH ABDP, Class F
Insul 104 F Atm Amb 40F Max. Amb.
SOC Rise 104'F Atm Amb 40C Max.
Amb.
SOC Rise 104'F Atm Amb 40C Max.Amb.
SOC Rise 104'F Atra Amb 40C Max.Amb.
105C Rise Not exposed to DBE Environment Westinghouse Spec 676370
& 676427 Not Exposed to DBE Environment Westinghouse Spec 676370
& 676427 Not Exposed to DBE Environment Westinghouse Spec 676370
& 676427 Not Exposed to DB Environment Westinghouse Spec 676370
& 676427 lA, 1B, lC, 1D Contain-ment Recirc. Units Area Ol Elev. 252'an:
Sturtevant 8530-D Motor: Westinghouse 588.5-
- CSP, Thermal Epoxy 80 pmig, 320F 2x10
- RADS, 100%
RH NCAP-7343-June, 1969 WCAP-7410-L-Vol. II WCAP-7744-Vol. II WCAP-9003-January, 196!
- ATM Atmospheric Pressure, AMB Ambient Relative Humidity'
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT
- 1. Mechanical Cont'd LOCATION*
VENDOR
& MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION lA, 1B Motor Driven Auxiliary Feedwater Pumps Area N3 Elev.
253'A, lB Component Cooling Area f2 Water Pumps Elev.
272'ump:
Worthington 2-WTF-87 Motor:Westinghouse 505-US ABDP, Thermal Epoxy Pump:
Ingersoll Rand 8SD Motor: Westinghouse 444TS TBDP, Class B Insul 104'F Atm Amb 40C Max.Amb.
80C Rise 104'F Atm Amb 40C Max.Amb.
80C Rise Gilbert Spec RO-2267 Westinghouse Spec 676427 See Text, Section
-A Not Exposed to DBE Environment Westinghouse Spec 676370
& 676427 1C, 1D Standby Auxiliary Area 56 Feedwater Pumps Elev.
272'.
Valves Pump:
Ingersoll Rand 120'F Atm Amb Motor: General Electric 50C Max.Amb.
Type K'Class B Insul 80C Rise Not Exposed to DBE Environment Gilbert Spec 520
& 711 MOV 825A, B Safety In-Area 42 jection Suction from Elev.
236'WST Limitorgue Smb-00
- Reliance, Class B Insul 90 prig, 320F 2xlo RADS 100 o RH Not Exposed to DBE Environment WCAP 7410-L Vol. I WCAP 7744 Volume I MOV 826A,B,C,D Safety Area 52 Limitorque Smb-00 Injection Suction from.Elev.'253'eerless, Class B Insul BAST AOV 836A,B NaOH Addition Area 42 Copes Vulcan to CS Pumps Discharge Elev. 236'-100-60 120'F Atm Amb 150'F Atm Amb Not Exposed to DBE Environment Westinghouse Spec 676258 Not Exposed to DBE Environment Westinghouse Spec 676270 Vendor Data
0 0
4
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR & MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION
- 2. Valves Cont'd MOV 841, 865 Accumulator Area gl Discharge Valves Elev. 236'imitorque Smb-2
- Reliance, Class B Insul 90 prig, 320'F 2xl0 RADS 100%
RH WCAP 7410-L Vol. I WCAP 7744 Volume I WCAP 7153, June 16, 1975 Letter to Pu e
from White MOV 850A,B Containment Area 51 Limitorque Smb-00 Sump B Isolation Valves Elev. 219'eliance, Class B Insul 90 prig, 320'F WCAP 7410-L Volume I 2xl0
MOV 852A,B RHR Core Deluge Valves MOV 856 RWST to RHR Pumps Suction MOV 857A,B,C RHR Pump Discharge to SI and CS Pumps Area 02 Elev.
230'rea 51 Elev.
236'imitorgue Smb-00 Limitorque, Class B Insul Limitorgue Smb-l
- Reliance, Class B Insul Area 52 Limitorque Smb-00 Elev.
236
- Reliance, Class B Insul Area
$ 2 Limitorque Smb-00 Elev. 236'eliance, Class B Insul 120'F Atm Amb 90 prig, 320 F
2xl0
- RADS, 100%
RH 90 prig, 320 F
2xl0
- RADS, 100%
RH 90 prig, 320 F
2xl0
- RADS, 100%
RH Westinghouse Spec 676258 WCAP 7410-L Volume I WCAP 7744 Volume I WCAP 7153 June 16, 1975 Letter to Purple from White Not Exposed to DBE Environment WCAP 7410-L Volum~
WCAP 7744 Volume ~
WCAP 7153 Not Exposed to DBE Environment WCAP 7410-L Volume I WCAP 7410.Volume I WCAP 7153
0
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR Sc MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION
236 'imitorque Smb-00
- Reliance, Class B Insul 90 prig, 320 F
2xl0
- RADS, 100%
RH Not Exposed to DBE Environment WCAP 74l0-L Volume I WCAP 7744 Volume WCAP 7153 MOV 878B,D High Head SI to RCS Cold Legs Area gl Limitorque Smb-00 Elev. 236'eerless, Class B Insul 120'F Atm Amb Westinghouse Spec 676258 See Text, Section IV-B MOV 896A,B RWST Isola-Area 52 Limitorque Smb-00 tion Valves Elev. 236'eerless, Class B Insul 120F Max.Amb.
Not Exposed to DBE Environment Westinghouse Spec 676258 AOV 3516, 3517 Main Steam Isolation Valves MOV 4007 g 4008 lA/ lB MDAFW Pumps Discharge Valve Area 03 Elev.
278'rea 53 Elev.
253'alve:
Attwood Morrill Operator:
Chicago Fluid Power A3I Solenoids:
Laurence
- 110114W, 125434W Limitorque Smb-00
- Reliance, Class B Insul See Text, Section IV-C 250'F, Atm Amb Vendor Data 90 pgxg, 320'F WCAP 7410-L Volum~
2xl0
100%
RH WCAP 7153 MOV 4027, 4028 SW Supply Area 53 Valve to MDAFW Pumps Elev. 253'imitorque Smb-00 Reliance Class B Insul 90 prig, 320'F WCAP 7410-L Volume I 2xl0
RH WCAP 7153 AOV 4269, 4270 Main Area 57 Operator:
=- Fisher 473 Feedwater Control Valves Elev. 272'-5 Solenoids:
ASCO-LD830061U See Text, Section IV-D 130'F, Atm Amb Vendor Data
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR Ec MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION Area gl Elev.
248'OV 587 1 ~ 5872 i 5873 AOV 5874,
- 5875, 5876
- 3. Electrical The controls,
- power, and protection circuitry for mechanical equipment previously.listed as well as:
Reactor Trip Breakers Area N3
.Elev.
253)
Reactor Instrumentation Area 48 and Control Cabinets Elev.
lA, 1B Batteries Area 48 Elev.
253'.
Instrumentation
Solenoids:
Copes Vulcan D-100-160 ASCO LB8300B64BU Westinghouse DB-50 1600A Frame Foxboro Gould FTA-19 Operator:
Henry Pratt RIA Solenoids:
VERSA VSG NEMA Standard SG-3 FSAR Section 9.9 Not Exposed to DBE Environment See Text, Section III-}
110'F Atm Amb Not Exposed to DB~
Environment Gilbert Spec RO-2400 Gould Instruction Manu<
See Text, Section IV-D 130'F, Atm Amb Vendor Data See Text, Section
-E 200'F, Atm Amb Vendor Data, WCAP 7153 Pressurizer Pressure PT 429,
RH See Text, Section IV-G WCAP 7153
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT
- 4. Instrumentation (Cont'd)
LOCATION*
-VENDOR 6 MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION Pressurizer Level Area Nl Elev.
236' Steam Line Flow FT 474, 475 Area Nl Elev.
278'AST Level Area
$ 2 LT 102,
- 106, 171, 172 Elev.
272'ontainment Vessel Area N3 Pressure PT 945I 946/
Elev.
253'47 i
PT 948 ~
949 I 950
'RWST Level LT 920 Area 52 Elev.
236'eactor Coolant System Area
$ 1 Loop Temperature Elev.
247'lements TE 401A,B, 402AiBg 403AiB 404AiBi 405AiBi 406AIB 407AiBi 408AIB i 409AiB 410A,B A Steam Line Flow Area Nl FT 464, 465 Elev.
278'oxboro 613M-MDL Modified Rosemount Engineering Company 176JA Barton 332, NEMA IV Enclosure Barton 332, NEMA IV Enclosure Foxboro 631DM-MSI Barton 332, NEMA IV Enclosure 920:
Foxboro 611GM-ASI 320'F, Atm Amb See Text, Section IV-WCAP 7354-L WCAP 7153 320'F, Atm Amb 318'g, 90 psig 3x10
- RADS, 100%
RH 320'F, Atm Amb See Text, Section IV-F WCAP 7354-L WCAP 7153 Not Exposed to DB Environment WCAP 7153 Westinghouse Spec Sht Not Exposed to Contain ment DBE Environment hCAP 7354 L
3x10
100%
RH Environment 60 psig, 286'F WCAP 7410-L Volume I WCAP 7744 Volume I 318'g, 90 psig WCAP 7410-L Volume I 3x10
- Rads, WCAP 7744 Volume I 100%
RH See Text, Section IV-H WCAP 7153 Westinghouse Spec t
200'F, Atm Amg See Text, Section IV-Vendor Spec WCAP 7153
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR 6 MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION
- 4. Instrumentation Cont'd LIC 921 A Steam Line Pressure PT 468,
- 469, 482 B Steam Line Pressure PT 478,
- 479, 483 Area g3 Elev.
253 Area 03 Elev.
253'21:
Barton 289 Foxboro 611GM-DSI Foxboro 611GM-DSI 200 F I Atmi Amb 60 pmig, 286 F
3xl0
- RADS, 100$
RH Vendor Data 7410-L Volume I 7744 Volume I 7153 7410-L Volume I 7744 Volume I 7153 7jCAP WCAP WCAP 60 prig, 286'F WCAP 3x10
RH WCAP Control Building Air Conditioning G Chilled Water System RHR Pump Cooling Syst: em SI/CS Pump Cooling System
- 6. Miscellaneous E ui ment Area NS Elev.
253'rea N2 Elev.
236'rea 42 Elev.
236'ir Handling Unit: Westing-house 8162 Return Fan: Sturtevant 8015 A-16208 W/WAV-40 Emergency Fan:
Sturtevant 8015 A-16216 W/WAV-40 Sturtevant A-16208 with WAV-4D Coil 2HP Motor, Class A Insula-tion Sturtevant A-16216 with WAVF-4D Coil 3 HP Motor, Class A Insulation 122'F, Atm Amb 122'F Max.Amb.
40'C Max.Amb.
40'C Rise 122'F Max.Amb.
40'C Max.Amb.
40'C Rise Not Exposed to DBE Environment Gilbert Spec 5201 Gilbert Spec 5542 Not Exposed to DBE Environment Gilbert Spec 5342 5201 Not Exposed to DB Environment Gilbert Spec 5342,5201 N/A Area N2,3 N/A Residual Heat Removal Area 52 System Service Water System Not Exposed to DBE Environment Not Exposed to DBE Environment
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR 6 MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION
- 6. Miscellaneous E ui ment Cont'd Component Cooling Area I2 Water System
- 7. Cables-Safe uard Circuits N/A Not Exposed to DBE Environment Power Circuits Control Circuits Area gl
- Kerite HT Insulation FR Jacket Area gl
- Kerite HT Insulation FR Jacket 60 pnig, 318'F 2xl0
- RADS, 100%
RH 60 pnig, 318'F 2x10
- RADS, 100$
RH Kerite Memo 7/22/68 WCAP 7410-L Volume I WCAP 7744 Volume I Gilbert Spec
- 5314, WCAP 7153 Power Circuits All Areas except gl Instrumentation Circuits Area Ol
- Coleman Cable Silicone Rubber Insulation Glass Braid Jacket Aluminum Mylar Shield Kerite HT Insulation FR Jacket 60 pnig, 287'F 2x10
- RADS, 100%
RH 60 pnig, 318F 2xlo RADS WCAP 7410-L Volume I WCAP 7744 Volume I IPCEA S-19-81-P-3.17 P 5.2 WCAP 7153 Ketite Mome 7/22/
WCAP 7410-L Volume I WCAP 7744 Volume I Gilbert Spec 5312 WCAP 7153
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR & MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
DOCUMENTATION
- 7. Cables-Safe uard Circuits Cont'd Control Circuits All Areas except 51 General Cable PVC Insulation Glass Braid Jacket with overall Jacket Rated for con-Gilbert Spec 5315 tinuous opera-IPCEA Standard S tion at 75'C 402 Section 3.8 (167oF)
Instrumentation Circuits All Areas except Ol
- 8. Penetrations Rome Cable
& Coleman Cable PVC Insulation Glass Braic Jacket with overall PVC Jacket Rated for con-Gilbert Spec 5324 tinuous opera-IPCEA Standard S-6l-tion at 75'02 Section 3.8 (167~F)
Electrical
- 9. Terminations Area il Crouse Hinds westinghouse:
90 psig> 320'F 1.17x10
- RADS, 100%
RH 60 psig, 340'F 100% Rg, 2.1x10 RADS NCAP 7153, Letter White to niemann 5/21/78 NRP Penetration Steam Incident Test Report, Crouse Hinds Westinghouse letter to CPL CPL-77-550 11/29/7 WCAP 7153 Gilbert Spec 504 Westinghouse Penetra.
Proposal Sept.
4, 1974 Terminal Blocks Area gl Nestinghouse:
542247 106 psig, 340~$
2x10
- RADS, 100%
RH See Text, Section IV-1 Westinghouse letter to E.E. Hoellen from A.P. Colaiaco, Manager of Swgr Developments, NCAP 7153
Cg
TABLE 3 ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT EQUIPMENT LOCATION*
VENDOR 6 MODEL QUALIFICATION DESIGN PARAMETERS QUALIFICATION PROCEDURES/
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.