ML20039A177

Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.

ML20039A177
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/14/1981
From:	FRANKLIN INSTITUTE
To:
Shared Package
ML20039A178	List: ML20039A177
References
CON-NRC-03-79-118, CON-NRC-3-79-118, RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM IEB-79-01B, IEB-79-1B, TER-C5257-510, NUDOCS 8112160322
Download: ML20039A177 (7)

Text

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• Enclosure 1 REQUEST FOR ADDITIONAL INFORMATION .

EQUIPMENT E!NIRONMENTAL QUALIFICATION (EEQ)

REVIEW OF LICENSEES' RESOLUTION OF. OUTSTANDING ISSUES ~

FROM NRC EQUIPMENT EtWIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (SER) AND TMI ACTION PIAN INSTALLED EQUIPMENT Arka.nsas.Fower and Light Company .

Arkansas Nuclear One - Unit 1 December 14, 1981 ,

NRC Docket No. 50-313 NRC TAC No. 42514 J

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. 00. Franklin Research Center A Division of The Franklin Institute TN %nn Frar*Bn Padmey. PMa Pa. !9103 (215)448-1000

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TER-CS257-510 BACKGROUND Franklin Research Center (FRC) of Philadelphia, Pa. is providing assis-for the equipment tance to the U.S. Nuclear Regulatory Commission (NRC) .

environmental qualification (EEQ) review of operating reactors. FRC will.

perform an EEQ review of the Licensee's 90-day response to outstanding issues '

from the NRC Equipment Environmental Qualification Safety Evaluation Report c j

l (SER) and the installed TMI Action Plan equipment. The review will be limited The I to safety-related equipment potentially exposed to a harsh environment.

l results will be presented in the form of a technical evaluation report for 4

each plant.

' This request for additional information (RFI) is the result of an 14, 1980 (1},

evaluation of the inf,ormation provided by letters dated April ,

October 31, 1980 [2], and October 2, 1981 [3].*

A. FIC REVIEW OF THE LICENSEE'S 90-DAY RESPONSE TO THE NBC EEQ SER Date Received by FRC_**

Inf ormation Requested

1. In reference to the Licensee's 90-day" response [3] to the NBC EER [4], a legible ~

single copy of each of the following

,' qualification documents is requested in order I that the FRC evaluation may proceed:

a. Babcock & Wilcox Report BAW-10003A, Rev. 4, " Qualification Ttsting of i

Protection System Instrumentation,"

Dated 1/76 (Licensee Reierence Codes B040-Al, W120-B1, and R369-D2; Vendors - Bailey, Westinghouse, and Rosemount)

b. ' Report B914, "BIW Bostrad 7E Thin Wall Instrument Cables," No Date (Licensee .

Reference Code B365-A2r vendor - Boston Insulated Wire) l

• Numbers in brackets refer to citations found in the list of references.

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• • This column will be completed by FRC as the ' requested information is received.

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I nklin Research Center A DMunn ei The Frumen huumas 5 .

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TER-C5257-510 Date Received by FRC_**

c. Report B915, "Bostrad 7E Cables, Flame and Radiation Resistant Cables for Nuclear Power Plants," Dated 11/80 (Licensee Reference Code B365-A2; ,

Vendor ' Boston Insulated Wire)

d. Lab Reports 98296, Dated 7/2/71; .98407, Dated 6/23/71; and $8415, Dated 7/2/71 .

9 (Licensee Reference Code B365-A2; .

Vendor - Boston Insulated Wire) f " Prototype Test I

e. Report IPS-48, Rev. B, .

Report of Penetration Assemblies, Arkansas Power & Light Company, Arkansas Nuclear One," Dated 3/21/72 (Licensee Reference Code C515-Als vendor - Conax)

f. Report IPS-585.2, Rev. O, " Qualification of Instrumentation Service Classi-fication, Electric Penetration (BF-LVI) for Class lE Service in BWR and PWR Containment Structures," Dated 1/81 (Licensee Reference Code C515-A2; Vendor - Conax) .

g. EPRI Report 1707-3, " Radiation Ef fects on Organic Materials in Nuclear Plants,"

by M. B. Bruce and M. V. David (Draf t)

(Licensee Reference Code E127-1; Vendor - Electric Power Research Institute)

h. FIRL Report F-C2883, " Qualification Test of Motorized Valve Operator Under Simulated Seismic and Post-Accident Reactor Containment Service Conditions," ,

Dated 3/71 (Licensee Reference Code Jll4-Alt Vendor - Electro / Dyne, Foxboro/ Jordan) 43854-1,, "Qualificat ion

.i. 'iIyli I;ab ReportTest for Electrical Connectors Used at Browns Ferry Nuclear Power Plant, Units 1, 2, and 3," Volume I of II, Dated 1978 (Licensee Reference Code F080-Als vendor - Fenwall)

-6 nklin Research Center

,, A Dhquen af The Frueen buenas

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TER-CS257-510 '

Date Received by FRC_**

j. Wyle Lab Report 26304, Rev. A, ,.

" Environmental Qualification Test Program on Pressure Transmitter, Fischer & Port &r Model No. 50EP1040 BCXA, and D. P. .

Transmitter, Fischer & Porter Model No.

13D24960s," Dated 12/12/78 (Licensee .

Reference Code F120-Als vendor - Fischer

& Porter)  ?

k. Wyle Lab Report 26304, Rev. A (12/4/79),

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" Environmental Qualification Test Program on One Electronic Transmitter, Foxboro Model No. EllAH and Etc. ," Dated 12 / 12/7 8' y (Licensee Reference Code FISO-Als Vendor - Foxboro

1. Engineering Report 720.3.28, " AH90 Series Milliampere Proportioning Hydramotor Actuator Special Environments Performance Summary Report," Dated 3/5/73 (Licensee Ref'erence Code G072-Als Vendor - ITT General, General Controls)

m. Report 600198, Addendum 1, " Test of Limitorque Valve Operator to Meet General Requirements of an Electric Valve Actuator in Nuclear Reactor Containment Environment," Dated 1/2/69 (Included Report F-C2232-01, Dated 9/72) (Licensee Reference Code L200-A3 r Vendor -

Limitorque)

n. Engineering Report No. Il0E, Dated 11/12/70 (Licensee Reference Code

' 0040-Alf Vendor - Okonite)

o. Joy Mfg. Report, " Qualification Test of a Fan and Motor Designed for Service in Nuclear Containment," Dated 5/14/75;

'"American Air Filter" Letter, 7/30/81 (Licensee Reference Code R165-Als .

Vendor - Reliance) 000u Franklin Research Center A Chuman af The feween busnee

TER-C5257-510 Date Receive'd by FRC_**

p. Babcock & Wilcox Report RPS/DHI (177)-R 1152 GP9, " Qualification Report for -

Pressure Transmitter Rosemount Model 1152GP9A2PB for Reactor Coolant Pressure Measurement," Dated 2/17/77 (Licensee Reference Code R369-A3; Vendor - ~

Rosemount)

q. Test Report for RfD 17,62, Rev. A, .

" Assemblies for Nuclear Power Stations Model 105-1619-6 Sensor Assembly, Model 89-138 Connecticsn Head Assembly," .

(Licensee Reference Code R369-Dl; Vendor - Rosemount) r.

"NA-1 Nuclear Qualification, Rev.1" (Licensee Reference Codes R378-A2, -A3; Vendor - Rotork) s.

"NA-2 Nuclear Qualification, Rev.1" (Licensee Reference code R378-A5; Vendor - Rotork)

t. Report 1827, " Environmental Test Report on TBC Model 75C-002,1, 'Y' Pattern

• Solenoid Motor Valve-Sof t Seated, High Pressure Version per Provisions of TR Test Procedure No.1674," Dated 9/25/79 (Licensee Reference Code T020-A4; Vendor - Target Rock Corp.)

2. FRC requests further identification of installed cable identifiedwire in References size, number3' and 3.1 with respect tot ,

of conductors; type, thickness, and ,

construction of insulation, and jacket materials; identification of shielding '(where applicable) , rated voltage, and type of application (i.e., power, control, or instrument. .

This information is required to provide traceability of the installed equipment to the equipment tested in the test report cited as evidence of qualification.

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' O nkun Research Center A Dhunon of The Frueen Dennae

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. TER-C5257-510 i

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3. FRC requests further l identification of the

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motorized valve actuators identified in References 3 and 3.1 with respect tot motor manufacturer, class of insulation, and the  ;

type of current used (ac or dc). The class

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I of insulation should also be specified for j any other motors located in the plant.  ;

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Enclos.ure 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO PRESSURE & TEMPERATURE PROFILES FOR PIPE BREAKS OUTSIDE CONTAINMENT FOR

- ARKANSAS NUCLEAR ONE UNIT NO. 1 DOCKET NO. 50-313 The licensee, Arkansas Power & Light Company, is requested to provide the basis, assumptions and 'an analysis of a typical pipe break. location (for example, auxiliary feedwater pump room) that in'cludes the following infor-mation. .

1. With respect to the pipe to be broken, provide the following:

a. Type of fluid (water or steam);

b. Temperature;_

c. Pressure; .

d. Source of the fluid;

e. Flow rate (or assumed flow rate);

f. Pipe internal diameter;

g. Wetted perimeter of the break .(feet);

h. Total pipe internal volum;e ,

i. Exit flow aree, if the break was not in the pipe, just described above;

j. Area of flow restriction, if any; '

k. Differential elevation from the source to the pipe break;

l. Total flow resistance (only if the fluid is water);

m. Means to stop fluid flow (none, gate valve, globe valve, etc.); and '

n. If 1.m'is a valve, then the valve's open throat area, full open flow .

• coefficient, valve closure time, and delay time until initiation of valve closure.

2. With respect to the compartments being analyzed:

a. Number of compartment analyzed; and

b. For each compartment:

i. initial temperature ii. initial pressure iii.

iv.

initial free airhumidity volume (cubic feet)

v. number of vents and vent areas (square feet) for each vent; and vi. minimum pressure to initiate flow to the next compartment (psia),

3. All assumptions used,.includino but not limited to the:

a. Orifice coefficient for the "end effects" for the discharged fluid; and

b. Fluid expansion factor.

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