ML19225C527

Provides Detailed Response to IE Bulletin 79-01, Environ Qualification of Class IE Equipment.

ML19225C527
Person / Time
Site:	Farley
Issue date:	06/13/1979
From:	Clayton F ALABAMA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7907310326
Download: ML19225C527 (22)

Text

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r, fg Y _' QTgij F L CLAMOfe JR c-Alabama Power c; 12 C L U, June 13,19 79 ,;

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g Do c ke t No. 50-348 -

p 1' NRC IE Bulletin 79-01 CO Mr. James P. O'Reilly C*'

U. S. Nuclear Regula tory Commission Region II 101 Marie t ta Stree t, N. W.

Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

In response Equipment, to IE Bulletin 79-01, Enviromen tal Qualification of Class IE ing responsedated February 8,1979. Alabama Power Company submits the follow-to Items 1-4 for inside containment, Plant Farley-Unit 1.

Item 1: Complete the re-review program described in IE Circular 76-08 within 120 days of receipt of this Bulletin.

The re-review has been completed.

Item 2:

D2termine if the types of stem mounted limit switches described M

above (NA. CO Models SL2-C-ll, SL3-OfL, sal-31, sal-32 D1200j ,

EA700, EA-7 70) are being used or planned for use on safety-related valves so, which are located inside containmant at your facility. If provide a writ ten report to the NRC within the time frame specified and to the address specified in Item 4 below.

Ncne of the above stem mounted limit switches are used or planned for use at Plar.c Farley-Unit 1.

Item 3:

Provide written evidence of qualification of electrical equipment required to function under accident conditions. (This written evidence should include:

(1) Component De s c rip tion (2) Description of the Accident Environment (3) The Environment to Which the Component is Qualified (4) Manner of Qualification, Which Should Irelude Test Methods (5) Iden ti fica tion of the Specific Supportii.., Qualifica tion Do cumen ta tion For those items not having co=plete qualification data available for review, identify your plans for determining qualification, either by testing or engineering analysis, or combination of these, or by replacement with qualified equipment. Include your gL)- schedule for completing these actLann and-tour justification (})

o for con tinued ope ra tion.

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Docke t No . 50-34 8 NBC IE Bulletin 79-01 J une 13, 19 79 All equipment has written evidence demonstrating that it will f unction under accident conditions. The writ ten evidence is provided in attachment A.

Item 4: Report any items which are identified as not meeting qualification requiremento for service intended.

All items teet qualification requirements for intended service.

Alabama Power Company's response to IE Bulletin 79-01A, Deficiencies in the Environmental Qualification of ASCO Solenoid Valves, da ted June 6,19 79, for Farley Unit 1.

Item 1: D1termine whether or not ASCO solenoid valves are used or planned for use in safety-related systems at your facility.

ASCO solenoid valves are used in safety-related system in con tainment .

Item 2: If such valves are used or planned for use, identify the saf ety sys tem involved.

Se e a t ta chmen t B Items 2a 6 2b The ASCO solenoid valven listed on attachment B are used as pilot valves for Containment Isolation Valves. All the solenoid valves except HV 3184, Component Cooling Water f roc RCP Thermal Barrier, are Pnase "A" isolation and will close in less than one (1) second af ter receipt of the isolation signal. The c.. aimum time for the containment spray af ter a LOCA is greater than thirty (30) seconds . The solenoids will have performed their function long before this time and isolated containment bef ore the LOCA environment is present. Also, both the solenoid valves and the isolation valve will fail in the closed or safe position.

+Jl Jdb

Do cke t No . 50-348 NRC IE Bulletin 79-01 June 13,19 79 Solenoid Valve HV 3184, Compone nt Cooling Water from RCP Thermal Barrier, is a Phase "B" isolation vc.1ve .

This valve is designed to perform when the pressure in con tair. ment reaches 27 psig. Using the serial number which was physically obtained f rom the valve, it has been determined that this solenoid valve has an llT coil, all metal parts and Vikon seals which are tested to 400 F. The valve is also explosion proof. Therefore, this valve will perform its function under Phase "B" environmental conditions .

Yourc very truly,

.C d'77

~F. L. Clayton, Jr.

FLCJr/ KAP /mmb cc: Mr. R. A. Thomas Mr. G. F. Trowbridge i

f f/37 334

e I PLANT IC.ME: Pl>?iT FAJt!EY - Ih;T 1 EWIRaeti.w r (1.0 CAT ION)

Time Qual. Doc.

Irem Equipment Description Peq'd. Parameter Spec. Qual. Me t hod a kef** k e .s t k s 1 Electrical Penetration Spec 1102-64 Asses.blies and Junction Temp. ( F) 307.5 340 Ssquential CE 100 l F SA E 3.11.2.1 f Some s Press. (psig) 46.3 103 Servie a techtel File 7 M 7-0 3- L-2 2-9 7-1 Test Rel . lla. 1001 100: Report 7597-03-E-22-95-1 Ceneral Electric Radiation 5.107 Rads 5.107 Rads  ! Jan., 1974

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$al n\W f k FOOTNOTES (1) WCAP 7817 was identified in Section 1.6 and 3.7.5.2 of the FSAR for Westinghouse Seismic Qualification of Electrical Equipment. The Foxboro EllGM (MCA) 4-20ma i ns t rume n t is not included in WCAP 7817.

However, Foxboro qualified this instrument model and the Foxboro test report is included in WCAP 8541.

(2) The test reports documenting the environmental testing performed by Foxboro are included in WCAP 8541.

(3) Westinghouse PWRSD has perforced scistic testing on the prototype model of the Barton 763 and 764. Additionally seismic qualification testing is included in the lot t2 sting of the transmitters and has been completed.

(4) NS-CE-13B4 describes the results of the prototype environmental testing performed on the Barton 763 and 764 transmitters.

(5) Seismic qualification of this equipment was not commit te d .

(6) This equipment is located outside containment and no environmental qualifi-cation was specified.

(7) NS-CE-ll79 indicated that this instrument had been environmentally tested by Wes tinghouse and ne t the established functional requirement. The testing has been documented in WCAP 9157.

(8) Seismic qualification testing of the Rosemount 176KF RTD is documented in bCAP-8234A.

(9) Wes tinghouse PWRSD has performed seismic qualification testing of the Rosemount 176KS RTD.

(10) WCAP 7817 documents seismic testing of the D3 Reactor Trip Switchgear.

Westinghouse has certified the qualificatiot of the type DS and the letter of certification is available at Westinghour PWRS D.

(11) Table 3.7-4 and FSAR Section 3.9.4.2 indicate tha t seismic accelerations will be included in the design of the pumps. The enalysis performed by the pump vendors is available at Westinghcuse PWRSD. No specific cocnitment is made for seismic qualification or the pump motors.

(12) No commitment was made in the FSAR for envirormer.tal qualification of this equipmen t.

Environ ental qualification committed only for in-containment ECCS and (13) in-con tcin x n t isolation valve operators.

(14) Section 3.9.4.3 references four seismic tests performed by lockheed for Limi t o r q ue . These are 2785-3-4786 (2/6/73); 2786-4756 Issue 2 (9/5/72);

2 7 73C-4 773 (5/ 3/ 72) and 2785-4-4785 (2/1/ 73) .

(15) The qualification results are not referenced in the FSAR. The seismic testing was performed by ASCO and a Ic!ter summarizing the results has been provided to Westinghouse PWRSD. */-

73/ 7c.

3Jl

ATTACHMENT B Valve Location Vals . Location Nitmb e r Sys tem or Piping HV 3103 Pressurizer Sample Lines HV 3104 Pressurizer Sample Lines HV 3184 C07 from RCP Thermal Earrier HV 3376 CTMT Sump Discharge HV 3443 CCW from Letdown Heat Exchan ger HV 3765 Reactor Loop Sample Line HV 3766 Accumulator Sample Isolation HV 3196 CTMT Purge Isolation HV 2866B Mini Purge Isolation HV 2867B Mini Purge Isolation HV 3179A Steam Generator LA Blowdown Sample Isolation HV 3179B ,

Steam Generator 1A Blowdown Sample Isolation HV 3180A Steam Generator 1B Blowdown Sample Isolation 3V 3180B Steam Generator 1B Blowdown Sample Isolation HV 3181A Steam Generator 1C Blowdown Sample Isolation HV 3181B Staam Generat r 1C Blowdown Sample Isolation HV 3101 Reactor Coolant Hot Leg Sample ? '.ne HV 3102 Reactor Coolant Hot Leg Sample Line HV 3880 Pressure Steam Space Samp2e HV 3881 Pressure Liquid Space Sample HV 3179C Steam Generator 1A Blowdown HV 2180C Steam Generator IB Blowdovn HV 3181C Steam Generator 1C Blowdown HV 3162 Accumulator Tank 1 Sample HV 316 3 Accumulator Tank 2 Sample ~.

352

ATTACHMENT B Valve Location Valve location System or Piping

_ Number HV 3164 Accumulator Tank 3 Sample HV 8047 Pressurizer Relief Tank to Waste Processing System HV 8149A Chemical an ' olume Control Sys tem Letdown Heat Exchanger i.iue HV 8149B Chemical and Volume Control System Letdown Heat Exchanger Line HV 8149C Che,tical and Volume Control System Letdown Heat Exchanger Line HV 8871 Accumulator Tunk Test Line HV 7126 Reac tor Coolant Drain Tank Heat Exchanger Line HV 3197 CTMI Purge Isolation