ML20125E398

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Responds to NRC Requesting Info Re Containment Purge Sys.Valves Will Be Used During Modes 1-4 Only,For Purging to Improve Working Conditions for safety-related Activities,Following Demonstration of Operability
ML20125E398
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 02/07/1980
From: Clayton F
ALABAMA POWER CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8002120525
Download: ML20125E398 (12)
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t Alabama P.wper Company 600 North 18tn Street

. Post Office Box 2641 Birmingham Alabama 35291 Telephone 206 323-5341 u

tho* tic",%i, AlabamaPower ett soutnem electre snem February 7, 1980 Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn:

Mr. A. Schwencer

Dear Sir:

JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO. 50-348 CONTAINMENT PURGE VALVES i

l This is Alabama Power Company's response to your letter dated December l

4, 1979 requesting information concerning the containment purge system at Farley Nuclear Plant.

1.

Request:

Provide a conniement that the main purge system (48-inch lines) would only be used for the reactor operational modes of cold shutdown and refueling-(modes 5 and 6).

Response

Alabama Power Company previously connitted to maintain the 48-inch valves closed in modes 1, 2, 3 and 4 until their operability can be i

demonstrated. This will be accomplished either by analysis which L

will be submitted for NRC review, or by blocking the valves to allow opening to 50 degree open, or less. The valve vendor stated that 65 open was acceptable. After the above is accomplished on the 48-inch valves, use of those valves during modes 1, 2, 3 and 4 will L

be only for purging to improve working conditions to perform safety l

related surveillance or safety related maintenance activities.

l 2.

Request:

With regard to the containment mini-purge system:

(a) In response to Branch Technical Position (BTP) item 5.b, regarding the protection of structures and safety-related equipment located beyond the purge system isolation valves, your submittal dated 6s\\

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Director Page 2 February 7, 1980 Office of Nuclear Reactor Regulation February 5, 1979 stated that the radiological analysis was per-formed taking no credit for the purge filter. This response does not appear to fully address the concerns of BTP item 5.b.

Provide a list of all structures and safety-related equipment that would be damaged or would suffer a, loss of function from the s

4 environment created by the escaping air and steam. Discuss, in p

detail, the potential of the damaged structures to adversely affect safety-related equipment in the vicinity. Discuss the impact on safety due to the loss of function of safety-related equipment.

Discuss all post-accident functions that are impacted.

7 (b) For the containment purge isolation valves, specify the dif ferential pressure across the valve for which the maximum leak rate occurs.

Provide test results (e.g., from vendor tests of leakage rate versus valve differential pressure) which support your conclusion.

Responses (a) The containment purge ducts pass through the piping penetration room at Elevation 121' and the electrical penetration room at Elevation 139'.

The purge system supply fan and the purge exhaust filtration unit are located in separate HVAC equipment rooms at Elevation 155'.

Saf ety-related equipment in these areas is as follows:

1.

Piping Penetration Room:

Post Accident Containment Venting Filter Unit CVCS and ECCS Piping and Valves 2.

Electrical Penetration Room:

MCC IU (for Train "A" HOV's)

MCC IV (for Train "B" MOV's)

Cables and Conduit for Safety-Related Equipment 3.

HVAC Equipment Room:

None

/

If it is postulated that the purge system boundary (duct, fans or filters) should fail before the isolation valves are fully closed, containment atmosphere could escape into the penetration rooms or other areas of the auxilicry building. The effect of the steam / air mixture has been reviewed with the following conclusions:

1.

Potential discharge is limited by the short time that the isolation valves are open, 6 seconds maximum. This includes one second for instrument reaction plus 5 seconds valve closure time. The maximum conditions of the steam / air mixture occur at the end of the 6 seconds and are 232oF at 38 psia in the duct at the valve.

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l Director Page 3 February 7, 1980

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Office of Nuclear ~ Reactor Regulation 2.

Based on the Pratt Company analysis of the 18" mini-purge butterfly valves, maximum flow under LOCA conditions is 10,721.lbs/ min.

If we make a conservative assumption that this' flow exists during the entire 6 seconds then a total of 1,072 lbs. of the steam / air mixture will enter the pene-l tration rooms. There will be a momentary temperature rise 0

from about 1000F to about 130 F in the air temperature in the immediete compartment of the discharge, but the heat will be rapidly dissipated throughout the penetration room volume of 328,000 cubic feet. The net effect on the equipment in the area will be negligible.

3.

The 48" purge exhaust duct passes in close proximity to MCC j

IU.

Jet impingement calculations show that the force on the MCC is only 36 lbs.

4.

Failure of the purge system boundary beyond the penetration rooms will not result in adverse effects on any safety-related equipment.

(b) Attached are the shop test records stating that the four 18" con-tainment purge valves for Unit 1 were each leak rate tested at a i

differential pressure of 65 psi for a time period of five minutes.

1 Also attached are the shop test records stating that the four 48" main purge valves were tested at 53.5 pst differential pressure i

for ten minutes.

]

3.

Request:

With regard to the purge supply and exhaust duct covering (bird screen),

discuss the design basis of the screen.

In particular:

(a) Discuss the design basis for the sizing of the screen mesh pattern; 1

(b) Discuss the provisions taken to assure that the screen has been properly qualified (e.g., for seismic events); and, (c) Describe the routine procedures (e.g., inspections, etc.) that you use to assure that partial blockage of the screen by debris during normal operation does not affect the ability of the screen to remain in place and perform its function when subjected to LOCA forces.

Response

i(a) Bird screen material is a steel wire screen with 1/2" square openings and.049" diameter wire.

It is a standard HVAC material for pre-venting debris from entering duct openings. As the openings are located outside the primary shield, no significant debris should be generated in a LOCA in the vicinity of the bird screen.

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. Direc tor Page 4 February 7, 1980 rY:

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P (b) Dynamic LOCA force on th's bird screen is less than 1 lb. based on the maximum flow race through the duct calculated by Fratt Company.

1 (c).The bird screen material is a commercial grade ' wire screen, weighing less than 0.4 psf.

It is attached by welding to the end of the' duct. We consider that the material and the installation adequate for the very low seismic stresses that would be encountered.

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Farley Nuclear Plant Technical Specifications require that no loose

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establishing containment integrity. This is accomplished by visual inspec-debris (rags, trash, clothing, etc.) is present in the containment prior to i

tion.

Very truly yours, F. L. Clayton, Jr.

FLCJr/TNE:bhj Attachments cc: Mr. R. A. Thomas Mr. G. F. Trowbridge E-i D

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~ T- - - Cu.iomer g m,,, A u ,_ n-seeb-1-n 5 A:sembly Record - Show Hec t or. l.ot No., Serict' As., Fabrication No. sody 9' o L T 0 C 0 2 0 C21 Sh!P ~ '7 Dise Nr S/dL W 66 W 6 903M6 6%0- ? sfo *T 'yo.P Shcf ts #7~ taco b s %s toeans-H Mr% Dt P VAJ/o d o k s? Operator ( Test Record Witnessed Proceduro Pre.sure Time Reject Accept by Dote Hys,lro En 9 l$ klW /~/ f/f h). ftl1lt).1 Stem Looko0* I N8- /^ 42f b( ~T ' Gogo No. 8 S #' Authorized Inspector V Acc. Witnessed Pressure ' Time lookogo Std. Reject Accept , by Date J. 16 8' ~ Sect ti Stem Leohoge SSS Eris /0 MI/Af U $ /JW (M4' n & M M Acc. Witnessed ^ Gooe No. 8G- /1 Authorized Inspector J Cyclo timo Std. Roiect Accept by Date Rs M,-/D jt,k1,/9 g j Osnroting N AL., ju.y j-Authorized Inspector Special Clooning Perbfr / Yq Final Volve inspection Accepted: N.e463 (includes Acceptance of Volve Tosting, nomeplate Witnessed bydpg 0,a. rnorking and packaging) m Doto to o.f.py Q.A.IM [ M Doto / j p.y1 ,$f//. A} Q , k /b Form No. liPCo. 8/OAP-6-i.2 l-SI A18.03 I>r.19k L F

.s ,y. l- ~ p - HENRY PRATT COMPANY ,'Pi'od,.,,Ordee No. g. g gg *f * * *

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ASSEMBt.Y AND TEST RECORD ltem N o,. / ?!alve Deseription g'* Qjyy Qy Customs Order No.f*A/P.2g4 . 0l t1C_$ ' ll' YAL1Y/s 'dPE/?MT'b4 ' Valve Tag No.6/pjat)2 gy Customer $ RAMA Aarn ~ ~ ~ ' ' ' " ' '

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_h ^ Assembly Record - Show Heat of 1.ot No., Serial

  • R5., Fabricotton No.

Body R' 0 1 T o s*o s' o 52 '7 C+f 9'- 9' 9,'v R'02k'/sl 4 40 -/2. l>isc Hr $'O 2 k'/sf//40 ~*" ros door H4/& uw-3 Shatts who40 en & as a.s-n Wr & noten I' Operefor Witnessed 4 Test Record Procedsrc Pressvec Time Reject Accept _ by _ Dote F Art 155 _b A&)y/ j/ " *l h10$9 /CMid // >L9/s.v ? Hyd.o L g.' Sto:n 1.cokogo b / M ~>t Gogo No. 8 6 - 8_,,,, Authorized insooctor ^ * ~ ' ~ ~ ' (* Acc. U Witnessed P. essure Time Lcokogo Std. Re[cet Accept by Date 3.. ,t".O Scot 8 Stem $ 35 Ata /0 N. l~l - f / fey A)/ Q Locheas .M. - .M_ Gage No. Ld-/J Authorized Inspcetor O witnessed Acc. Cycle dmo Sid. Reject Accept by Date s4 (D_L, pk, -),., y O m rotina t-/ ju , g,,., Authorized ins: ector Spoeial Cleaning Per f//,2,f / bfg Final Wlve Inspe: tion Accepted: %.44#3 (Incivies Accootenco of Wlve Testing, nomeplore Witnessed bygg.g g,m rnorking and p:ckcD n0) I /4 - 'U' M Q A.[ h M..E / Dole /O.Qg-7 ~ yt j' ,/ < /p > ^ Form No, liPCo. C/OAP-6-1.2 91 A18.03 W;c M ~}}

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