ML19269D045
| ML19269D045 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/18/1978 |
| From: | Crane P PACIFIC GAS & ELECTRIC CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7902260620 | |
| Download: ML19269D045 (9) | |
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BRC PN' PACIFIC GAS AND E LE C T RI C C O M PANY bbW3 77 BEALE STREET. 31ST FLOOR . SAN FR AN CISCO, C ALIFO R NI A 94106 - (415) 781 4211
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Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 Division of Proj ect Management U.S. Nuclear Regulatory Commission . Washington, D.C. 20555 j ,, [z,g.
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Re: Docket No. 50-275-OL .r.U .r Docket No. 50-323-OL ,f f '^ d Diablo Canyon Units 1 and 2 k" s .. h ',.f:,,./> ;" ' '
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Dear Mr. Stolz:
@h %3.:h,3 Your letter dated July 25, 1978 requested additionat information on the Diablo Canyon main steam line break (MSLB) analysis. Our letter of November 2, 1978 stated in part that we expect to satisfactorily qualify all safety related electrical equipment for a new MSLB analysis by performing component thermal analysis.
We have performed the component thermal analysis based upon the calculations made by the NRC for a typical containment. Attachment 1 summarizes review of MSLB using heat transfer approach. Figure 1 shows containment temperature with respect to time. Attachment 2 is a sample calculation of instrument thermal response to containment environment. Attachment 3 lists the qualification temperacares for Class IE equipment with potential for exposure to a main steam line break. As indicated in the attachments, the calculated instru-ments and equipment temperatures are less than what would be ex-pected from a design basis loss-of-coolant accident. We conclude that the qualification program provides adequate margin for steam line break accidents. 79022606R G _
Mr.' John F. Stolz December 18, 1978 Kindly acknowledge receipt of the above material on the enclosed copy of this letter and return it to me in the enclosed addressed envelope. Very truly yours, PHILIP A. CRANE, JR. Enclosures CC w/ enc.: Service List -- -- f
. ~ ATIACHMENT 1
/:
Environmental Temperature Qualifications ?? For . Containment Instrumentation ,, ., e. Wa have reviewed the environmental conditions (mainly temperature that equipment listed in the table of Environment Qualifications of Class IE Equipment, submitted in a lette, on May 3, 1978, would be subject to in the event of a main steam line break. The instrument transmitters listed are protected more than those at most other reactor installations because of the protective cabinets used in the Diablo Canyon design. Although the instrument cabinets were provided for other purposes, they do afford insulation from the general containment environment in the event of a super-heated steam environment. For purposes of calculating the environmental temperatures of the instrument cransmitters and equipment, parameters were taken from a typical NRC Staff calculated contain=ent atmosphere. The Staff's calculational results were obtained from an internal memorandia dated February 24, 1978,
" Containment Environmental Qualification Best Estimates Evaluation for Main Steam Line Break Analysis." The basic parameters as used are contained in Figure 1. The assumptions and a sample calculation are shown in Attachment 2.
Using conservative heat transfer assuuptions, calculations show that the peak surface temperature of the instrument transmitters would be about 252*F. This is less than the saturation temperatures resulting from a design basis LOCA. Using more realistic, best estimates, heat transfer coefficients would result in a peak temperature of about 230*F which is less than the saturation temperature of the steam environment. With regard to equipment in the containment, the peak temperatures were calculated to be 262*F. We have, therefore, concluded that the qualification program for the design basis LOCA environment provides adequate margin for a steam line break temperature exeirsion.
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Attachment 2 Sample Temperature Calculations Assumptions
- 1. Material is steel flat plate geometry
- 2. Use in. finite thermal conductivity -- no insulation effect of paint
- 3. Instrument wall thickness of inch Heat Balance WCp hh = hA(Tc - T) ,,
lJ - Where: " 0 ,. tR W = weight of instrument , _fgi Cp = specific heat ^ < ~ > L7j T = temperature . , . ,q G = time Qf h = convection heat transfer coefficient :\ /
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A = heat tr'ansfer area Subscripts: C = temperature of containment atmosphere sat = saturation temperature of steam in = initial wall temperature Referring to temperature response figure, it is assumed that the heat transfer process is in two distinct parts; that of steam condensing for the first 23 seconds followed by a heat up due to superheated steam in the second time period. In the first time period a high condensing heat transfer coefficient of 400 BTU /hr ft2 0F was assumed and in the second time period a high steam heat transfer coefficient of 5 BTU /hr ft 0F2 was- chosen Performing calculation for 1 ft 2 area for first 23 seconds: W = 10.4 Cp = 0.11 h = 400 Tsat = 240 Tin = 120 .
hA T23 = T sat - (Tsat - Tin) e ;7 @ P T23 = 227 Or for ease of calculation it was assumed that at 23 seconds T23 = 240 , Calculating second time period to 130 seconds: h =5 Tin = 240 Te = 335 and T130 = 252 e mins duS e e
~
QUALIFICATION TEMPERATURES FOR Sheet 1 of 3 - CIASS IE EQUIPMENT '. WITil POTENTIAL FOR EXPOSURE TO A MAIN STEAM LINE BREAK Class IE Equipment inside Contairment - Subject to LOCA Equipment gnufacturer g (Model No.) Qualification Temperature
- 1. Pressure and Differential Transaltters
- a. Pressurtzer Pressure
- Rosesomt 1152 350*F '.
- b. Pressurtzer Level ITT Barten 7_64 320*F
- c. Containcent Sung Level ITT Barton 764 320*F
- d. Reactor Coolar.t System ITT Barton 763 320*F Wide Rar.ge Psessure
- e. Karrow Range Steam ITT Barton 764 320*F Generator Level
- f. Steam Flow * 'osecount 1152 350*F .f
- g. Sensor for Contaf rment Pressure Sarton 351 320*F
.Th, :I T>~T.lJ q A-{ h ,
- 2. Reststance Terwerature ,. f. %
Detector J, - u
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- s. Rea'c tor Coolant System Sostman 118348-1 ja Tg'; },1'l 320*F Temperature ...c r, i ~ '
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- 3. Valve Motor Operators Limitorque 5H3-0, 00. 000 ' , .',.
${ wy 340*F >
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- 4. Containment Fan Cooler Westinghouse 300/100 h.p. ' /;,({ g 326*F $
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Sheet 2 of 3 Type (Hodel No.) Qualification Tenperature Equipment Hanufacturer N502/03/04 340*F
- 5. Electrical Penetrations General Electric
- 6. Electrical Cables Stitcon/ Silicon 392*F Continental
$111 con /Hypalon ' 340*F*
Boston Stilan 554*F Raychem Tefre) 346*F Okontte Boston Silicon Glass 8rtad/ Kapton/Hypalon SealeJ spilce 357*F Raychem
- 7. Electrical Terminations EA180 340*F Namca
- 8. Stem Mounted Limit Switches 8300 See FSAR Paragraph 3.11.3-3 ASCO
- 9. Contaltunent Isolation 3302 Solenoid Valves 8316*
8321*
'Special valves with all plastic parts replaced with stainless steel or brass parts to withstand higher temperatures.
k Sheet 3 of 3 .
- Note for Qualification of Boston Cable The Boston " Silicon Glass Braid /Kapton/llypalon" insulated wires were tested in an autoclave at 302*F at 50 psig of saturated steam for .2 hours and 48 minutes. Insulation resistance was measured every 15 minutes during this period and found to be satisfactory at all times.
The insulation system of this conductor consists of silicon glass braid, 3 mils of Kapton tape, 6 mils of asbestos tape and an overall jacket of flypalon. The silicon glass braid, Kapton and asbestos tapes are all capable _ of maintaining their properties at temperatures. of 392*F. Ilypalon , as an insulation for other conductors, has been qualified to 340*F.
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