ML20009C704

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Forwards Addl Info on SER Open Item 25 Re Reactor Core Isolation Cooling Temp Sensors
ML20009C704
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 07/17/1981
From: Mccaffrey B
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
SNRC-597, NUDOCS 8107210375
Download: ML20009C704 (5)


Text

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LONG ISLAND LIGHTING COMPANY 4

J 7 $m SHOREHAM NUCLEAR POWER STATION f.a__--.__-,.,_..?

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  • r.o. sox en e, nown couwrav no Ao wAomo mvein, ca.v. $$7a2 July 17, 1981 SNBC-597 s 4 x.g3 gs, y', .
/ -Q Mr. Harold R. Denton, Director  ? -

2I Office of Nuclear Reactor Regulation y #'

U.S. Nuclear Regulatory Commission 4> 7887A /s,/ (6 Washington, D.C. 20555 'L 'i,

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'f h.', ),e SHOREHAM NUCLEAR POWER STATION - Unit 1 fif"tp Docket No. 50-322

Dear Mr. Denton:

Enclosed herewith are 60 copies of additional information regarding SER Open Item No. 25, RCIC Temperature Sensors, which was previously identified as requiring clarifying infor mation to complete NRC review.

-If you require additional information or clarification, please do not hestitate to contact this office.

Very truly yours, ..; ,

M/8-N '

B. R. McCaffr Manager, Project Engineering Shoreham Nuclear Power Station...,.

CC/mh . ': .

Enclosures Ol cc: J. Higgina 3 , $CP y

8107210375 810717 PDR ADOCK 05000322 E PDR FC 4935

i 46 1 Open Item No. 25 NRC Request:

1

a. Provide an illustration to show where the temperature sensor elements are located.

~~-

b. Describe why a failure (steam line break) will not isolate both systems (HPCI and RCIC).

Response

+

a. See the attached table for the location of the temperature sensor elements .
b. To the maximum extent possible, the temperature sensor elements are placed to minimize the possibDity of interference between sensors and isolation of both the RCIC and HPCI systems. In order to be more conservative, for the condition of a break in the RCIC steam i supply line it is assumed that HPCI also becomes unavailable.and vice versa. This is d,iscussed in detail in FSAR sections 3C.4.3.9 and 3C.4.4.9. As discussed therein, the plant can nevertheless be safely shut down. Note that each pipe break analysis considers, in addition to consequential effects, the worst single active failure associated with each pipe break.

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1 HPCI & RCIC TD'PERATURE SENSOR ELD 4 BITS

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' Elevation Radius i Tomo. Element Azimuth (ft) (ft) l 1E51*TE 052A 2110-10' 24.06 60.78

-i 1E51*TE 052B 2040-10' 22.54 55.79 1E51*TE 053A 2040-37' 20.42 'B.40 1E51*TE 053B 2190-13' 26.99 61.53 1

l 1E51*TE 054A 1940-26' 71.91 65.18 i 1E51*TE 054B 1970-26' 68.71 65.08 le51*TE 055A 1900-44' 65.38 45.76 9 1E51*TE 055B 1900-28' 64.19 49.46 1E51*TE 055C 1900-12' 69.32 45.22 1E51*TE 055D 190o-49' 71.77 47.73 -

3E41*TE 053A 190o-43' 37.19 50.72 1E41*TE 053B 1890-10' 37.23 48.19 1E41*IE 054A 2030-15' 24.98 58.97-1E41*TE 054B 2050-36' 24.99 60.81 1E41*TE c56a 193o-56' 69.53 63.15

! 1E41*TE 056B 1960-07' 67.61 65.12 I

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EL. 63'- 0" TO 78'- 7" SHOREHAM NUCLEAR POWER STATION - UNIT 1