ML19309A857

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Forwards Response to NRC 800223 Request for Info Re Intersystem Loca.No Valve Configurations Conform to Event 5. Plant Design & Insp Commitments Are More than Sufficient to Ensure That Event 5 Will Not Be Problem at Facility
ML19309A857
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 03/24/1980
From: Clayton F
ALABAMA POWER CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 8004010425
Download: ML19309A857 (9)


Text

o

. Alabama. Power Company 600 North 18th Street Post Office Don 2641 Birmingham, Alabama 35291 Telephone 205 323-5341 hhoPv7.'#,"iff.n, AlabamaIbwer tre nutwo eenc sem March 24, 1980 Docket No. 50-348 Division of Operating Reactors Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. Darrell G. Eisenhut Centlemen:

J. M. FARLEY NUCLEAR PLANT-Unit 1 LWR /PCS PRESSURE ISOLATION VALVES We have evaluated the valve configurations which could be involved in an intersystem loss-of-coolant accident per your letter dated February 23, 1980. Our response is as follows:

1. Describe the valve configuration at your plant and indicate if an Event V isolation valve configur ation exists within the Class 1 boundary of the high pressure piping connecting RCS piping to low pressure system piping: e.g. (1) two check valves in series, cr (2) two check valves in series with a MOV;

Response

Attached is a sketch for each of the valve configurations identif led below:

Sketch "A" - Low HD Inj., Cold Leg Sketch "B" - Low HD Inj., llot Leg Sketch "C" - Ili IID " BIT" Inj. , Cold Leg Sketch "D" - 111 IID Inj . , Cold Leg Sketch "E" - 111 HD Inj . , (BIT Bypass), llot Leg Sketch "F" - Normal Charging Sketch "G" - Normal Letdown As these sketches clearly indicate, none of these configurations conform to Event V.

2. If either of the above Event V configurations exist at your facility, indicate whether continuous surveillance or periodic tests are being

[00/

S accomplished on such valves to ensure integrity. Also indicate whether ///

valves have been known, or found, to lack integrity. /} pp,. d3g

5. 0<4N4 6  !

P. Po//r i P 8004o1a 42s

Division of Operating Reactors Page 2 March 24, 1980

Response

As indicated in response to Item (1), there are no Event V configurations at Farley Unit 1.

3. If either of the above event V configurations exist at your facility, indicate whether plant procedures should be revised or if plant modifi-cations should be made to increase reliability.

Response

As indicated in response to Item (1), there are no Event V configurations at Farley Unit 1.

The present plant design and inspection commitments are more than suf fi-cient to ensure that the hypothetical Event V accident could not be a problem at our facility.

If you have any questions or comments, please contact us.

Very truly yours, b

~n . . C.

9 g f. .

LdacKe*L.-

F. L. Clayton..'Jr. '

FLCJr/TNE:bhj SWORN TO AND SUBSCRIBED BEFORE ME THIS,.f8 . DAY OF /'/d/2/*f4 Attachments 1980.

n ec: Mr. R. A. Thomas c'; )! / /7 4 Mr. G. F. Trowbridge ///_ SIl///[/04i*. rh' Office of Inspection & Enforcement Notary Public Div of Reactor Operations Inspection (/

4 My Commission Expires:

d csC. v.*95 .- [*[5 I

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- FIGURE

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NOTE /. ALL VALVE

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PRE.CEEoEo SY REGEM, Q . \ . E.2] .

HEAT E.XCH444 ER.

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