ML19309A857
| ML19309A857 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| 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,
[00/
indicate whether continuous surveillance or periodic tests are being S
accomplished on such valves to ensure integrity. Also indicate whether
///
valves have been known, or found, to lack integrity.
/} pp,.
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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
C.
9 g f..
~n..
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 rh' 4
Mr. G. F. Trowbridge
///_ SIl///[/04i*.
Office of Inspection & Enforcement Notary Public
(/
Div of Reactor Operations Inspection My Commission Expires:
4 C..*95. [*[5 d
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RGURE " A FARLEY UNIT
- 1
~~~ ~ ~~ _. CHECR VAe/E CotW\\GORAT\\oM COLO LF.G
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FIGURE "6' FARLEY UN I T
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NOTE /. ALL VALVE
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HEAT E.XCH444 ER.
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