ML19305C087

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Responds to NRC Re Primary Coolant Sys Pressure Valves.Describes Valve Configuration within Group I Boundary of High Pressure Piping.No Event 5 Isolation Valve Configuration Exists
ML19305C087
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/19/1980
From: Daltroff S
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 8003250576
Download: ML19305C087 (5)


Text

.

s PHILADELPMiA ELECTRIC COMPANY 2301 " dKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101

$HIELOS L. C ALTROFF ELECT 4tc PRCC CTioM March 19, 1980 Re: Docket Nos. 50-277 50-278 Mr.

D.

G.

Eisenhut, Acting Director Division of Operating Reactors JS Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Eisenhut:

l Th is letter is in response to your letter to all Ligat I

Water Reactor (LWR) licensees dated February 23, 1980 concerning primary coolant system pressure isolation valves at Peach Bottom Units 2 and 3.

The items of concern and our responses are listed sequentially.

Item 1 Describe the valve configuration at your plant and indicate if an Event V isolation valve configuration exists within the Class I boundary of the high pressure l

piping connecting PCS piping to low pressure system l

piping; e.g.,

(1) two check valves in series, or (2) two caeck valves in series with a MOV.

Response

For Peach Bottom Units 2 and 3, no Event V isolation valve

. configuration exists within the Group I boundary of the hign l

pressure piping, i.e.

(1) two check valves in series, or (2) twc che'k valves in series with a locked open motor operated valve.

(See Attachment I)

(

l b

e, 1.

.s l-o 1/

f e

10D03 25 05 ' E

d '

Mr.'D.

G.

Eisenhut Page 2 Item 2 If either of the above Event V configurations exist at your facility, indicate whether continuous surveillance or. periodic tests are being accomplished on such valves to ensure integrity.

Also indicate whether valves have been known, or found to lack integrity; and

Response

This item doe not apply due to the determination in Item 1.

Item 3 If either of the above Event V configurations exist.at your facility, indicate whether plant procedures should be revised or if plant modifications should be made to increase reliability.

Response

This item doe not apply due to the determination in Item 1.

Should you hava any questions or require additional information, please do n.t hesitate to contact us.

Very truly yours, Attachment

A?TACHWtNI I LISH? WATER REACTOR PRIMARY C00LAlli SYSTEM PRESSURE ISOLA?!0ft vs.LV HIGH PRESSURE TO LOW PRESSURE C0ftf1ECTI0tlS SYSTEM P S ID C0tlFIGURATION ll0T EVEfli V BEC#'JSE 28 \\ '96 NO HIGH PRESSURE-N [-

FEEDWATER 351.308 LOW PRESSURE WO CONNECTION UNTIL 2149 AFTER 3RD CHECK VALVE 8 2ND WOTOR OPERATED VALVE.

HIGH PRESSURE,,,(HP) f,,_

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SS VALVES I CLATE HIGH PRESSURE 365 f

LOW PRESSURE COOLANT INJECTION PIPING W-A0 WO 1,8 18 L,

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NORWALLY CLOSED SIMILAR TO VALVES ISOLATE REACTOR CORE 353 ISCLATION COOLING HIGH PRESSURE LOW guRE COOLANT INJECTION p

PEACH BOTTOW ATOWIC PDF9 STATION SHEET 1 0F 's WAR 0H 1980 j

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SYSTEW P 1 10 CONFIGURATION NOT EVENT V BECAUSE

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96W NORMALLY CLOSE0 REACTOR WATER 351.354 f

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- $2 PIPING.

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-hLP TO RAD TO CONDESER WASTE f

PEACH 80TTOW ATOWIC POWER STATION h

SHEET 2 0F 3 l

WARCH 1980

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SYSTEW P 1 ID CONFIGURATION fl0T EVEffi V BECAUSE 8I"8L

" K V^L E 28 1 96 N0RWALLY CLOSED START UP 351

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1 rWO 2 3 TO CONDENSER -

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?I I9 "yALVES ISOLATE HEAD SPRAT

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LOW PRESSURE l

PIPING.

HP _.,

LP RELIEF VALVE,

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OPS NO TWO CHECK 118 VALVES IN SERIES WO MO NORMAlt.Y CLOSED 361 18 1

17 RES g yEAT SHUTDOWN COOLING

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j PIPING.

i CONTINUQUSLT ENIT0RE HP

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PEACH 90TT0W ATOWIC POWER STATION WARCH 1980 SHEET 3 0F 3 l

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