ML20198L134

From kanterella
Jump to navigation Jump to search
Forwards RAI Re Instrumentation & Controls for AP600.Staff Concludes That Encl Does Not Contain Portions of Info for Which Exemption Is Sought
ML20198L134
Person / Time
Site: 05200003
Issue date: 12/02/1997
From: Kenyon T
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9801150181
Download: ML20198L134 (4)


Text

h a

3

+g f

1 f; JDecemb:r 2,;1997-

)[ri

i.

e

-(A

.)

Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities

" Nuclear and Advanced Technology Division -

iWestinghouse Electric Corporation ;

S, 4 '

P Oi Box 355? _

"^t ~ >

,i e ;Q.' % ; Pittsburgh, PA 15230:. 4 -

f3:

~

+. ;

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSTRUMENTATION

.Su D

- - AND CONTROLS FOR THE AP600 Tt3 Py~

w 0<

s

  • if 4

"s

y., e

Dear Mr. Liparulo:

4 T N.. s i k, N ;-,.

q,'

O,#

1 As a result of its review of the June 1992 application for design certification of the AP600; the.

N, " { p!:

([j h

staff has prepared the final safety evaluation report (FSER) on Section.7.0 of the AP600J,

y-jj 4 3

- ':A

.f Standard Safety Analysis Report (SSAR).- The FSER identifies an open item needing resolution M i s i 4.

O ]f (. t' W by Westinghouse before the staff can complete its review of this SSAR section. This issu TV A l discussed duriag a November 13,1997, telephone conference between the NRC staff andi f/ t

.y 5

+ g f f b Westinghouse representatives. De open item is identified in the enclosure as Q420.127F.

f; g hy ? lou have requested that portions of the information submitted in the Ju i

WN

, e r

/

?! j f ;Y, design certification be exempt from mandatory public disclosure ' While the staff has not "g~

/ i J

'

  • M" W 3 completed its review of your request in accordance with the requirements of 10 CFR 2.790, that -

portion of the _ submitted information is being withheld from public disclosure pending the staff's

(', final determination.1The staff concludes that the enclosure does not contain those porti J6 f

f information for which exemption is sought. However, the staff will withhold this letter from public

' tolie~riffth's staff'is concluiil6nsTlf, aftiRhahime, yod'd5;not request that all or p 4 e information in the enclosures be withheld from public disclosure in accordance with 10 CFR 4.790, this letter will be placed in the NRC's Public Document Room.

p If you havri any questions regarding this matter, you can contact me at (301) 415-1120.

Sincerely, original signed by:

Thomas J. Kenyon, Project Manager Standardizction Project Directorate.

Division of Reactor Program. Management Office of Nuclear Reactor Rsgulation I

. Docket No.52-003

Enclosure:

[As stated

~ Mkr...

cc w/ encl:: Sea next page :

q DISTRIBUTION, n ' M

bg y See_next page t{(

' ~ L DOCUMENT NAMEL A:\\RAl.l&C -

L LTo receive a copy of this document, Indica'e in the bcx: "C" = Copy without.

)

  • attachment / enclosure ^"E" = Coay with attachment / enclosure "N" = No copy.

x OFFICE L PM:PDST:DPR,M D:PDST:DRPM:

M ESh k -TRQ k

(-

2 NAME7 DATEb

<12/F 97) 12/.3497

/

1

$k@M " ' 98di150181 971202

  • it O f

PDR ADOCK 05200003

. 4y- '

EE M o

PDR

- r1 'W

Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc:

Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Ucensing Advanced Plant Safety & Licensing Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Enclosure to be distributed to the following addressees after the result of the proprietary evaluation is received from Westinghouse:

Mr. Russ Bell Ms. Lynn Connor Senior Project Manager, Programs DOC-Search Associshs Nuclear Energy Institute Post Office Box 34 1776 i Street, NW Cabin John, MD 20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC-781 Advanced Reactor Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC-754 Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE 50 Barton Z. Cowan, Esq.

19901 Gem,aniown Road Eckert Seamans Cherin & Mellott Germ- #.own, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr Lharles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE 50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 L--..

\\<

i

DISTRIBUTION: Letter to Mr. Nicholas J. Linarulo. Dated: December'2. 1997 VDocket File >Ersclosure to be held for 30 days
  • PUBLIC POST R/F

' JWRoe DMatthews TRQuay TKonyon

-WHuhman e

' JSebrosky DScaletti

' JNWilson JMoore,015 818

WDean,0-5 E23 ACRS (ii) -

,,. f=.

MPSeimen,0-15 B18 HLi,0-8 H3 i-

{;

' '~

MGareri,0-8 h3 -

1 3-

~ { } 4, <

.a

  • 3_

2,

~

-\\ p f %,,

4 p,..

s f

.y 7

~..

.g

+

s

. s

,.g f '

u y

/

('_ f'

~~

9 y

'1

^., 9 y y

.c'

.3 l

4 N

L 1

.,Isu f; ; *, 4 i

y e

o p p ti. -

x,

.)

i

,x d-y

. l 4]-

1.

i-K.

y

?-

,, ex

~

q!

2

[

A g

-w.

3 -

r

_ ')

  • I

}

z

(

s I

e

+

.e a-


m

i

(..,..'*

OPEN ITEM ON INSTRUMENTATION AND CONTROLS FOR THE AP600 DESIGN 420.127F On October 21,1997, Westinghouse submittei a design (;escription which shows the arrangement of differential pressure instruments that will be used to measure the core makeup tank (CMT) level. Ten level channels are installed on each CMT with eight of these being narrow range level switches that 1re qualified for pust-accider.t monitoring. Four of these narrow range level s' ches are used to actuate the automatic depressurization system (ADS) stage 1 valves and the other four level switches to actuate ADS stage 4 varves. The remaining two level channels are wid.' range level indication channels which are used to verify the levei during normal operation, but are not qualified for post accident monitoring.

Decause the CMT is full during normal operation and four (ovel switches share one set of level taps, the staff is concemed that a postulated common-mode failure in the level sensing line could make all 4 level switches at each CMT incorrectly stick at the high position without being detected until the next surveillance period. The instrument channel operation test for CMT level is perfomied every 92 days and the channel calibration is performed every 24 months. A comi.wn undetectable failure willinhibit a protective action. Address this concem.

1 Enclosure y

j