ML20023D241

Proposed Tech Spec Changes Re Process Piping Penetrating Primary Containment

ML20023D241
Person / Time
Site:	FitzPatrick
Issue date:	05/13/1983
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20023D238	List: ML20023D237 ML20023D239 ML20023D241
References
NUDOCS 8305200272
Download: ML20023D241 (4)

Text

__

,,a-- -el--_ - 5,, 4---, _k ks_m +m_ _ - + - 2.-_ _eSw- aW - J4 - ,=-,A=-

- - - -ab ,- _, J - -- -, -+- -. ---w + . A g e G

l ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO PROCESS PIPING PENETRATING

PRIMARY CONTAINMENT l

4 d

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 8305200272 830513 PDR ADOCK 05000333 P PDR

-- - - - , , , - - - - , , , - - , , . . , - . .-- , - -,,,n,- ,-.--,-n., , , , ,..,,,,,,,.-,,-----,-n-- , , . , n .--, , - , . , ,,,--- ,,---, , .. , , .-.. . --,,,,,- . , , . . , ,-.-

_ ._ . 4 _ _. - .. -. . _ , _ --a_____. .

,5 a

I l~ .

, f 8

JCFNPP f

f48LS 3.7-1 i

! PROCESS PIPELINE PENEFRAf!NG PRIMARY CONTAINAENT (Numbers in parentheses are keyed to numbers on following pages equal codas are L Lsted codes are listed on followlng pages)

• Power Location Power Drywell Valve Type to Open Ref. to to Close Isolation ClosLng Normal Remarks an!

i Line Isolated Penetration (6) (5) (6) Group Drywell (5 ) (6) Signal Time (7) Status Exceptions 1

Main Steam Line X-74,8,C,D AO Globe Air amt A Inside Air and a,C,D,P,E

! Note (1) Open AC, DC spring 7 Main Steam Line X-74,8,C,D AO Globe. Air and A outside Air amt 8, C. D, P , E Note (1) Open AC, DC spring s

Mtin Steam Line X-8 MO Gate AC A Inside AC j Drain 8,C,D,1, E 15 see Closed Mtin Steam Line X-8 MO Gate DC 4 Outside DC Drain 6,C,D,P,E 15 see Closed i 4

From Resctor X-94, B Check -

A Outside Process Rev. flow NA Open

{ Feedwiter f i

From Reactor X-94, B Check -

A Inside Process Rev. flow NA . Open Feedwnter I

Reactor Water X-4L AO Globe Air amt 4 Inside Spring 8,C Sample NA Open.

3 AC Reictor dtter X-41 AO Globe Air amt A Outside Spring L 8,C NA Open

, Sample AC f 1 j Control Rod :Iy- X-36 Check -

A Inside Process Rev. f low NA) e draulic Return Controt Rod Hy- X-36 Check -

4 Outside Process 1

' Rev. f low NA) Opens on Rod draulic Return I movement and

) closed at att

) other times, Note (4)

Control Rod )

X-38 SO Valves Air and A Outside Drive Exhaust 1pring Note ( 4 ) NA)

• AC ,

)

)

Control Rod I X-38 SO Valves Air and A Outside Spring Note (4) 44) t Drive Exhaust AC  ;

D L

control Rod X-37 I So Valves Air and 4 Outside Spring Note (4) NA)

DrLve Inlet AC

) "

)

, Control Rod X-17 SO Valves Air and 4 Outside Spring Drive Inlet Note (4) NA)

AC i

i Amendmant No J P* 199

• t i

~ m - -

, a _- -4__eA - 1,u .J ~_m. a_ 4 +e- ~4 a4. J 2-_a m . m. _ a ,__ ,, ____4 ATTACHMENT II SAFETY EVALUATION RELATED TO PROCESS PIPING PENETRATING PRIMARY CONTAINMENT l

4 j

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 f

i i

l

-,. __ ,- _. ._, ~,,._ ,. ,_ _ . , -,,- . . _ , , . . . , ,,,_- .._-. . , . _ , - - - . _ _ _ _ . - , _ _ _ . - - . . _ _- _. - -- - _.-.. . .

Section I - Description of the Change ,

This proposed Amenoment to Appendix A of the James A. FitzPatrick Nuclear Power Plant Facility Operating License revises Table 3.7-1 (Process Pipeline Penetrating. Primary Containment) on page 198 to correct an inconsistency revealed during normal operation and described in Reference b. Isolation signals for two Reactor dater "B, C" from Sample Valves (drywall penetration X-41) are changed to "B, C, D, P, E." (Refer to page 206 of Appendix A for a description of'the isolation signal codes).

Section II - Purpose of the Change During normal operation, it was determined that the Reactor Water Sample Isolation Valves associated with penetration X-41 did isolate on all signals required by Table 3.7-1. The table was ,

not (

found to be in error. A design change (made during initial construction) had not been incorporated in tne Technical Specifications. During construction of the plant, the isolation signals provided these valves were properly reviewed and changed.

The FSAR was not updated to reflect this change, and therefore Table 3.7-1 was not updated. Immediate corrective action was to voluntarily keep these valves closed.

The Commission was informed of this via Reference b.

The purpose of this change is to ' rectify the, inconsistency between the plant as it was constructed and Table 3.7-1 of the Technical Specifications.

Section III - Impact of the Change This change will have no impact on the operation of the plant since it's only purpose is to correct an error'in the Technical Specifications as they are currently written.

Section IV - Implementation of the Change The change, as proposed, will not impact the ALARA or Fire Protection Program at FitzPatrick. -The proposed change will not impact the environment.

Section V - Conclusion The incorporation of these changes: a) willornot change the malfunction of probability nor the consequences of an accident equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility of an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report; c) will not reduce the margin of safety as defined in the basis for any Technical Specification; d) does not constitute an unreviewed safety question; and e) involves no significant hazards considerations as defined in 10 CFR50.92.

l Snction VI - References . .

(a) James A. FitzPatrick Nuc1 car Power Plant Final Safety l Analysis, revised July 14, 1982.

i (b) November 1, 1982 letter, C.A. McNeill, Jr. (PASNY) to R. C.

tiaynes (NRC) regarding LSR 82-045/03L-0.

l l

i l

I l

I

{

o i

1 I

i l

1 l

I I

I i

l i

{

. _ . . _ _