ML20070E189

Forwards Ssar Markup of Section 1A.2.34 Which Responds to TMI Item III.D.1(1).Mod Makes Section Consistent W/Ts 5.5.2.2.Change Will Be Included in Amend 35 Mod Package Scheduled for Distribution Later This Month

ML20070E189
Person / Time
Site:	05200001
Issue date:	06/08/1994
From:	Fox J GENERAL ELECTRIC CO.
To:	Boyce T Office of Nuclear Reactor Regulation
References
TASK-3.D.1.1, TASK-TM NUDOCS 9407140165
Download: ML20070E189 (2)

Text

- ,_ .- . . - . .- - . . _

4

. . . ( )

- GENuclear Energy j caouerccm

? ?5 Cume henue Lrtme CA 95C5 June 8,1994 Docket No.52-001 i

i i

r Tom Boyce, Senior Project Manager ~

Standardization Project Directorate  !

Associate Directorate for Advanced Reactors  ;

and License Renewal  ?

Office of the Nuclear Reactor Regulation 1

Subject:

Submittal Supporting Accelerated ABWR Schedule -TMI Item III.D.1.l(1)

Dear Tom:

J Enclosed is a SSAR markup of Section 1 A.2.34 which responds to TMI Item  ;

llI.D.1.1(1). This modification makes this section consistent with Technical 1 Specification 5.5.2.2. This change will be included in the Amendment 35 modification l package scheduled for distribution later this month. )

1

- Please provide a copy of this transmittal to Melinda Malloy. I Sincerely, Yd J k Fox Advanced Reactor Programs -!

I cc: . Alan Beard GE) l Norman Fletcher DOE) i Joe Quirk GE)

Cal Tang GE) 8 I i m,-

1SGG08 g l 9407140165 940600 hv.op )l0n PDR ADOCK-05200001 Y -

l A l 23A6100 Rev. 4 I

. AB.WR standardsafety Analysis Rep: '

I

Response

All of the generic February 21,1980 GE responses were reviewed and updated for the ABWR Standard Plant. The specific responses are provided in Table IA-1.

1 A.2.34 Primary Cooir nt Sources Outside Containment Structure [iii.D.1.1(1)]  !

1 NRC Position Applicants shallimplement a program to reduce leakage from systems omside containment that would or could contain highly radioactive fluids during a serious I

transient or accident to as-low-as-practical levels. This program shall include the following:

(1) Immediate Leak Reduction (a) Implement all practical leak reduction measures for all sptems that could carry radioactive fluid outside of containment (b) Measure actual leakage rates with systems in operation and report them to the NRC (2) Continuing Leak Reduction-establish and implement a program of preventive maintenance to reduce leakage to as-low-as-practical levels. This program shallinclude periodic integrated leak tests at inten als not to exceed l each refueling cycle. I

Response

Leak reduction measures of the ABWR Standard Plant include a number of barriers to I containment leakage in the closed systems outside the containment. These closed '

systems include:

(1) Residual Heat Removal (9) Proces s sca. w 6el Codammk Abo.rphcat  !

(2) High Pressure Core Flooder g og l (5) Low Pressure Core Flooder b 0 m sssoA Peve6d Modw )

( p a r \- o-F LO S )

(4) Reactor Core Isolation Cooling g a) ggy.o e,w Q.a.to 4 we#

(5) Suppression Pool Cleanup Ct3ISY^dd1 M N "

(6) Reactor Water Cleanup b

(7) Fuel Pool Cooling and Cleanup (8) Post-Accident Sampling j

1A 32 Response to TMI Related Matters - Amendment 34 b .