ML20134Q143

From kanterella
Jump to navigation Jump to search
Summary of 970204 Meeting W/Westinghouse in Rockville,Md Re Proposed Design Changes in Response to NRC Policy Position in SECY-96-128 on post-72 Hour Actions
ML20134Q143
Person / Time
Site: 05200003
Issue date: 02/20/1997
From: Huffman W
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
SECY-96-128-C, NUDOCS 9702260282
Download: ML20134Q143 (56)
v • d • e


Text

.. .. -_. . - . - .- _ . - -- .- . .

, p*H4 y h UNITED STATES 7 E NUCLEAR REGULATORY COMMISSION

'f WASHINGTON, D.C. 300edHlo01

% p* February 20, 1997 APPLICANT: Westinghouse Electric Corporation
PROJECT
AP600

SUBJECT:

SUMMARY

OF AP600 MEETING ON PROPOSED DESIGN CHANGES RELATED TO POST-72 HOUR ACTIONS i

The subject meeting was held on February 4, 1997, in the Nuclear Regulatory Commission (NRC) Rockville, Maryland, officer between representatives of Westinghouse and the NRC staff. The purpose of the meeting was for Westing-house to present proposed AP600 design changes in response to the NRC policy position in SECY-96-128 on post-72 hour actions. The Westinghouse goal was to obtain feedback from the staff on the acceptability of the proposed changes.

The changes proposed by Westinghouse include increasing the size of the passive containment cooling system (PCS) to provide additional makeup water supply to the spent fuel pool and up to 7 days of sustained cooling water to 4

the containment shell. The spent fuel pool makeup water supply will be supplemented to include seismic connections from the PCS tank and from the i

cask washdown pit to ensure at least a 7 day supply of makeup water to replace spent fuel pool boiloff under worst case spent fuel pool heat load conditions.

Cross-connections between the spent fuel pcol cooling system and the active i residual heat removal system will be provided to permit full core offload into l the spent fuel pool and as a backup to the normal spent fuel pool cooling '

i system. Two permanently mounted 15 KW ancillary diesel generators will be provided to supply post-72 hour power to post accident monitoring instrumenta-tion, emergency lighting and PCS makeup pumps. The ancillary diesel genera- 3 i

tors will be protected from natural phenomena, including seismic events, l consistent with GDC 2. Post-72 hour control room habitability and instrumen-  ;

tation & control (I&C) equipment room environmental control will be estab-lished by opening the control room doors and establishing natural circulation cooling since Westinghouse believes that dose rates in the main control room  !

i will be negligible 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after a design-basis accident (DBA). This is a change from the previous AP600 post-72 hour actions associated with control room habitability in which additional bottled air would be brought in from offsite to protect operators from radiological exposure (if necessary after 72 i

hours). Portable control room air conditioning units and portable diesel '

generators to power the air conditioning units would no longer be used as part

of the post-72 hour action approach to cool the control room and I&C equipment

, spaces.

Highlights of the staff's feedback on the proposed changes include the following:

In determining water flow from the PCS to the containment shell for the i

7 day period following a DBA, what was the Westinghouse containment pressure criteria after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 7 The staff also noted that the 18 gpm water flow to the containment shell after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> appears to be outside the range of qualified water coverage data.

9702260282 970220 WC HLE CENTER COPY PDR ADOCK 05200003 A PDR

'2- > February 20, 1997 v  ; ,

'Because issues related To*the' calculation!of source terms have not been resolved, the acceptability of opening Lthe controltroom doors after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (from a DBA dose: perspective) will need to bejlooked'at closely by ,

the staff. <

ll .

, -s ,

1

~

The staff questioned Westinghouse's assertion that'the AP600 global '

seismic analysis would not be substantially,affected by the proposed '

changes to the PCS tank. .

Since Westinghouse is r_elying-on boiloff as the seismically, qualified '

method of removing ~ heat from the spent fuel pool and because the AP600 design does not include a seismically qualified heating, ventilation, and air conditioning system, Westinghouse will need to address where the steam goes from the spent fuel' pool boiling and,how it would affect main control room habitability after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The availability controls of the ancillary diesel generators will need >

to be explained. In addition, the controls on quarterly testing and how testing will be implemented by the COL applicant will need further i clarification.

Westinghouse requested that formal feedback on its presentation and proposed design changes be provided by February 11, 1997. The staff agreed to this commitment.

Attachment 1 is the list of meeting attendees. Attachment 2 is a copy of the presentation handouts.

original signed by:

William C. Huffman, Project Manager.

Standardization Project Directorate r Division of Reactor Program Management Office of Nuclear Reactor Regulation i Docket No.52-003 Attachments: As stated cc w/ attachments:

See next page DISTRIBUTION:

See next page l DOCUMENT NAME: A:PST72MTG. SUM r T> seestwr espy of thle aloeunient,inessene in the boa: "C" = copy without ettechment/ enclosure' *E' = Copy with attachment / enclosure *N* = No copy 0FFICE PM:PDST:DRPM l D:PDST:DRPM l NAME WCHuffmant w TRQuay f '

~

DATE 02RC/97 02/m/97 OFFICIAL.. RECORD COPY < ,

s- ,

y s

4 -

t~

+

. . s s

u

i l

D Westinghouse Electric Corporation Docket No.52-003 l

, 4 l-cc: Mr. Nicholas J..Liparulo, Manager Mr. Frank A. Ross )

Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 1 l Nuclear and Advanced Technology Division Office of LWR Safety and Technology l Westinghouse Electric Corporation 19901 Germantown Road )

l P.O. Box 355 Germantown, PW 20874 l Pittsburgh, PA 15230 Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute i Westinghouse Electric Corporation 1776 Eye Street, N.W.

Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 l Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34

, Westinghouse. Electric Corporation Cabin John, MD 20818

, Energy Systems Business Unit l Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 l Nuclear and Advanced Technology Division San Jose, CA 95125 ,

Westingliouse Electric Corporation l l Dne Montrose Metro Mr. Robert H. Buchholz f 11921 Rockville Pike GE Nuclear Energy >

Suite 350 175 Curtner Avenue, MC 781  :

Rockville, MD 20852 San Jose, CA 95125 ,

l Mr. Sterling Franks Barton Z. Cowan, Esq.

U.S. Department of Energy Eckert Seamans Cherin & Mellott i NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219  !

Germantown, MD 20874 i Mr. Ed Rodwell, Manager  !

Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874 i

l l

.. .. - . . . - - - _ - ~

1 .

6 DISTR::BT::0N w/ attachments:

4

'm pMe . .

PUBLIC ,. ,

.PDST R/F- .

'TMartin

DMatthews TQuay '

4-

'WHuffman

TKenyon-  ; '

l .JSebrosky ,

j ';

4 DTJackson' i SCollins/FMiraglia,.'0-12 G18 >

AThadani, 0-12 G18 '

L GHolahan, 0-8 E2- -

4 Glainas, 0-7 D24 I JMoore, 0-15 818 i G8agchi, 0-7 H15 l

. WDean, 0-17 G21 '

i.

CMiller, 0-10 D4 4 1

TMarsh, 0-8 D1 '

CBerlinger, 0-8 H7
. JCalvo, 0-7 E4 JWermiel, 0-8 H3 DISTRIBUTION w/o attachments

JLyons, 0-8 E23 i ALevin, 0-8 E23 4- ACubbage, 0-8 E23 i HWalker, 0-8 01 .i l JRaval, _0-8 DI. i i EThrom, 0-8 H7 l j JKudrick, 0-8 H7 i DThatcher 0-7 E4-NTrehan, 0-7 E4 REnch, 0-10 D4 JLee,.0-10 D4 i HLi, 0-8 H3

.TCheng, 0-7 HIS MGareri, 0-8 H3 JHolmes, 0-8 D1 )

SJones, 0-8 D1 i BThomas, 0-8 D1

.CLi, 0-8 D1 JDawson,.0-8 H7 ACubbage, 0-8 E23  !

ACRS (11) J l I I .;

gob 4 4 A, -

k

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

l l

WESTINGHOUSE - NRC MEETING ON PROPOSED AP600 DESIGN CHANGES TO ADDRESS POST-72 NOUR ACTIONS FEBRUARY 4, 1997 i

I l MEETING ATTENDEES l

l 88ME ORGANIZATION Brian McIntyre Westinghouse '

Ed Cummins Westinghouse l Ron Vijuk Westinghouse Tom Hayes Westinghouse i Gary Holahan NRC Tom Kenyon NRC (Part Time)

Alan Levin NRC Ted Quay NRC Bill Huffman NRC Jim Lyons NRC Mario Gareri NRC Narider Trehan NRC Dale Thatcher NRC Jay Lee NRC l

Rich Emch' NRC Hulbert Li NRC Tom Cheng NRC Jeff Holmes NRC Steve Jones NRC Brian Thomas NRC Chang Li NRC Jack Dawson NRC Ed Throm NRC Jack Kudrick NRC Amy Cubbage NRC Steve Mixon NUS Charles Thompson DOE l

i i

Attachment 1 l

1 l

. 4 I

PRESENTATION HANDOUT MATERIAL FRON FEBRUARY 4, 1997, MEETING ON PROPOSED AP600 DESIGN CHANGES TO ADDRESS POST-72 HOUR ACTIONS l

l l

1 l

Attachment 2 l

..e ,

~

l jii""ill j -

l ii AP600 AP600 Systems Changes Post 72 Hour and Spent Fuel Pool Cooling Presentation to NRC Staff

~

R. P. Vijuk Manager,. Systems Engineering (412) 374-4728 Wesiinghouse 2567p j

=-

~

i pou iI l AP600 PCS Design Changes

^"oo e Additional 150,000 gallons of water in PCS storage tank on top of shield building l

e Add fourth stage standpipe for additional control of flow from l PCS tank to containment shell over 7 days e Modify PCS recirculation path to als merve as post 7 day onsite equipment for makeup to PCS tank i

Replace single pump with two higher head pumps Modify piping / valves to provide pump suction from grade level connection to water tankers

  • Backup power to pumps from ancillary diesels ,

e Add piping connection from PCS tank to spent fuel pool for long term makeup in scenarios with no fuel in reactor vessel l Westinghouse i 2ss7, 2 I

,. .j ,.

AP600 PCS Makeup -

. ,i,nnu' .

Current Design m;.m' "'

aesoo 3

. ._.....-. % m>; m ,;--

,.,,' . ..~* " #* * ^ -

PCS MAKEUP  : CURRENT DESIGN cro

.. /FeRE PROT NS v5 f E t.t

]( '

  • [ L, -

1' t  :. -

--.w..~.-~

2'3 B PCS WA TEP S TOR A GE et*------ >- gg TANK *- SAF E tv FIRE PRON, P[ t a TF fi b S YS TE t> /

.._. _ . . e s ai. t (n> CD

= .,

t' ( N qy Of G T

OEuen wN sys tEi e m

E,<-

P F N/ I r I <r .

Li___ ri rJ as" x e, a 1 i,

t- to:  :':

C0t4 T AttJt.'EtJ T

~i' F-4' n

ut ciRcin c reces cHE nic 't PtJe tp cD DIitOli IatJK t ..,-

Westinghouse -

ur, 3

l '::i""It ;

! llP It '

si! i; AP600 PCS SFS Makeup Changes . n

^"8oo PCS , SFS MAKEUP  : . CHANGES '

ED [D A :y / FIRE PROT

-EL , . _

I NS YS TEM .

303 - - - ~ ~ - - - - - - - -~ *

[+

- S AFE i y /DEMiti W k PCS WATER y REL A TED M AKEUp NSYS TE M g g" '

STORAGE Corat4E C itOt4 T At4K FIRE PROT ,

SYSTEM

}

y vg

. _. [D

~

HE A TER H 04 ,,,

T II

\_ _ . ./

1 < - c l 1r it'P l C 1r it

,cx, x. . n n c- t- to: ,' :

Cots T AitauEf 4 T

*1 -

-4

  • l-'4 N 10 r-,

. 7, , nruit at

- Co l-+: ADO 1 Ots i t tik P[ CIRCUL A TIOta N .

PUMPS

] - -- - r = >

('SPE rOEtt si .t.

Westinghouse 2ss7, 4

O

  • 1

.sp uggi..

4. ..

ill!

AP600 PCS Design Changes ^"8oo

- .awwnse.w.*ww_ - __

Passive Containment Cooling Flow Delivery Rates 3 Day versus 7 Day i I  : i l  !

I - l' s

I '

b s

i

' i i i l

I i,

~

as - : - ' ' ,

l l  : .

i i i  ; '

l i l i

i  !

l t

n. I I

e  !

i t i t  ! . l E . i i l  !  !  !  ! l

' l I

5

_l -  ;

7 Day Delivery Flowroces I

l l i 1 o , I I i I l  : -

it i I '

=

me -.

I I  !

' i '

3 PW Delivery Flowestes '

l

+

! I l l l - - ' l i

/ -

- l i

100 -l ' '

, i -

! i , i  ?, * ' '

l

! . l  ! i -

P l.  !

- i '

t  : l i_

. t

. I i . i g to N M 40 SO 90 79 - 90 SS 100 190 120 fM 140 150 180 SFO hE) 5  !

t b

! il8 88till Y. llll ,

AP600 PCS Design Changes ^esoo

~

^iV : :GWF.Yl' _,

rh. y .:-l;;.v gh l

m'T#,..n..,

00necvenienw,ssees.e waseen,a ses:eeEDT1988 t

Contenment Presswo with 7 day PCS Ilow - Preimnery  !

oc23 -

SW ,

A

~

t t

e b

g - N a i h -

i

.4

.. I C3 a a a e Ia e a a Ie a a a Ea a a a Ia a e a !e a a a Ie a e a 1 0 1 2 3 4 5 6 7  !

rnne(dsys)

Westinghouse  !

m7, 6 i 1

' e

. .r

  • AP600 Evaluation of Shield ii lg.i.r :i.ii Building Roof Structural Changes

... ~ . .. , x ;a.; . .. ; a:,,e .: -. .

'e*"'N eso!

g i G" er e-

! sos 3' p,- 4  : ,

i.

(

FPS Tyg

. 4  ! .

e i

l - 4 i A-5:

- K I l

- i at m-ek- l

  • t
n. se-e- 3/ l e

. m >. .- i t E i .

! f

.i .  ;

. I I ,

! i i g

r(2#" ""' .i .i

. I i

'I  ; i 7

j AP600 Shield Building Roof -

q In.iir,ii;j Structural Changes ^esoo

_, ___ m__ .

e Maximum water level in PCS tank increased 5 feet from ,

elevation of 298' to-303'. Top of tank is raised 1 foot resulting in freeboard above maximum water level of 39 inches which is sufficient to prevent water sloshing due to SSE from impacting the underside of the roof.

~

i e Supplemental fire water inventory (18,000 gallons) included in small tank integral with PCS tank roof.This tank is maintained full.

l l

1 i

Westinghouse '

2567p 8 l

l _

l 1 AP600 Shield Building Roof poin .

u Structural Changes , --

^eeoo e PCS tank roof construction revised from 24 inch thick reinforced concrete to 15 inches reinforced c'oncrete on top of 9 inch deep stainless steel fire tank. The fire tank has stainless plates top and bottom plus radial beams. This 1 construction meets SSAR commitment for protection from l tomado missiles and meets SRP guidelines for minimum  ;

thickness.

i t

e Inner wall of tank (chimney side) decreased from 24 inches to 18 inches - this meets SRP guidelines for minimum thickness for tomado missile protection.

Westinghouse I ur, 9 l i

AP600 Evaluation of Shield

.,i noi -

Building Room Structural Changes

^"8oo Current Percent Design Proposed ~ Units increase WEIGHT OFSTRUCTURE ABOVE 9630 9100 kips ELEVATION 260 ',

WEIGHT OF PCS/ FPS WATER 3757 4907 kips TOTAL WEIGHr 13387 14007 kips +4.6 (FULLY EFFECTIVE FOR VERTICAL SEISMIC)

EFFECTIVE HORIZONTAL 1127 1440 kips ,

SEISMIC WEIGHT OF WATER ,

(30%)

)

i TOTAL EFFECTIVE WEIGnr 10757 10540 kips -2.0  ;

FOR HORIZONTAL SEISMIC  !

i Westinghouse I

2567p 10 e

AP600 Evaluation of Shield

~

iiiini 4  :

Building Roof Structural Changes

^"*oo 4 'e For horizontal seismic, mass decreases by 2% for vertical seismic, mass increases by 5%. These changes are small enough that they will have negligible effect on the global seismic analyses of the nuclear island.

e The changes in loads will have small effect on the structural design of the shield building roof. The design calculations for l the shield building roof including the local seismic analyses  !

are being updated. These documents have been reviewed by NRC staff during recent audits of the critical sections. A summary will be provided to NRC showing the effect of the design change. This includes:

Westinghouse 2ss7, 11 j

i AP600 Nvaluation of Shield iini il j Building Roof Structural Changes AP600 i

e 3D finite element analysis of roof used to develop the equivalent stick model used in the global nuclear island seismic analyses  !

e Dynamic sloshing analysis with increased inventory l

e Design calculation of shield building roof i t i  ;

I e Concrete outline and reinforcement drawings e . Seismic margin evaluation of roof structures i Westinghouse u7, 12  :

a-  :

~

lilli""!ijjjj -

ii; illi AP600 Spent Fuel Pool Coohng

,_,c

^esoo

. SECY-96-128, June 12,1996 review based upon previous design-

- SFS should be Seismic I, or

- Pool makeup water source, building, and HVAC should be Seismic I i

  • Additional on site SFP c' ooling capability should be added
  • AP600 should be capable of sustaining design basis events for 7 days without offsite support .

Westinghouse 2567p 13

  • i i

. .- =.

- t girri .

It j

AP600 Spent Fuel Pool Cooling

^"Soo .

~

e AP600 SFS Design Changes j Significantly Enhance Spent Fuel Pool Cooling Capabilities i

l Meets NRC Position on Spent Fuel Pool Cooling in SECY-96-128 Meets SRP and URD Criteria for Full Core Offload as Normal Refueling Practice Westinghouse u7, 14

t 41; ij AP600 S ent Fuel Pool Cooling

^esoo AP600 SPENT FUEL POOL COOLING SYSTEM BI L OPE Cf1 AtlGES

[ .

SPtNT f t41 8'tka I ~" "I # #' E MWE G wi tPOL S v5 fE M AP( W t'C 5 L -t _

r )

5F5 H' ,1

/

Cr5

~

g* m 9., n.

'J 5 IWP Westinghouse aw7, 15

a_

. - t

::- an i Isl -
. 4 sti,l ii AP600 S ent Fuel Pool Cooling ... m yu.e m , q;gggamm.3 g .

= oo s..

semesewme-mwa- '

AP600 SPENT FUEL POOL COOLING SYSTEM i

AF TEP CH ANGES i m.s .. .. i '

5,0.s.GE 1 Nm Y  % I

>- r,< w .

(n.m ,ss.su-e erm- .

--ii d., _Q. . _ _ , , , , t

. . - - =

t ] . . . . . . - l i

t Ct% t as LEJ -

Nk 3 1

vs ~ C,,'- '

(j  !

9 5 Me* t Pt6 Ptw I i crs  !

as L"J  ;

L 4

p

- , LTJ -

,,,,.. (;7 -- - -- -

(y  ;

vs . mn nw i Westinghouse P

2se7, 16 i

l 3

ijjii- lijjjj .

l iit !ill M"1 emf _{

l lCooling ^ "soo e AP600 SFS Design Changes (continued)

=

Cross connections added to normal residual heat removal

~

system (RNS)

~

- RNS can provide 100% of SFP cooling when normal RHR is not in use for RCS

- RNS pressure boundary is Seismic I

= Seismic I makeup water line added from safety-related PCS water storage tank

= Seismic I makeup water line added from cask wash down pit (CWP)

Westinghouse 2567p g j

itil""l 3 ['

[j$1 88[

i! j l

AP600 Spent Fuel Pool Cooling .__

^Psoo .

i i

i

. AP600 SFS Design Changes (continued) i a

Number of safety-related SFP level instruments increased

. from two to three (diverse power divisions)

Seismic I qualified drain lines and isolation valves for fuel i

transfer canal and CWP moved to secure, vital area.  !

=

Level instrument added to cask wash down pit i

" Normal Refueling" redefined as Full Core Offload Calculations demonstrate compliance with SRP and URD ,

requirements for normal refueling with full core offload Westinghouse '

2ssa 18 t i

    • = .

e giriiigg l

AP600 Spent Fuel Pool Cooling

^Peoo l e AP600 SFP Cooling Capabilities J

l

=

1 Seismic I, safety-related passive makeup to SFP available for more than 7 days 1

=

Normal Residual Heat Removal System provides 100%

backup SFP cooling during full core offload and during power operation

=

Seismic I, safety-related makeup path to SFP is available from 'CS tank which is supplied from on-site pumps for post 7 day makeup (post 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> design changes) with water from offsite .

Westinghouse 2567p 3g S e

T

:: i ,

liin 't I -

iii ll l AP600 Passive Spent Fuel Cooling ^"6oo t

i t

t e

ers i*

i. m. i j -

til I

i "a

m r

i

~

. ec l. wc l ,

r

! m  !

i m i. F

-._........._...l1___"____.___.___-

[

s IPEI MIt(188G IK ff MP (EF

( 8 " ' I  ;; m  ;

!  !! t

:: I i  ::  !

i j

J  !

3 k_ m--

r

\/

i x  ;

l _

  1. z  !

,1 \

3

.cits m as - . ve ., u . , a .,%

f; i  !

N. _ _./ u, se e so, VP enscup erm renweeg ad test tw t

Westinghouse -

2567p 20

- - _ - - _ _ _ _ _ . - _ . _ - . _ _ _ _ _ _ _ _ _ - ____-.-_______._-----_______2

'. *f -

i *)

  • l.
PASSIVE SPENT FUEL COOLING CAPABILITIES

} Delga Basis Case:

4 Events .

All DBA (including external) i Basis / Assumptions Safety-related, SSE

[ Timing of Offsite Support After 7 days i

l 4

Water Supplies Ptsel

Thee to Cover 9

~3 Condition 8 F C P Saturation 7 days, Uncover j

Omond FuelIn F T W C h feet Time, days

{. Case (I) SFP R ,C P S (2) (3) (4) f  ! Emergency I core. x. x x x 5.1. 8.3 10.1 i full core @ 150 hr, .

offload 1/3 core ,

i.' ,

e 17 days i *

2 Refueling - I core x x x x. 6.0 8.3 _12.6 4

@ 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />

! 3- Refueling 1/3 core x x x 16.3 2.1 7.7-

O 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> 4
4 Power 1/3 core x x x 22.5 6.4 9.2 l @ 17 days

! 5. Power 1/3 core x x 46.0 12.2 16.3 l @ 4 months

6 Power 1/3 core x 52.4 14.7 18.7 l @ l year i-i ll, Notes: -

l (1) All scenarios assume 10 years of spent fuel. in the pool.

(2) Time after loss of normal cooling when SFP reaches saturation temperature.

i. . .

L (3) Depth of water covering spent fbel after 7 days of loss of normal cooling. Makeup is from on-site i safety-related water supplies as indicated.

j-i (4) Time after loss of normal cooling when spent fbal starts to uncover. Makeup is from safety related water supplies as indicated.

1 r u.

1 1 21 I

il!"~ii .

i i AP600 Spent Fuel Pool Cooling ^Peoo

___m-- .

i e Offsite Release Assessment Off site dose analysis for boiling pool shows compliance with 10CFR20 with no mitigating HVAC filtration or

. , t processing .

  • SRP is met by providing Seismic I, safety-related coolant inventory and makeup water system. HVAC provision of SRP is not applicable (no HVAC filtering is credited for dose mitigation)

Westinghouse 2567p 22

[

I

~

. 1~

p,,rn;l.

4 AP600 Spent Fuel Offsite Doses

~-n- .

nn

^eso:

e Loss Normal Spent Fuel Cooling

=

LPZ dose is 1% of NRC limit, 0.1 rem TEDE (10 CFR 20) i

-No iodine removal in nonsafety HVAC or in l

building j

- All activity assumed to be 1-131

-Boil-off rate based on full core off-load j

-lodine partition factor .01 (same as SGTR) j s

-Conservative atmospheric factors lt j ,

Westinghouse ass 7, 23 i

e t

- l:iIl :- -

1 11133.

II! cjj l AP600 Spent Fuel Offsite Doses -

^"6oo i

e Fuel Drop Accident .

=

Site boundary dose is < 32% of NRC limit,6.25 rem TEDE LPZ dose is less than site boundary dose l - No iodine removal in nonsafety HVAC or in building  !

- All activity assumed to be 1-131

- No boiling during site boundary dose calculation I (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)

- Heatup/ boil-off rate based on full core off-load I

-lodine partition factor .01 (same as SGTR)

- Conservative atmospheric factors Westinghouse  :

u7, N i l

...',.~ .

::n  ::::: -

! !P '

e ' ,'till ni Open Items Resolution ^e8oo

_ _____s ~

q e Changes described today are considered by Westinghouse as resolution for the following Open

. Items: ~

  • # 4170 Spent Fuel Pool Cooling
  • # 1018 Post 72 Hours
  1. 4149 Post 72 Hours
  • # 4163

, Post 72 Hours Westinghouse 2567p 25

  • i

~

AP600 Main Control Room .!ainil,i Habitability _ _ _ _ m,__,s _

^"6oo e MCR is pressurized by MCR Habitability System (VES) l for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i

e Analysis shows that MCR stays within habitability limits by using natural ventilation after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i

Heat loads very low Operator dose remains within 10CFR20 limit (5 rem TEDE) i Westinghouse 2567p I

i

_ _ _ _ _ _ _ _ _ ___.___________._.____.____...._____________________._____._____________.m_____ _ . _ _ _ _ . _ _ _ _ _ _ _ _

AP600  : .

! POST-72-HOURS DESIGN CHANGES i

February 4,1997 TOM HAYES AP600 PLANT ENGINEERING ~

/

Westinghouse m .r-e

. s\.

o AP600 E . .

POST-72-HOURS DESIGN CHANGES '

7 OBJECTIVE: Make design changes to the AP600 design so that the site is capable of sustaining all ,

design basis events with onsite equipment and supplies Replenishment of consumables after 7 days is expected. The equipment required after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> will not be in automatic mode but will be i protectedfrom naturalphenomena.

J I

i Westinghouse l w r-a

.a  !

AP600 k I

~

POST-72-HOURS DESIGN CHANGES CRITERIA: -

The functions required for long term safety of the plant include:

Core cooling and reactivity control Containment cooling and ultimate heat sink-Main control room (MCR) habitability Post-accident monitoring Spent fuel pool cooling

- Equipment and a 7-day supply of consumables is stored onsite.

Provisions for connection of temporary equipment for PCCWST fill and PAMS electrical supply will be retained. Temporary connections provide a back-upfor onsite equipment.

Westinghouse  ;

Ws. 7 3 s%\

AP600  :

POST-72-HOURS DESIGN CHANGES CRITERIA: -

The onsite equipment provided for post-72 (cont.) hours is at least classified as non-seismic, Equipment Class D and is protected from credible natural events. The equipment is analyzed or evaluated to show that it will withstand an SSE and located above the site maximum flood level.

The buildings that contain this equipment are at least classified as AP600 Class D and seismic Category 2. The buildings will be analyzed to show they will withstand an SSE and a 145 mile-per-hour wind.

Westinghouse pa 7 - 4 s%

_ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _._________________.__.__.___.___________.____.___.__m._____ _ . ____ _ _ _ _ _ . _ _ __._ ____._______..__.___ __..__.__ .______

~

AP600 H .

POST-72-HOURS DESIGN CHANGES CRITERIA: .

Control of equipment required for post-72 (cont.) hours is local at the components.

Redundancy is provided for active components.

Separation of redundant components is not required.

The functions provided by this equipment will be tested during plant startup testing.

. The functions provided by this equipment will be covered by Tier I descriptions and ITAACs.

. System level ISTs will be defined to show system operation every 10 years.

Westinghouse sphews.F S .

l

~

AP600  !

POST-72-HOURS DESIGN CHANGES CRITERIA: -

Operating procedures will be provided to (cont.) require this equipment to be available during specified plant operating modes, to operate the equipment on a specified frequency to show that it is available and to return it to operation if it is found to be unavailable.

The equipment provided to perform these functions will be included in the RAP program.

I l

t Westinghouse ,

e. r . s

~

AP600 i- L POST-72-HOURS DESIGN CHANGES FEATURES: -

Two ancillary ac diesel generators provide ac power for PAMS, MCR lights, and pump power. -- PAMS requirements are limited to variables identified as Class 1E in SSAR Table 7.5-1 and requiredfor long term monitoring.

- Passive containment cooling system modified to provide cooling for 7 days with onsite water.

Provisions added for refilling using onsite equipment.

Main control room habitability requirements are met with control room pressurization to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and natural ventilation after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

)

Westinghouse We._ f F s%\

AP600 E .

POST-72-HOURS DESIGN CHANGES FEATURES:

~

Spent fuel pool cooling modified to provide (cont.) makeup from onsite safety-related water sources that are adequate for at least 7 days.

Containment makeup is not required for more than 30 days.

We'stinghouse w . r..

~

AP600

~

.i POST-72-HOURS DESIGN CHANGES

SUMMARY

The proposed AP600 plant design modifications i completely address the NRC staff position which was endorsed by the commission. No equipment is required to be brought to the site and no water or ,

consumable is required for at least 7 days. ,

i 4

Westinghouse O *:

~

AP600 m .

POST-72-HOURS DESIGN CHANGES ANCILLARY AC DIESEL GENERATORS

- Two independent 15 kW units and fuel source located together in annex building.

- Located in south-east corner of annex building. '

New room with large outside door Protectedfrom SSE and 145 mph winds Located above site maximum flood level

- Packaged unit (skid-mount)

Equipment Class D .

Rugged design, will withstand SSE Seismic anchors Westinghouse ,

m_F - 10 .

.O

L lt

t ~!!

'i ; in i <>, "}

je i

b, ~,..

_gp- = 13 E- gli 11! - .

i I l al ,

3 i IT o[ s9,p-i l l: i li lii i l ,i

r. -

m -

3 si

=2% -- <a liLi ili fli n e esi e a '7 o@il g j~j s.

sj '

O m= =

a El ogj. .

3 av -

_ - . l Q $n sw i

4 si m ui  :

Rh. ns - s s-;

i 1 N e

, - . 1x d J

!l - - - - - - I

~ .

AACILLMY FUEL OIL TANK DIESEL GENERATOR 350 GAL DEMINERALIZED 5 POWER PANELS WATER SUPPLY 3'-O'e,7'-O'L

  • i MODULE .

i . . 'S I // '

b /

./ l l  %

. . m

/

'_ . _ _ /__ _ __ _ _- _l'-

_ _ _ O' [j e i l

l 8

g HIGH [ $ ' - l l O

CURB 0

l

'l' l 1 I o I 1, l l bl sl,:

l V - -

. l l

A

__ y ;__________________________________ .. _'l '

, h' IP PE TRENCH '

' l

, w t. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ,

,________ ^ ______a g u -' ~

V .'

l

, [ SERVICE MODULE l

~

HOSE RACK ,a $

, - - - j, -

l l -

. c r e

,1 c i . - -

1 L C'l l i .h -

I

-a m } ,

g . . ,_ . . __ y g r---]

ROLL UPj i

.si .- m DOOR "WY l j  ;>' ' j , 2 DIESEL GENERATOR UNITS i

l j fl -

N., ; =

HATCH l

s 27'WX63'LX40'H l z ..'-.. _x ABOVE E i

~i y

, j _ _.

m ,

' I B 2-6' DWS LINES I-4' CVC LINE 1-l' PGS LINE (H2) a

. .. . .. ..c... . s. _.m.. . m . _,.. ..... . .. .

(

l l

a 1

f

_ r . - -

BORIC ACID i BATCHING TANK

's o CVS MT 02 i

i f x EL 126'-3' l

i i V i

EL 119'-8' I

~

DIESEL GENERATOR UNITS 27'WX63'LX40'H FUEL OILTANK  !

t E L 11

..._..____.1.'_.8..'..

- l'-O' CURB

, , ll , , FL EL 107'-2' i

.u.

. f

. .q l

l 1

l i

== TOTR. PAGE.03 ** ,

o

~

AP600 1 POST-72-HOURS DESIGN CHANGES ANCILLARY AC DIESEL GENERATORS (cont.)

12 Vdc automotive-type starting system with lead-acid battery and float charger -- Charger is Equipment Class E

- Local controls and instruments .

fuel level output voltage, current, frequency (shaft speed) engine temperature and oil pressure starting system voltage

- Exhaust outlet separated from normal building air intakes to allow for diesel testing. -- Exhaust piping requiredfor operation of ancillary generators is protected (seismic, wind, flood).

Westinghouse j we) te

~

AP600 g . ;

POST-72-HOURS DESIGN CHANGES ANCILLARY AC DIESEL GENERATORS (cont.)

Onsite fuel storage 350 gallon capacity tank (4 days @ 50 gallonsiday to meet PAMS and MCR lighting loads + margin for t sludge and testing and protection against overfilling)

  1. 2 diesel fuel -- same as standby power source  ;

Located in same room as ancillary generators Tank, piping, valves will be analyzed to show they will withstand an SSE -

Refill capability Local indication of fuel level Manual normally-closed valves I

westinghouse O

~

AP600 m .

POST-72-HOURS DEMGN CHANGES ANCILLARY AC DIESEL GENERATORS (cont.)

HVAC During normal plant operation air supply is from existing annex building HVAC Normal ventilation exhaust fan to prevent buildup of fumes from fuel During engine operation roll-up door is opened making the room essentially outside -- During cold weather door may be partially opened to retain some heat in room -- Tank heaters are provided to keepfuel warm.

Westinghouse

w. r . ,s
. , t

'l:I , i. j l - .I o_

~

L Ar C y I

/ ns e '"'

4 MH ro r 0c ueA"c" _

nE Qcy _

F M ' A H '" _.

C) _

dy i W0 Tr '

A l /

hrs ,

T _

N z A _

Tm

[ { y L V t o

gw p

I T _

N W4 s

f f a 4 E _

Mr V

n L e _

lL t .

g Cn l

$ e G y Ac D

  • L n

M p A M

Te d -,

P E R S s} $

O Nw A s. f).

_ dDL

- C Mrs L N Es $qp L

8 u

'e o t e gres t pa Arc

/

A-4. -

c' .

1 j

9 o

4 i

k 4

w a .

Uk I% ~

w s~

X k u M

  • wo o + w i

g ' '

~

xm

~h a ,

k f N N ** 4 K

I

%u m

h

~

AP600 .

POST-72-HOURS DESIGN CHANGES ANCILLARY AC DIESEL GENERATORS (cont.)

Fire Protection Ancillary generators and fuel tank are separated from rest of building by a three-hour rated fire barrier.  !

Automatic dry-pipe sprinkler system Hose stations Portable fire extinguishers -

t I

f i

Westinghouse '

w. i . so

. t i

~

AP600 [7 .

~

POST-72-HOURS DESIGN' CHANGES ANCILLARY AC DIESEL GENERATORS (cont.)

Electrical connections Local distribution panel -- one source breaker,four load breakers Permanently installed cables to loads Class IE voltage regulating transformer PCS recirculation pump Fuel tank heater Local lighting .

No provision for parallel operation or cross-connect "Bumpless" transferfor PAMS loads provided by  ;

maintenance bypass switch in Class 1E inverter Westinghouse  !

=

W .7 - 20 sU

i,

'.__----_--_-_--_--_----_____l 7%,pMk AC Gs., emir StI #

1 I l i i AC GottsI*' gf I

g. te ks sto v,0't g l 30,60II'- t I

i I

l l) l I

I 1) ) ) ) l l

v v s i Tsnk team l l 6mes I.,)ht;n) e i i i I

-_-------_- - - _ --.- - - - . --__- s Me m l b Je #

$0 A %f

- -/h ---7 r - - - -- .

I I pp } - )#-

l 1

  1. c. }-----)# l 1

I g

I g Vdbf l N "

7, %.e f

l p- ] I .

I I

(dru l y. tow)tef r I

  • i 4,vv ggag .pr-I l l l L_ I

_ _ _ _// -

s e

4.

E Oe $, ,

N .I.

.g i J 2' "

i l

e

a 8 k i

,I i

i

..h ng' s l

I. si t i k. ,

fI li k 8 p -a fI 9

',L s

i  !

lllM ils P ~ l

! '.T 1 I i4

  • C l

{ l l

i

  • y e * . b

,_'. , % g i

.I 11M .' A

.!(k j ,

~

t ,,,,,,,3 L._.1

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

i s

c- -

r- + r- 7 i II, a ,< >

i i i 4

i IJ i

}' !I u.

f ,s .> u - .

y l L, , p .

Q i I i i'-* g i l . .L -m L'~~

L- +J #f ' - '- ' k'u---E E r h. A. '.N.._.....J

.._..._. ..... .... - y3 ~----_----- - _ . ~ . - - _ (-- 1 h $.s il U i S

O h H

@' - i ,,

0(b.a.g

,4 J

i t._q.;j

.. 'E g..g i ........._,

84 ....4 t..1

  • =*=--*_*_._._...J 4

kN Y Ok

( kl g c ,-

    • k*n l

@ ,_.7, m l@;t,l.,Sl.........

17W -

1 t..1 l

.- 3 .... -

A......_...

p _} .g, ....._._._...

7

  • d  ! 3
  • j f~3' i

l4

-i ,

'- N ,4 ,,_.

Il L. 1 , , ; ij 3 4

! '.:5{...k....._._!

t I8

]

-t+ " -
N i .._._..._ ._. g _._._, j -+ r, i...g'..p'!j .s y--4 it i k a l..... ,

(),p !

- -  : J ,.. . ..._._ ........

l '

r- vi ie I l N  :

il .--

N hl

...........  ! g mi .......... '4,{b 5v ~

3- ; ,

t...q, r

g&

l!h,I.l.._..._._...._)

l l

l R___

~

AP600 E .

POST-72-HOURS DESIGN CHANGES

~

4 PROPOSED SSAR CHANGES Chapter 1 - Revise containment heat removal design basis from 3 days to 7 days.

Revise control room habitability and I&C equipment room environmental control post-72 hours design bases from using temporary equipment to natural circulation of air.

Revise figures 1.2-xx to show plant layout changes.

Add onsite equipment provided for post-72 hour support to s1.9.5.4.

Revise spent fuel pool makeup to include 7-day capability.

Westinghouse w .

r.n s%\ '

~

AP600 o

~

POST-72-HOURS DESIGN CHANGES PROPOSED SSAR CHANGES ,

Chapter 3 - 3.1.l(Criterion 38) - Change "3 days" to "7 days" (2 places).

Tables 3.2-3, 3.9-16, & 3.11 Revise classification of  :

valves and add / delete valves.

~

Figure 3.7.2 Revise PCCWST dimensions. Revise to show doorway change in Waste Monitor Tank Room B.

Table 3.9 Add system level testing to demonstrate system operation every 10 years.

1 Westinghouse mi- a

.s\

~

AP600 -

~

POST-72-HOURS DESIGN CHANGES PROPOSED SSAR CHANGES Chapter 5 - Add spent fuel pool cooling back-up function to normal residual heat removal system.

Revise figure 5.4-7 to show spent fuel pool connections.

Westinghouse We_1 - ts

.w\

.- - . . _ - . - - . - . . - . - - - - . = - . . ..

AP600 -

POST-72-HOURS DESIGN CHANGES PROPOSED SSAR CHANGES  :

Chapter 6 - Add function for PCS to provide makeup water to the spent fuel pool in the event of a prolonged loss of normal spent fuel pool cooling. Add a description of connection from PCCWST to spent fuel pool. 8 Increase PCCWST volume allocated to passive containment cooling. Second recirculation pump added.  :

Revise passive containment cooling flow rates to reflect  ;

7 day profile.

Revise basis for post-72 hours MCR habitability and I&C room environment to natural circulation Add fuel oil storage in annex building to table 6.4-1.

t Westinghouse

AP600 L .

POST-72-HOURS DESIGN CHANGES 1

PROPOSED SSAR CHANGES ,

Chapter 7 - Revise number of spent fuel pool level PAMS instruments from 2 to 3.

Table 7.5-1, Note 1 - Revise from three to four branch flow devices.

i

)

Westinghouse W 9-21

AP600 E .

POST-72-HOURS DESIGN CHANGES PROPOSED SSAR CHANGES Chapter 8 - Add description of ancillary diesel generators.

Revise to show new loading for ancillary diesel generators (i.e., delete requirements for ventilation units, add requirements for passive containment cooling ,

system pumps, tank heaters, and diesel room lights). ,

i Revise figures 8.3.1-3 & 8.3.2-2 to show ancillary diesel generator configuration.

)

Westinghouse gehwwc_F 29

.a

1

~

~

AP600 E' POST-72-HOURS DESIGN CHANGES PROPOSED SSAR CHANGES Chapter 9 - Revise to describe full core off-load as the normal refueling basis heat load and provisions for back-up cooling by the normal residual heat removal system.

Add function for passive containment cooling system to provide makeup water to the spent fuel pool in the event of a. prolonged loss of normal spent fuel pool cooling. Describe new configuration for spent fuel pool cooling.

Add description of HVAC associated with ancillary diesel generator room. .

Westinghouse y-. r . n hh

AP600  : n .

~

POST-72-HOURS DESIGN CHANGES PROPOSED SSAR CHANGES Chapter 9 - Add fire analysis of ancillary diesel generator area and (cont.) fuel storage tank. Add fire area 4035 AF 01 containing ancillary diesel generators and fuel tank.

Add description of fuel supply for ancillary diesel generators.  :

Revise figure 9A-1 to show doorway change in Waste Monitor Tank Room B.

1 Westinghouse W. F - 30

AP600 l

POST-72-HOURS DESIGN CHANGES -

6 PROPOSED SSAR CHANGES Chapter 12- Revise figures to show ancillary diesel generator room and doorway change in Waste Monitor Tank Room B.

Chapter 14- Add tests of ancillary diesel generators and added fluid system functions / connections.

Chapter 15- Opening the control room will be included in the Chapter 15 dose analysis currently being performed.

J Westinghouse mi n

AP600  : .

POST-72-HOURS DESIGN CHANGES .

PROPOSED SSAR CHANGES  !

Chapter 16- Increase Tech Spec required PCCWST storage volume.

Add Tech Spec section for minimum PCCWST level during full core off-load.

Add Tech Spec section for Cask Washdown Pit Water .

Level.

Add the equipment required for post-72 hours to the Reliability Analysis Program.

J l

l Westinghouse m_ r . 3

e AP600 i =

~

POST-72-HOURS DESIGN CHANGES PROPOSED ITAAC CHANGES ,

2.2.2 (PCS) - Add test of PCCWST refill function. ' Add test for spent fuel pool make-up.

2.3.3 (DOS) - Add test for ancillary diesel generator fuel tank.

2.3.6 (RNS) - Add test for spent fuel pool cooling.

2.3.7 (SFS) - Add tests for new RNS cooling and PCCWST refill functions and for new level instruments in SPF and cask washdown pit.

2.6.1 (ECS) - Add ancillary diesel generators.

Westinghouse w.m . , - n u1

e AP600

~

i.

POST-72-HOURS DESIGN CHANGES PROPOSED SCHEDULE 1/30 Submit summary paper to NRC staff for review 2/4 Presentation of design changes to NRC staff 2/11 Receive feedback from NRC staff 2/18 Markups of SS^R text and tables for chapters 1,3,5,6,7, 8,9,12. -

2/28 Next revision of SSAR containing new text, tables and figures for chapters 1,3,5,6,7,8,9,12.

Changes to Chapters 14,15, & 16, and ITAACs will be included in the next scheduled revision for these documents. /

h O

Westinghouse m F 34 A\

Retrieved from "https://kanterella.com/w/index.php?title=ML20134Q143&oldid=2843083"