ML20033H288

Summary of 900329 Meeting W/Util Re Control Room Ventilation Sys & Proposed Improvements to Tech Specs. Handouts Encl

ML20033H288
Person / Time
Site:	Waterford
Issue date:	04/05/1990
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9004190100
Download: ML20033H288 (22)

Text

{{#Wiki_filter:! O

• d April 5,1990 Docket No. 50-382 LICENSEE: Louisiana Power and Light Company FACILITY: Waterford Steam Electric Station, Unit No. 3

SUMMARY

OF MEETING HELD ON MARCH 29, 1990 WITH LOUISIANA POWER AND LIGHT COMPANY TO DISCUSS CONTROL ROOM VENTILATION IMPROVED TECHNICAL SPECIFICATIONS On March 29, 1990, the staff met with the licensee to discuss the Waterford 3 control room ventilation system and the proposed improvements to the technical specifications. The list of meeting attendees is attached as Enclosure 1. The licensee's presentation was made from the viewgraphs attached as Enclosure 2. The improvement effort is to replace the current train oriented technical specifications (TS) with TS that address the required functions in normal, toxic gas, and radiation release conditions. This would allow the licensee to operate the plant so long as the required functions are available, i.e., control room temperature, air filtration, and isolation / pressurization. The way the control room ventilation is designed, these functions may be accomplished by a variety of means which is not addressed by the current version of the Standard or Waterford Technical Specifications. The licensee discussed each of the modes of o)eration and provided responses to the questions that were outstanding from t1e previous NRC questions. These responses will require, however, a revision to the proposed technical specifica-tion which the licensee will provide in the near future. The proposal by Waterford has merit and the improved technicel specifications are expected to include the control room ventilation by function rather than by train. /s/ David L. Wigginton, Project Manager Project Directorate IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures: See next page DISTRIBUTION, C DOCRet Fil W NRC & Local PDR F. Miraglia PD4 Reading F. Hebdon D. Wigginton OGC E. Jordan C. McCracken C. Nichols ACRS(10) J. Rogge, 17G21 0FC IPD4

PbT7P F M....::............:............::............:............::.........

NAME :DW nton:sr:FHeb3bn DAT E : 0 4 />j....... :............ :............ :............ :............ :............ :.... /90

04/5'/90-OFFICIAL RECORD COPY g //)t y

Document Name: WATERFORD TAC 72846 9004190100 900405 (.()(f V' PDR ADOCK 0500038'2 t P FDC ll'

April 5,1990 Docket No. 50 382 LICENSEE: Louisiana Power and Light Company FACILITY: Waterford Steam Electric Station, Unit No. 3

SUMMARY

OF MEETING HELD ON MARCH 29, 1990 WITH LOUIS?ANA POWER AND LIGHT COMPANY TO DISCUSS CONTROL ROOM YENTILATION IMPROVED TECHNICAL SPECIFICATIONS On March 29, 1990, the staff met with the licensee to discuss the Waterford 3 control room ventilation system and the proposed improvements to the technical specifications. The list of meeting attendees is attached as Enclosure 1. The licensee's presentation was made from the viewgraphs attached as Enclosure 2. The improvement effort is to replace the current train oriented technical specifications (TS) with TS that address the required functions in normal, toxic gas, and radiation release conditions. This would allow the licensee to operate the plant so long as the required functions are available, i.e., control room temperature, air filtration, and isolation / pressurization. The way the control room ventilation is designed, these functions may be accomplished by a variety of means which is not addressed by the current version of the Standard or Waterford Technical Specifications. The licensee discussed each of the modes of operation and provided responses to the questions that were outstanding from the )revious NRC questions. These responses will require, however, a revision-to tie proposed technical s)ecifica. tion which the licensee will provide in the near future. The proposal by Waterford has merit and the improved technical specifications are expected to include the control room ventilation by function rather than by train. /s/- David L. Wigginton, Project Manager Project Directorate IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures: See next page DISTRIBUTION Docket Fl W NRC & Local PDR F. Miraglia PD4 Reading F. Hebdon D. Wigginton OGC E. Jordan C. McCracken C. Nichols ACRS(10) J. Rogge, 17G21 g.. g ,p 7_.......___....... ____= ......:....p i AME :DW nton:sr:FHeb n AT E : 0 4 />j....... :............ :............ :............ :............ :............ :......... 4 /90

04/$/90 i

OFFICIAL RECORD COPY Document Name: WATERFORD TAC 72846 l

l p rao UNITED STATES i 8" NUCLEAR REGULATORY COMMISSION i ~ o WASHINGTON, D. C. 20565

• April 5, 1990 Docket No. 50-382 i

LICENSEE: Louisiana Power and Light Company FACILITY: Waterford Steam Electric Station, Unit No. 3

SUBJECT:

SUtmARY OF MEETING HELD ON MARCH 29, 1990 WITH LOUISIANA POWER AND LIGHT COMPANY TO DISCUSS CONTROL ROOM VENTILATION IMPROVED TECHNICAL SPECIFICATIONS On March 29, 1990 the staff met with the licensee to discuss the Waterford 3 control room ventilation. system and the proposed improvements to the technical specifications. The list of meeting attendees is attached as Enclosure 1. l The licensee's presentation was made from the viewgraphs attached as Enclosure 2. The improvement effort is to replace the current train oriented technical specifications (TS) with TS that address the required functions in nornal, toxic gas, and radiation release conditions. This would allow the licensee to operate the plant so long as the required functions are available, i.e., control room temperature, air filtration, and isolation / pressurization. The way. the control room ventilation is designed, these functions may be accomplished by a variety of means which is not addressed by the current version of the Standard or Waterford Technical Specifications. l The licensee discussed each of the modes of operation and provided responses to the questions that were outstanding from the arevious. NRC questions. These responses will require, however, a revision to t1e proposed technical specifica-l l tion which the licensee will provide in the near future. The proposal by Waterford has merit and the improved technical specifications are expected to include the control room ventilation by function.rather than by train. David L. Wigg nton, Project Manager Project Directorate IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation l

Enclosures:

As stated cc w/ enclosures: See next page l

Mr. Jerrold G. Dewease Waterford 3 Louisiana Power & Light Company CC: W. Nalcolm Stevenson, Esq. Regional Administrator, Region IV Monroe & Leman U.S. Nuclear Regulatory Commission 201 St. Charles Avenue, Suite 3300 Office of Executive Director for New Orleans, Louisiana 70170-3300 Operations 611 Ryan Plaza Drive, Suite 1000 Mr. E. Blake Arlington, Texas 76011 Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Mr. William H. Spell, Administrator Washington, D.C. 20037 Nuclear Energy Division Department of Environmental Quality Pesident Inspector /Waterford NPS Post Office Box 14690 Pest Office Eox 822 Baton Rouge, Louisiara 70898 Killona, Louisiana 70066 Mr. Ralph T. Lally President, Police Jury Manager of Quality Assurance St. Charles Parish Middle South Services, Inc. Hahnville, Louisiana 70057 Post Office Box 61000 New Orleans, Louisiana 70161 Chairman William A. Cross Louisiana Fublic Service Commission Bethesda Licensing Office One American Place, Suite 1630 3 Metro Center Baton Rouge, Louisiana 70825-1697 Suite 610 Bethesda, Maryland 20814 Mr. R. F. Burski Nuclear Safety and Regulatory Affairs Manager Louisiana Power & Light Company 317 Baronne Street New Orleans, Louisiana 70112 l i l \\ l I i

t I Control Room Ventilation Meeting March 26_1990 ~~~ Name gganization D. Wigginton NRR/PDIY .C. McCracken. 'NRR/SPLB Charles R. Nichols NRR/SPLB Robert S. Starkey LP&L/Waterford 3 Larry W. Laughlin LP&L/Waterford 3 Bruce B. Kennedy LP&L/Waterford 3 . 9 r e R 4 I -m v e e ,sy&

.). j AGENDA E e SYSTEM DESIGN AND CONFIGURATION BRUCE KENNEDY e PROPOSED TECH SPEC CHANGE. LARRY LAUGHLIN r o QUESTIONS AND ANSWERS ROBERT.STARKEY BRUCE KENNEDY LARRY LAUGHLIN e D v 9 o o + 9 e 4 b k ,m.,. - -. ,.y

1..

l i CONTROL ROOM VENTALATION PRESENTATION t t i Prepared By .A4LA DYtAtL& $~'S$~?0 B.B. Kennedy, System Eng! Mg - Electrical, Reviewed By /c $-/7-ve Mlleg, Site Licensing Support Supervisor / / / .\\ . f' 1. Approved By d J/M /70 T.H. Smith 7 Plant Engineering Superintendent 1 l 5 t a g 1 'e l

l' rLPeL 1

F "" ( N b4) As achaSLite& Wef(mt4 aa ese g,gg,esje unset S g 5 naw4 t, { \\ \\. rje r \\ \\ i ' '[* ' l uag y"-IA"32ndhe e l p)w. naw - ' -{Nj gg, J .l /.~.?!% - " rL-wwm;wm n 't M W:mtanetS'N 7_4,EgM"AWYM'g' g>. = s'JeM49%+ ,l s fs c, r.w w a . &,y o g',y.T '- d esa ..re f. "T'gsmam*' @ r e n s,. t i I s. .si <., a k W ee 'g m _ ~.g Rti",7C'" q il }1

yws, 1,o[y.}a 3 l..

y.,,,,,v 1

< c.='m. r a-1; n,, ,.y r { .i_.. t $^y -~ j j! ',oc'4 g'gg$ 2E. $~-== w g 1 A r i !l F o k;N e ! ' I'h[.d, ~IT ~ ,,,,g I l F 'g 5IS5 * { c.. i. 1 .--- e rooo= n,gz==== / =I N. c, met... = * *

• l j.

y gg'"** c c.: e

l 7

.- g,, - i .b, >'"'.I.f."N.'e, inA = ~ ~ ' D .sss._ c- '-a c,., ..I!" ' "3 ! i 1 . y. x

== i ~ ,l k '". "M t" T

==*** J II s an AMe'!!","iif%,.,. t" I IIIER g:e if T0 J t w = asa u u'I@ x.seU !I l e t =t!"a"">'"ffs.h Basse:at = se [ M * #* t r: i _A 8 " " * ~ r, 1, p i

1. 4SM,,,,, -

g p N u

! 4 m$ _ S. d4 >b 7,!N. r--5 a e m.! = Al ir-!! !! :! po E u il eT. b.r Au u6a v L p X ta 1 1

H Q v_

ft g 4 a g j To, ut ~ k

• I)I

'1[! b_b !* ] E , 4.,,. 4..ry"~'.*lP " 1. i,* ,mj'aiW6.,:. .i a _. m ,,... t -c6 era,t neem 14.4180' et asao' k

h, o c.,. jn l4l 4 4 .e, i iinninnui l IIJHiD JHiD JH!D JH!D innunni .I i i 1: l .L m m l, i "j"] i+3-- % " g - 3 i an i i; .g g g g m, inninunit sinn nnn 1 j q ll N N A5 i . !!, b d ! III h h .i ic l $s4M i ,i_ ,u, l11! 110 i !i!; !! + ! !l i'l ! M" = ff, t 9, t !!ilI f,i8$ H, b !!I I';ll l et i I e i'l i i'l I j,ji l l 5g ja, l ,-Q .I 1 I e I i l - ~1-I

• I l

9 fgi _ _ L" i _t. _ i __J pn 3 _ _ _ /_ _ _ _ _+4 I l L 9%_I ! II,! D I I A ____i____ _r _,,g g- _7 C Tx l \\-t +h>I-2$6l9),4 11 l Ii j l _ _ _ _ _ _ _ _ _ _ _ _ P_ t* I,', i F-F -,- mI ' ' ' I wi ,i

T ei 3

I

• Ils I

sh;w s m .-.,,.,.m ,+m,- .c 3 7, 2 .. w.

1 t a o u o - p l I! k I l@l@ l@l@ " gg i l)y l 'I i J.gg i: 1 2 l [d3$)b f Illlli Illill 11llll1H1llll l l l 3 l = NI A ll i m n m i:i l __.L

ljE,

-;l If' 6 L3 t i w, o m j yyi..g, i i n il, ~y v j aa als i l,(,. l,(.s l i~ im i a o !!O.g 4.[%$ l i!n I!nm l 1 l J A a o c !,1!. ~ 33o$,3 d $4. *$5rv, ",4 iP

3. y,, -

v gl - ;x \\. irl1 !.i,l p.i i !p i FIEe a 2 i s i

• r o 3l! i l

-l l !3 I E g =? I t li i i en o 4 I $ ;s % ' 4 i_ '_ __, _f -r f B d I I l i i i i 9o "_OI i i iF43 i HII YI III lt o _ 7_(L _ _ /- -- - - - ---l- - -- r-C q _x l \\-r I-le,d ;, 8 i q 4; l ll s i . _ _ _ ___J sc l fI I l, os en g S _Ig ___, b s H l I i i ,-.-.,,e-w .____________--___,.-__--v__,a-__

i...

N isl 1i l i:Ml i.;l.h m m.h e'dp i .s ei o,oo,li 1p-Ha :+s jeHE r=

iooooo,

,uo 1 5: 1 I gg N NI is -l i e e k i-I i+$ pr+T 1 i l'namj insninil iinninni l lyd i I i 3 1C I:Q,j!. N INI l X-g Ab aA i ce '!~ 'li! I! o, l I! EE}DE _ l it ; it c Ra. f *n B 1 4 @e $ 4 llil %3 lEa c r$ r fqgg>g s 6 !ll .mg 2 s l! I g I l 5.l w6 5 ni i alg jag i !p.i l -w i..g -i ~ i iil= et b E*g #

• g i

l(il l g -l l 53 l

==2 i ij' $$a52 s Edim _b T lo i o i i i i i

• DI i t41 1

__7_gt.__/_____dl1_ _ _ _ _ _ _ _i> a nii Eo g* L r,- l s -r' l3.i4&+ra q-lx, Ng 4

i i

l l s ___ _____J m: L-i g % I vDI i j. gi gl !. m: W___ _ _ _ _ _ _ _ _ _ _J,2_ __ i 'li l i'W4llf I I

c. a.,,.

J 1.: 1g---- ~ L SAFETY-REl.ATED 1 peg ng333 PE-5-004 4 l-PW EECT205. EE713105 1 l t Field Copy h I.I~i t l l This POcument #11 no ic@Qa cascogoQ aiter this$ ate.L,..,_. _. t.. & / l i .......-~ce.-.- Control Roca Air conditioning Systasa Surveillance:(Rev.4) 1 e h L URCONTROLLED L C..O P Y L. l 4 l-name v u i, s..- D ter $G9$& -T L /

• • • bO **h) m 4

i ~ f. ,u.e.... m _1... t 122astll,Te Data 4 Al i \\ i i f 1 1/ I art-t-co2 a,tste to 23.3 (1 at-p 4/gE' E f Ji I ________.__________,,_.____._._.__.-........_,...__,._,..__..,,..,_.2,...__,,

. t ~ Survaillcnca Preceduro -PE-5-004 I[ C:n't'rol Rcos Air Ccnditioning. R2 vision.4 o .-,~' - System Surveillance 7.r. PRETEST VISUAL INSPECTION Results of_the' pretest visual inspection are satisfactory. Any i deficiencies: observed have been recorded and corrective action identified. Each deficiency and corrective action has been evaluated for its effect on further tests and test.results. Verified by 1 Signature Date 7.2 LABORATORY TESTING OF ADSORBENT Within 31 days of removal, a laboratory analysis of a representative sample,-obtained in accordance with Regulatory. Position C.6.b of Regulatory Guide 1.52 Rev. 2, March 1978, meets the laboratory testing critieria' of Regulatory Position.C.6 of Regulatory Guide i 1.52, Rev. 2,~ March 1978. Verified by l Signature Date 7.3 T0XIC GAS TEST SIGNAL RESPONSE i A toxic gas test signal automatically switches system operation to an isolation mode. Verified by Signature Date 7.4 HIGH' RADIATION TEST SIGNAL RESPONSE A high radiation test signal automatically switches system operation t to a recirculation mode with flow through'the-emergency filtration 1 system. i Verified by Signature Date ~ a 6 e-

1;

= J Surveillance Procedure-PE-5-004 =* Control Room Air Conditioning Revision 4-System Surveillance r 7.5 CONTROL' ROOM PRESSURE VERIFICATION

• The Control Room Air Conditioning System maintains the Control Room 2

at a! positive pressure of greater than or equalfto 0.125 INWG relative to the outside atmosphere when operating,in recirculation j mode.with an emergency outside air intake open. . Verified by. Signature _..Date 7.6 AIRFLOW CAPACITY AND HEPA/HECA DP CHECK + 7.6.1~ Emergency Filtration System' airflow rate is 4225 acfm *10% .when the CRACS is operating in recirculation mode. Verified by Signature l Date 7.6.2 With Emergency Filtratton System-flow at 4225 acfm 10%, the pressure drop across the combined HEPA filters and HECA bed is less than 7.8 INWG. Verified by Signature-Date 7.7 IN-PLACE LEAK TEST - HEPA FILTERS-With an emergency filtration unit flow ra'te of 4225 acfm *10%, each HEPA filter bank removes greater than or equal'to 99.95% of the DOP-when tested in accordance with ANSI NS10-1975. Verified by Signature Date' l.

q .a Surveillance Procedure - PE-5-004 i Control Room Air Conditioning Revision 4 System Surveillance 9 i h 7.8 IN-PLACE - LEAK TEST, ADSORBER - .7.8.1 With an emergency filtration unit flow rate.at 4225 acfm *10% .the HECA bank removes greater than or equal to 99.95% of the halide test gas when tested in accordance with ANSI.N510-1975. Verified by .j -Signature-Date 'i 7.9' HEATER PERFORMANCE TEST Each emergency filtration heater dissipates 10 +0.5..-1.0 kw when tested in accordance'with~ ANSI N510-1975. Verified-by. Signature..Date f' T W 4 1 4 s v b 4

q.. d [ HVC 202A HVC 201A HVC-102 -HYC-101 Y' ,Y V-14 NORMAL QUTSIDE d/ '( h( h( - AIA: INTAKE r HVg:1028 Hg g018 M M HV6 7028 HVI IC18 P ~""~~~~~""~~"" ' r' l- . 'y-4 F 'y-3 ^ lk 040(SA) i 'HVPd.04A HVC 203A HVC-103A M V-8 M V-5 lHAWW 39,230 C.F.) l =,_ w /H-4/HH UL, - E g-!- HV,C,-1048 HY M 038 l $HVC-~ = Y i M M l"H" 105A ' E CC CC AH-12. GO-11 HVCIIO48HVC]O38 l D"ff'(SA)- (3A-5A) (SA): /, MVC-1038 7, g ' _V-8 V-7 040j,58,,) r f EMERGENCY OUTSIDE l,,M 49P E W E l l v AIR INTAKES i.g lllllll l1 l HVC-10581 ~ CC HC AH 12 = GO-11 041(SA) H ($gI. H 039(58) '(38-58) l[HVC -213A _3800.C F.M. CONTROL RM. AH UNIT 5' m 017,$,2,05A HV p

=e

e = g l i (SA) g E l lI f! l, r , l,l gi, c m-l' i l 4000 C.F.M S = f G0-12

t 5-8(3A-SA)

(SA) m I GO-12(58) 017(58) H E Y = l hl ( j ~ = I( l G HVC-2058 $ H 5-8(38-58) 4000 C.F.M. .HVC-2138 I' -H 041(58L EMERGENCY FILTRATION UNITS l .-.n.

. J'.. .a e a .-4e OVERVIEW: e -DESIGN ~ FUNCTION. e SURVEILLANCE PROGRAM TESTS FUNCTIONS L 3 e HoWEVER, TECH SPEC WRITTEN AS IF:ONE. FUNCTION 9 l-i. I i [ \\ 0 e w 4* A h 4 8 '.I a i ~ ~

/,h[' ' ' _ ':( [' e b e e

DEVELOP TECH SPECS WHICH ARE CONSISTENT WITH DESIGN FUNCTION.AND TESTING F

r O u e e D e 5 4 e I - f a

g i.. + 't .s[ SYSTEM FUNCTIONS l Je . MAINTAIN CONTROL ROOM TEMPERATURE 'e AIR FILTRATION-e ISOLATION AND PRESSURIZATION i 'l l T. e e l . 3 w. e l l l .g4 i -l i -i i 1 4 1 1

. a.; .c AIR FILTRATION l d L I I 'O MODES 1, 2,-3 AND'4'- TWO TRAINS OPERABLE l L: ACTIONS: A. ONE TRAIN INOPERABLE: ' RESTORE WITHIN 7? DAYS OR L INITIATE PLANT SHUTDOWN B.- TWO TRAINS INOPERABLE:- RESTORE ONE TRAIN OR INITIATE PLANT SHUTDOWN [ SURVEILLANCES: SIMILAR'TO-PRESENT TECH SPEC s 9 MODES 5 AND 6 - ONE TRAIN OPERABLE ACTION: SUSPEND CORE ALTERATIONS OR POSITIVE. REACTIVITY. CHANGES . SURVEILLA,NCES: SAME'AS ABOVE L r i e b? i a 4 v 4 n. ,w5- -s. ~

r ].'.. AIR TEMPERATURE e TWO CONTROL ROOM AIR CONDITIONING UNITS SHALL BE OPERABLE ALL MODES - ACTIONS': A. ONE UNIT INOPERABLE AND-T s 80*F RESTORE ONIT WITHIN 30 DA'YS OR INITIATE PLANT SHUTDOWN l B. ONE' UNIT INOPERABLE AND T > 80*F-RESTORE-UNIT WITHIN 7 DAYS OR l INITIATE PLANT SHUTDOWN C. TWO UNITS INOPERABLE DUE TO LOSS OF j COOLING CAPABILITY RESTORE ONE UNIT WITHIN 3 DAYS OR q INITIATE PLANT SHUTDOWN D. TWO UNITS. INOPERABLE DUE TO LOSS OF AIR CIRCULATION CAPABILITY SEE SPECIFICATIONS 3 3.7.6.1 OR 3./ 6.2. 1 1 -l j 2 i [ a j i t /' j 9 i g y g. g m - w e'w w -ye-vy ae F s

~' 3, I' ISOLATION AND PRESSURIZATION ISOLATION AND PRESSURIZATION BOUNDARIES SHALL BE 9 OPERABLE - ALL MODES i ACTIONS: A.. EITHER ISOLATION VALVE IN NORMAL OUTSIDE l AIR FLOW PATH INOPERABLE y RESTORE THE OPERABLE WITHIN 7 DAYS OR ISOLATE AFFECTED FLOW PATH .B. BOTH ISOLATION VALVES IN NORMAL OUTSIDE AIR FLOW PATH INOPERABLE 'l ISOLATE'AFFECTED FLOW PATH WITHIN l ~ HOUR' I C. AN EMERGENCY FILTER UNIT OUTSIDE AIR INTAKE VALVE (S) INOPERABLE RESTORE TO OPERABLE 1WITHIN 7 DAYS OR ISOLATE AFFECTED FLOW PATH D. MAINTAIN; CONTROL ROOM. ENVELOPE AT A POSITIVE PRESSURE OF GREATER THAN OR EQUAL TO 1/8' INCH W.G. DURING HIGH-RADIATION l MODE / IMMEDIATELY RESTORE CONTROL ROOM ENVELOP,E BOUNDARIES j 0 s 1 !}}