ML20091K568

From kanterella
Jump to navigation Jump to search

Electrical,Instrumentation & Control Design Aspect of Proposed License Amend Rev 1 for Single Loop Operation of Duane Arnold Energy Ctr,Unit 1, Technical Evaluation Rept
ML20091K568
Person / Time
Site: 05000000, Duane Arnold
Issue date: 11/30/1983
From: Donich T, White R
Lawrence Livermore National Lab (LLNL)
To: Dunesia Clark
Office of Nuclear Reactor Regulation
Shared Package
ML17139C189 List:
References
CON-FIN-A-0250, FOIA-84-105, TAC 43126 NUDOCS 8406070138
Download: ML20091K568 (14)
v • d • e


Text

q Lawrence Livermore National Labora@ tory r_u g., )

3 r

(

r.

y, e.

"Y INTERIM REPORT MRC TAC No(S),

43126 REPcRT No, UCID-:cccc CChTRACT PRCGPat CR TF.cJECT TITLE:

Selected Operating Reac:or Issues II SU3 JECT CF TrilS ECCUMENT:

Technical Evaluation Report on the Electrical, Instru=entation, and Control Design Aspects of the Proposed License A=end=ent Revision 1 for Single-Loop Operation of the Duane Arnold Energy Center, Uni: 1

'l v. 2.n.C.n.T.- a.n.xi !. sCo.v. -

Informal Report Aur.<CR(s):

Terry R. Donich/ Robert Mtite n a n Ct N vrs,

ura -

uC.

n.

Nove=ber 30, 1983 RESFCNSIELE NRC DOIVIEUAL A?O NRC CF: ICE CR DIVISICN:

Dick Clark, Division of Licensing 2'his i :. car.t cas prepared pri:~.cri".y for preif. :ir. cry or ir.ts.w.:'. use.

_Tt hca r.:t receivei fu ~. rev*cu ~.d ::: :v:2.

Sir.ca charg may bg 3:;bs ar.gi.;g S.crfes, this i:c:cer.t shcuid r.ct We ccr.aidsred fir. i.

Prepared for the U.S. Nuclear Regula:ory Cen=ission k~ ashing ca, D.C.

Under DOE Centract No. 3&R201910ll NRC IIN No. A0230 8406070138 840319 PDR FOIA BELL 84-105 PDR GlWers.t'/ :! CB I? r*!3

{h{.'*j f}Qh} LJ wit?C 9 Ly t"~;:0.*e'2.'Ct*3l LJ: crit:ty ei3.EctJ$ vere:;ry. hewa:a 33:23 im

-~ 1, *. TECHNICAL EVALUATION REFORT ON TF.E ELECTRICAL, INSTRQ2NTATION, AND CONTROL DESIGN AS?ICTS OF THE FROPOSED LICENSE AMENDMENT REVISION 1 FOR SINGLI-LOOP ??ERATION CF TEE DUANE ARNOLD ENERGY CENTER, UNIT 1 (Docket No. 50-331) Terry R. Donich - Lawrence Liver = ora National Laboratory Nuclear Systems Safety Progras Novesber 30, 1983 FIN A-0250 Responsible'NRO Individual and Division Dick Clark Division'of Licensing aA

l( _ A2STRACT This report docu ents the technical evalustien of the proposed ' changes to the plant reactor protection syste= by the licanaee of Duane Arnold Energy Center, Unit 1 to account for single-loop plant operation. This _ evaluation ir, restricted to only the electrical, instrumentation, and contrcl desiZn aspects of proposed changes to the plant technical speci-fications for single-loop operation beyond 24 hours. The conclusion of the evaluation is that the Duane Arnold license acend:ent for single-loop operation has set the review crite::ia provided anc:alous control roo= indications are corrected or warning-tagged for the duration of single- - loop operation. FORZb'ORD This report is supplied-as part of the Selected Operating Reactor Issues Progran II being conducted for the U. S. Nuclear Regulatory Co==ission, Office of Nuclear Reactor Regulation, Division of Licensing, by Lawrence Livernore National Laboratory. The U. S. Nuclear Regulatory Co==ission funded'the work under the classification entitled " Selected-Operating Reactor Issues Program II, B&R 20 19 10 11 1, FIN No. A-0250. I t 6 m iL_s,_ "._~

I TA3LI 0F CO:.TI'CS 1 Paga 1. INTRODUCTICS. 1 2. IVALUATION.CD RICClOE: CATIONS 2 3. CONCLUSIONS 3 RIFIRINCIS. 4 -111-IL:-

4 TECHNICAL EVALi'ATION RE?CRT ON N TtT m ' CAL, INSTRDSNTATION, A'iD CC TROL DESIGN AS?ECTS C? THE PROPOSED LICENSE.UENEMENT REVISICN-1 FOR SINGLE-LCCP OPERATION CF THE DUANE ARNOLD ENERGY CINTER, UNIT 1 (Docket 5a. 50-331) Terry R. Donich. 'c '- - Lawrence Liver = ore National Laboratory; - - ~, 1. INTRODUCTION 3y letter to the U. S. Nuclear Regulatory Co "fssion (NRC) dated June 24, 1983 [Ref. 1], the Iowa Electric Light and Power Co=pany sub=1::ed infor=ation to support its proposed license a=end=ent to operate the Duane Arnold Energy Center, Unit 1 (DAIC-1) with one recirculation loop out of service (i.e., single-loop operation). This request supercedes all other-sub=ittals. This infor=ation included the-licensee's analysis of significant events, which were based on a review of accidents and sbnor=al operational ~ transients associated with power operations in the single-loop = ode provided by General Electric Co=pany, Nuclear Energy Division (GE-NED), the nuclear stea: ' supply syste= designer. Conservative assu=ptions were e= ployed, as discussed in the GE-NED report NED0-24272 dated July, 1980 [Ref. 2], :o ensure that the generic analyses for boiling water reactors (37R 3 and/or 4) were applicable to :he DAEC-1. In response to a= NRC request,- the licensee provided supple = ental infor=ation in conference calls of Septa =ber 13, 1983 - [Ref. 3] and Septe=ber 19, 1983 [Ref. 4]. A letter to NRC docu=en:ing :he conference calls was da:cd October 11, 1983 [Ref. 3]. The purpose of this :eport is to docu=ent the evaluation of the electrical, instru=entation, and control (EI&C) design aspec:s of the proposed license a=end=ent change to the DAEC-1 technical specifications. The consider-ation of p:oper plant variables, co=pu:er =odels, and the licensee's conclu-sions on core perfor=ance and clad te=perature are outside :he scope of this evaluation. 3 This review was-conducted using ICCFR30, Appendix A, " General Design Criteria for Nuclear Power Plants" (G.D.C. 20 through 24) [Ref. 6] and IIIE Standard 279-1971 [Ref. 7].with the following' guidance fres the NRC staff for the application of Section 4.13, =ultiple 'se: points, of the IEEE Standard: - Manual switching :o the = ore. restrictive se: point for the A?RMs in the reae:or protec:ica systes is accep:able for SWRs if sufficient adminis::a:ive controls exis: :o assure :ha: :he = ore res:rie:ive seepoin:s are in effec: when : squired by :he plan: Technical Speci- ~ fications. The NRC has defined sufficient ad=inistrative centrols as: 1. There is to be an independent check of the gain or se: point adjust =ent. ~ 2. The check is to be vi:hin the next shift. J 3. Checks are by appropria:e technical individuals (e.g., shift supervisor or SRO). The adjust ents to the reactor protection syste: for single-loop cperation (i.e., SCRAM trip setpoint adjus =ents or A?RM gain adjust =ents) =ust be_within and therefore satisfy the functional require ents of the reactor protection syste. 2. EVALUATION AND RECOMMENDATIONS ~ ..1 2 M.: os.'. w ( .s~ -;,_.g.-_._ The current DAEC-1 Technical Specifications do not per=it single-loop plant operation at reduced power for core than 24 hours. The licensee's propesed technical specification change: would allcw the reactor. to operate at reduced power, not greater than 50%, with one recirculation loop inoperable for more than -24 hours if certain changes are =ade to the reactor protection systems. These changes are to the Average Power Range Monitor (A?RM) SCRAM trip setpoint and the Rod Block Monitor (R3M) rod block setpoint or to the A2RM gain. A different flow pattern is es:ablished in the vessel during single-recirculation-loop operation as co= pared to the norcal two-loop operatica (Ref. 2]. In single-loop operation, there is backflow through the je: pe=ps in the idle loop. The jet-pu=p core flow reasure:ent syste: 10 calibrated only when both loops are in operation and all jet pu=ps are in forward flow. - The total' core flow is the su= of the =easured ja: pump flows. In single-loop operation,'the =easured flow in the backflowing jet pu=ps =us: be sub-tracted fro: the flow through the other jet pu=ps. Also, the je: pu=p flow coefficient is' different ftr reverse ficw than for. forward flow in :he je: i pu=ps. .--~ Because of the different f'.ow rate and flow path during single-recirculation-loop: operation, the A?lM SCRAM trip _ settings, which are flow-i biased according to.the equation'in the proposed technical. specifications, require reset:ing to protect the re.-::or fro =. overpower. The rod block se. - j - poinc equation is flow-biased-in ths sa:e way and with the same flow signal l

as the A?RM se
point, and us: also

- =cdified: o provide - adequate core protec: ion-for a.postula:ed rod. withdrawal error.- This change is effectively - acconplished by ac A?RM gain adjust =ent. S O E g y y-n w r* 7 m v =

6 [ i The =anual A?RM gain adjustment to acce==odata single-loep operation is the only change i= posed upon the DAIC-1 reactor pro:ection systen (R?S). This codification adds the tera 0.66 W :o _:he APRM readings to co=pensa:e for backflow through: the jet pumps of the idle loop. This change will not cause the RPS to violate General Design Cri:eria 20 to 24 of ICC?Rf0 Appendix A. The licensee provided in a letter dated Octcher 11, 1983 (Ref. 3] the l ad=inistrative controls to be used to assure that the gain adjus::ents are per-for=ed correctly. The Duane Arnold staff will write a procedure which imple ents the requirements of the proposed single-loop operation. The =ul:1ple SCRAM trip se: points will not be used to adjus: the reactor protection sys:en for single-loop operation. Instead, the A?RM SCRAM and rod block settings will be effec-tively reset by the A?RM gain adjust =ents. These gain adjust:ents for starting single-loop operation will be performed by the licensed reactor operator. A second reactor operator will independently review the settings as an adainistra-tive control. The Senior Reactor Operator and the Shif t Technical Advisor will review the docunentation. This =eets'the NRC definition for sufficient ad=in-istrative controls. c. - %ga,c3 ;;;;, u_.,,..,.;_.,. .,,.p.,gg-3. CONCLUSIONS ~ - Based on our. review of the infor:ation and docu=ents provided b'y the licensee in References 1 and 5, we conclude that the A?RM gain adjust =ents for 1 sin 3 e-loop operation will satisfy the functional require =ents of the reactor, i protection systen. .n i The manual A?RM gain adjust =ent settings to acco==odate single-loop. coeration is the only change i= posed upon the Duane Arnold Energy Center, Unit i reactor protection systen (R?$) instru enta: ion. This change.uill not cause the R?S ins:rumentation syste= to violate ICC7R30 Appendix A General Design Criteria f 20 through 24 (Ref. 6] or IEEI 279-1971 [Ref. 7] with the exception of the IEEE standard as discussed below.~ 3ecause of backflow through the jet pu=ps in the idle loop during single-recircula:icn-loop operation, indications in the control roos of ind!vi-i dual je: pu=p flow and total su=ned core flow will be =isleading. We-recce=end j that these ano=alous control roon indications be corrected or warning-tagged for the duration of the single-recirculation-loop operation, as required by Section 4.20 of IIII Standard 279-1971 [Ref. 7]. s rirt The adsinistrative conrrels to be used by the licenses to assure the A?RM gain adjust =ents are performed correctly =ee: the NRC criteria for suffi-cien: ad=inistrative controls. t-3 ~ We recc==end to the NRC, that upon implementation cf the above recen=endsd actions, the proposed electrical, ins:runenta: ion, and cen:rol design aspects of the proposed license acend ent for single-recircula: ion-loop operation at Duane Arnold Energy Center, Uni: 1 he found accep;able. REFERENCES -...,3~-.~. 3...-,. ,y ., s .,,3

  • r.,
1. -

Iowa Electric Light and Power Cospany let er (Richard McGaugh) to NRC ~ (Harold Denten), " Single Recirculation Loop Operation," dated June 24, 1983.

2.,

General Electric Company, Nuclear Power Syste=s Division, "Duane Arnold Energy Center Single-Loop Operation," NEDO 24272, July, 1980 - 3. Telephoneconferencecall(JackDonohew);IELPC(Tony 3howning);LLNL (Terry Donich), September 15, 1983. 4. . Telephone conference call (Jack Donohew); IILPC (Tony 3rowning); LLNL (Terry Donich), September 19, 1983. 5. Iowa Electric Light and Po er Co=pany letter (Richard W. McGaughy) to NRC (Harold Denton) HG-83-3374, "Addi:ional Infor=ation on Single-Loop Operation," October 11, 1983. 6. Code of Federal Regulations, Title 10, Part 50, Apendix A, " General Design Criteria for Nuclea: Power Plants," 1981. 7. IEEE Standard 279-1971, " Criteria for Protection Systens for Nuclear ?cwer LGenerating S:ations," dated 1971. + 1 1 4

..,.,,,..,i.. -... ..I.. e. ...u.-: .. e

* ;. t N.. L.,.,
1. 5 J 1...
  • 1.

.. 6 t y:t, . i.8 '.,s. e.. v 6 '.', 2 L. i. ;,. 3 C.- ,.. w v. ..,,,s,,..i ..,,,r ...,.w.., 6 .s.7.,.,, i. ,,s.s .,._..;.-; a .e 0s.- ..s.

t. 3

... J.,./..v s...

  • m

.s* . u .n 1. 'J n ( w,.. ss. ;.,.. s -terry,s. nOn l C.n s I 3..r e. c. e. t s. fw j y c.e...a,. r a. i t ( C Ii '. l '..'.D 's r.' *. v.,V "3 h .'l f. e 4 3 2 s* (..S'..a~.)- 3 a #. = 't. '/ .U **

  • C **.$ -'

~ w -f .v e',r..., 4 6 ' c..J 1 i u.s e E[.S 40253 .?. s S.,.. i. % ii s. .? O..*.

  • .,44 4

.. q u./. w. 3 t

3. a.., q i.,1 c.

v., p ...a J 1 C,< ',. i r,< ~ 1,.,1'

t.,.

v,i g l C.., S J - 3 o ,,3.,.q e 0 s......,.. .4.. a 7...,.,-.... : a..s i......,.j. v.. ...e -) ..s :,,,,,4,..,.,, .a.,..st i.. : s. ,,3 :.

i

..3 i.. 1, i; ..s.....s .**t .'....7 . a a. a. n. s.a i.. .s...,, i

r.....

.i. w a ...wo. .t s., s.... .a.* t-s. .C.,,,a.,s-,.- -..- .n. ...es

y.. e..,

.. u.s .(. ..r,,...,,,, ... 3.,,I.1 ...,i ..i....el .is. .;. w., 3..,....... s .e.. z ~

i t4 .~

t I n i. s

.e s. e n. r *. 4.s's.,. r s. m.a..- s. s..ss... =s m..Jn+. a:,^ n e. '. ' 'q = .u s.e.. v f e

  • ese.

s g 2v. .-. 1 t.,u. 5 1" +. 2. A

  • 2. +. :-s.cCV:T.u -.w.

a" s. j.L r -4 r.qj..s a,- # 2-0, .c a:. wo. v. 60. ..s..e

a.... - e. :. '.

".y a ww... igency tF.e eof, er =ny Of their e ployees, Oakes iny wa-inty, 2x0ressed er t4

4..3 i. eu.,

a s s...:... n,,. * :. :.1 1 13 4, *i 1.,.. v

t. r

.r, s a s..s :i.- 4 1 ;. j. .m.r

b. 4..- s.

r, ) .s w. i.. . w. .,.,..3 . A. _.. : 3 s...,.. w, e. 2, c.w...., ..., v.. . :. s-- = :,.,. 2..:......a .s ,.n. y.. wau .i. .o.m + 2. ~ icr orocess disclosed in this repcrt, cr repressnts that its use Oy such third -..... w o u 'e w' .. *.. 4..+... #..a. "3

p..- i.
2. '.e. '. v,.<...c.'.

. i.

b.. '. s.

A3STRACT This report documer.ts the technical evaluaticn cf the peco: sed changes to p 1.2 n e 2. w w, r g,.,O +.3 c 'L. u n 5j"s '. =..'.' " v, n i- ' 4.. 'e i. =..a.s s w" # 5 " w=.9 =. A.*.*n s^ 1 ' :"-. ra v .. e. w, i .w 2. uenter to account ice sing,se,icc? 3,En aceration. -.ints = valuation is restricted to onl.y the electrical, instrumentation and control design asoects ~ o:. er % ^.s,:#. c 4. 2 r. a * - '..".s ,' '. a.. u '. = c..h... 4. ',..= 1 s., s. e #. #. 1 c.= 'w # c.a. s #.- s i. r. a. l s 'i *.,.* o* 'a g y.2 i i v cperation beycnc 24 hours. The conclusien of the evaluation is that the Ouane 3 nrnoic i1 cense a:encment r.ce sinc.e.c0:: c;:eration nas mst tne review c-iteria -provided sufficient acministrative centrols are put ir.ts effect. ..--...,n.. ....s..., he-r:,. m. w' r. i s .C ' *.,* 'a i c... .= e * = r '... #. - h. a. 0 2. 'i *.. s '., s' 2.. $ '. i.."' w'

0. 3 2..- '. -

^ .i. s.* 2..C 6 as t s .-2m 1; ., 3 4..q.,3 _ C *.,.. d 'J ",. ' s. ".#'. .". a.l'. S. ". ". r '. a..=. r n s ~J 'i o 3 f- * *... i. s s 1',.o9, ^ # # '. w s. w isg =* iw w

n. #.

.. U w-l =,=. 'u= =.. *. c r .'.s. y "o 's a '. i a n, 0 4. V. s '. o r. v- #i L i c s.r.s 'i r. a, ". 2" 1 = a. a. a. - = '. '. ". s. r e.- = i ~ 3 . w. u +

u..s. j e. 6.s '1 t.s. w. v-,,3,.,..f.

T h. a.. f.t.. 3. n"g.. 'i, 3. .q.s -.. ].2. +.w p y....

3. $ 2 3,, pi ', r... 2,..w. :.

-r.,. 2 .a. s .. ;w ww .a i g ] s > s-j e. d. w.s. e c.q s..q *. 4 6 ] s. d u t s. i s,...:u' .J,- s. e.s. :..r. ; p, c..a. w- +.,, r.' s.i "... .I.'.' ; r,=. "1 II, 3 ' 5.5 i .+ E e . c.. la 3.3 I 1e.I,.t. .e. 0. a6 - M -O f.n. a -q

ev 4

n ( - 1 ^ 1 A -w-

  • y--

.w-q -y ,w, .i 9 gr g-w ee-

- ~ I. .....m, v,.,, e m. d. m o. .a

  • v i s. '. '. = - '. o

..k. =. U.0 ii(*'.=..=.-

0. =. ; 'J '6 = '.,'
  • j".... ". c. t 'i r..

^ l.'t.., ".. = *. =.. Y s, ... e. 9_ w*

7. O_c,.e. r e.s. -

i.

.,,, 3 7's.

.,j ' e., p. .:.r .w 6.,

e..-,. 2.,

.e-....2.-. 2 .r. -.. .c d

4. o :. v-. c :. 4. r n c g g.,..

j.s.> .f ne.gs.g '. j e... g :. ...a. a, .c i. 3 w--.,.2 3. =.. 2. r. u. 2..,.. .=.3 .,.w s.....i n,a60 ;.,,.:. r f, e. (, r..-ar 3-ic,.,

n..,.1 4

i) W. c.n

u.., :.

r3 :,.,..:.a .o. ... =.

i. :

L... sis...

ur v.

y r s e,\\. : 3 ( 4.. :. s... 1:-2.-

c.., i. ).

i. ws. .7 6., ...i2 . :c,..:2. s s,s. u..a :i i..., 'i s. i.u.1 e.

n:.#

1

4. n 1

.t..p:s .. a_

, :.n. z :. s -

a .. 3y.4.s e.:.:- ::;.. i e . : 2 s air.... " e =. ". s n '. s, w". i. c.h a = r e 5 2 s =. d. n.=. - =. ". i =. n- ,. #. 2.-.*.-=...'.c .=.'....v..2'. .-=...=.s'..='. a -~ transients associated with pcwer 0;eraticas in the sincie-loco ce provided I by General Electric Company, Nuclear Energy Division (GE.NED), tne nuclear s .,. 1 s u - - l y s y e....

s.,. s 4. -.,,. r.

e,

s...,.:.

1,. . e. >..... 1... s,e 3. :.. s. s g,2.., 2 o rs ., o e. .. s. d i s..'< s.n '.i i n "... = ^s. .'.'7. 'J '-=..-..". 7. ", 0.10. 7 7

d. 2. '. a. d. i.'. U I v, '. 0. 0. '. ", r'. c- #. O ',, '.: =.."i o.. - =.

7 a . L. :.. a. 3 3... 2., j - 2,,.=]v. 3 : ~,,. b '.'i'.. a=.2.. -=..='.~,.,.s'.-'n.. 2 O .=. '.,' c.- 4 ) x = '. '.- ,2 s 3 u 6.. m 2. t s

2.,.,/ 6 1 v s., s s

.,..w. .:.:.r.l. o c. The purpose of tnis report is te docu ent the evaluaticn cf the

e. ] e r. *6 r i w.1,

'i. c., '6 t.u =.. *..= '. i c n, = 1. u" c c n '.ro l ( :. P..s v ) d =s 'i ~;.4 .=. c.. e c.. > ^ #. 'w " a.'.. "r. s a. d i-2 +- w o lics..sa .=. e m.. = n ' c ". =.. c...o... a. "n' e r - 1 ' =. c.".n i..=. 'I s *, =. i i ' '....=. i o a. c.. d s ".. = u o. c o.. s '. w- =. r ". 4.. r. m #. pec-=.r 12.a.* "..=r.i = ", '. e e, e.....~".=- ....- d a ' e.,. =.... " C...=.

l. i _- = a. c e. s. ' >-

s w .,i.,. ,-.. i.. 1 r. s. -,. -.,.,,. ..-.,. o.. - .....= o ...... u i . t i s

a. v.= l ".=. '. i.. r1.

H.. >- - =. v ' =.. w.=. s i. -.. ~. =.. ~ s ' n. u.' n "a -=_.."ix,'. ~~. i v. "3enerai Desica Criteria for nuclear P:wer Plan s" (G.D.C. 20 thr:ugn 22) a.nc n..s.,I.... <,"

c.,

,,I ..,s=. - w r... .,. a........s..~. ....s..= '...s - r. a.t 4 .i, .e the.'GC staff for tne application cf Section a.15 of the 2.NSI/IEEE Stancard: . :.,, "u.,. 3

e. g..,. c. j ri ;..,. =....- - a. u... e.,.. :. o.,. < =., r. :. a.. w.-..,. m.:.:. v.e c. >.

e - ~ o s i. .+

s 1......,.. s.
a. s e.. e

,m,,.e.' 6 :., 4 n. n s f. :... n i

v. ~. a. :: a :::.:...

s. 2.; 10 1 >...,.. :., e s,.r... *.

2. A. 13 *.

... 3 . o 3.; a... r 2 .u...,.. .w3...2 ,3.s,. 4...g ....i. 4 S e s s.. ". o i n. C .=.-a.

  1. .q

=".3..*.*. w 'a. =. 0 r =.. u i # 3. 'd o v F... a. p l =.a..

7. 2...b n i C 2. l i

u J..-::I' :. :. s. .s'... 1 p .., ~..

s.... - 1 1. t e. ; i.r

  • l ;!.=i c.u ni., o. c..-. v.v.r.. n S ?. i. n..n t u

M. n.J: .w. .m i.

7. r. s. c.. r-o r..

n., e' e. r..1 -3..a.n :~.- 31 3.. w :. :.1v.s + 1 v n e -:.:12. 2 ~..... 2...,.. i. s. se s.. s 'i.,....,...= 1.n.3, , 2_ "s =. d 2 g,., w.= r

  1. . e., r.., r a.

'.".=o- .? C. ". ~ u - s. T.*. =. l ' - = " s = = ' s a o ..o.... ] e,3.. j f j e.s. 4.,.. m.,., w 3 3. 4 c.,. : 2. 3 w. n. 3 s. 21 1.,.x

s..

2 2.,. 3. g 6. e..:,2 s. 2

s.cc a e

(.,,,.. c. ..=r .>,n.:,.r.y..l<.n c 3 < r. 4. .,., 3. 3

4.,,
n - -.. : u. s.

.2 .~ a a ..s. on. . w e. ..,.r,.. . x..= n . w,.,, 2

4. :..

2.- 2 .a:

  • w
=...

..o.... 2.-= '.o '..".=. c."..=.".~;=....a=. .2..-=. ..--i. ".,.....> ....c c.;u s u,,. 3. ..i.. =. 5 3 en.... ..,.= n a s. e. w m .o e. .4 i,3..e. e..

4. 4.

2 e - a.. .,.~.a e., ] v.. > .v. s.4.... .v. ),, e.

s. 't w, a 3 2..,, 4. n.

a n ...a. . m. v. g A different ficw pettern is established in the vessel curing single ~ .-s c i rw u'. a *.i C n I"

  • w o's,.#..= 'w. w.#-.= s - -... n:..=." '0

... *..9 '... 2.1 ' d 'N^.^ C c ' =. " >. '. #. ^.7 w w s s

  • m

' L F. s. :.. si.

n

.1 ,. t. :. -A,.D c,.:r.2. jw,

4. w. 3 15 w.2,m.n e ] w...

.o e n.. - h *o n :.,. 2 -.- s

  • s w

3 3.: r-e v. o .o z. v a so

i. n

'.h a. i d i :. 'w~ a. n.. ". =.,i,,=,.'. p ".. c u-.#.

  1. 1 cv.'...2 a < u r =...=. n 'w

> ;" s '. s..,. i= s.= 1 4. 5 - =. '. =. '. = w ol.v '<.*..=... ' v'.'n ' %e.:.= r =. i. ~, =.. 2 - 3.. o- .o-d = '. l,i = *. r-... s.= - = '. n.

  1. . v rw c..d ' '. *. w.

4. The total care fica is the sum of the ceasured jet pu:rp fl ws. In single-loco - paration, the measured ficw in the backficwing jet pumps cus; be subtracted t fr:m the flou through the other jet-pumos. Also, the jet puro ficw ccer,i 1cient 15. dirrerent ior reverse 7lcw than ior iorward i,i w in tn.e je. punos. Escause of the different ficw rate and ficw path during single !l . e. r. : r,.- s..=. '...a. ' '. o. o,,, =..= i w., '.. ". = c'.:.:.V o .,.. u?. '.. i.n s =... i..r a. s, "...". i c '. a.- = a. y .. p x.,. 2c.a ,c_ 3.. .,,. j g o. 4. .a.e o. ,,3:. . :......,. : a c e. :. :. j r. 2.

4. e r. d,

-e.c. t i r =.. a. s s ". i..a.;- . a,., '. r o '. s ',. +r=_-=.2.'.^.,- i.v-... v- "...- '. e. w =.r. " =. 4 .o r.'d.- b i o r.k s =.'.p o i n '. c -" $ '. #. a., a 'as #.1 e c'.2. ed

4. n '.h..: e.=...d 4 4=

a..d "s. 1..W. s' 5 =.= q . o w s a e i -g g 4. y. 3 2 23 =.o.ws i .m. n.i.. . :. - ^ '. n 'i.,.=.a.,d ... ". s '. ~. 2='6 v' ' s. ..v w" # #. '. 2 d. '^#..' V i w^ = 6 s. >..g w 2 /.s. m. s + m. C a..r m. g. 4 en 1 a nro*er.*s.On.ur 3. n n s.,J..s. m. e .a 4*- .vu 6.-n.s. w3

r. ro,.

w. - $ 4. .. s.... 1 a. 4 : 2..; . 4 -ro...,: 3s..,..:..s.ig. .a

4.:...

...: i

.. s:

.. :.:...:.....-i =;. ...v. 6. 4 i n e. l JO=. '.h e M.(.Y c..a i n .a..d *.j c.....a..n. '. 6 e. 3...- a. n o- *. - - c .m, M. . 'i v,, O - s..c.3

3. n.

c. 6 .i i ~- i v. 4

  • r...>. :

sig ..w.u.. s. s. 3.c a. s :nis. z..ii.3 C,,,n. r s i s. a 2,,.,.o .. 3.4 .s g. : i. a. ..i .v a.. u ..w.. ~. . + h.: *. *..w. e.,. 3. r 4 ..a ua..n 3.,.2.-..,,. ..:.a .+ ...s.,.. ,e.....,.. r. s. '1 :. s. a. o g c .s.. 1 4.. e.,.,. c a. :....js. o..-. w..... 2.3... *. 4...,.,

4..c... : s a..
. 3..c...., ro

.sj ~. .s. a.... 3..,... q.. p. :.

4. 2.. -

4 . 3...,. 4.. :. 4... ....3

2... :

,.s....w.., 2, .s.., .2.. 3. . : w. J.. 0..l:/*. s.., e :. * :,.... 1 ... +...... e. s..

a

- = s.

Ths M a. r.. 2 ] A.O. 9 .2... 2.

.. g 6.. s..n. *.

4 3 +m 2.---.-+.;

s. s. c. :. -.. =. $
r. s. - 2. r. 2.:,,
4.,3 w.

wv .v y th e ca l y ch.= r e. s. 4

3...(. s.
n....m NA:~._]

.... -.. -, c.. :... :.,..,...- e.. 2..,.. i::qs.

  • w wa r

,;3 .v.- A. f f i e..a.s e r. m.as. $ s k. a r.=...,. n. :. :s. s3 s.n.....::y w w. v nn 6

., a 4. - - e s.

._..,..3 ,3 2. - > e. g :. 'i y s. -,., u. ..a .a. ,n.....,..

3. :.. u._ 4 w, ~6. ~,,.,.

,,u. ; s. u, m.. -.,,.,.,.. n ,3 a ...w. s.. wo iv, ii 3. .w ... e. 5..q a ./..* 7 - 4 ... a. r. 'I

  • : >- t. r o F..r 4 62. r.j.a a

.s .s. ^^ ** a l. ] ^s. a r.t. :.*t -;- :.X

1..

wic.. .v 1.1. L s..,,,01, v. 3 .w. C.15 c.4 uq v( - v.; : n, .- :. s.u. a :.:, v-e..,r :......,4 a,,,. s . :.,..... :.a a,/. u. e. ,. i. l i C = ns =.=. i n.R '1, w s. c.' n e. '. o s.s.'. ".. '.'.'..s....-. s_ C... s 2. -. =. '. 4. < =..=. = '. '., -.- - e * =. '.1 n S ..w. system (R?S) setacint trips for the A?RM and REM will satisf.v the functional r:. < u i r =~..s.q 'w. (j.=..,e-=.=..:..1,g .'., e.. : i. - i e_ e_, e =. ~. f.- 4..r..,

  • .T

..F c s .3 s i ng,l e-reti rcu l atiCn-l0Cp :C er:ti on. Ihe ~anu al A?R.Y glir i justment setti gs to 20:0 c;te single _i;c; d CperatiCn ic. '.h s Cni" Ch.:n~2 #.~ a ' d _.d '. m o n. '..b. s. P ' m a. s n' r.a. a l d Ca.s.a. P n'w. ~0 s / ro r s s re5Ctor prCiection systeO (RPS) ins;ruce.1tatiCC. This Change will n01 Cluse ..une n. 3 instrumentation system to viciate 10C.R50 A;;endix A 5e.erai :esign Criteria 20 -hrougn 2; [Ref. 3] Or IEEE-279-197I [Ref. 4] with the exts;; ion a c. ..e.m m..a w,,.. m.sv st,a u w... _.m m.:.n . 2.. : s e =.. -.. ..z .g ,.wg . a. e..., n r... a.... u .....,g .....c 31 a c. l a.- r s. '. i r.. '.. 2 '. '. a. a.'. v o -.~ ~ a. -. '. i. n e., i..r....: .-.1 s 1'.n, '. W. :- , g w individual jet-pump #lcw 3nc ;;t3] gg7.,7:c c;rg f;;g gj*; -53'g3;j] .g g

  • E C O.T.T.:q d

'.h a '. ~.h 0 < 3-. 21 +*. 2 '. ' ' ' u" J.a.'..*.*l .*^.. i 9.d.. _:t.T'- .3 .s - s_ .-+.-_, a r.

  • b s.

H o f.2.. w p.

e... f....2 q }. F.,. O.. - s.. *..e.......S.*.A.e...e..m 9 9 : e.2
  • 7. A ],

.I g g.2 P ] 9 e e. ".1 m. a. c. a. 6 a k.

  • o.

wo .+. v. .d h.a R: h 1.9 n **. 7 fd.. ...4

  • 777 Q&

S** --J ..j.... 6. 7 *.74 4 ...O., =.. ..b .I. E...e d h n s ee ,CI)*.' Ce )ssy."iO(@ ( d ', ~ 1] { 3 C W i ',,, * *

  • }

Ine T0re restrictive se p:. int for the A?RMs nas sufficien; i:Tinistr3-ive Ontr0ls 10 issure th2t the rs Est-ictive set::in ; 3 g g g;; .gg-

-a=.... a... 1.. a. _. -

.- e :...:'. t. 2..:::. .e .w......g. e

    • -.......=.. -
m..=a 2 -:..----:.e.. e s, s.. 6.- * *
      • .*-t

.......s 4 A6 .e 2-*' .t**'.*-*g

  • .. * * * =..S 4 : *

-..,.., e..

v. -.....:....

... N.... - e .. n..-...1 ._e

m ~ _.._ __ 2: .*4 .t. c L g

o....,.., c..-

......mw3 (Cuana ArnOI. EnerO..V Cer.t er-l ) i- / i-t -] 'f ...3

r. i s.e. t - j C l #. ":'.'. '. a.. # E v' W s..- f."....*.:..*.V'.*.*.*.s.*.

(' U. #..'..= d **~^2'**.'a.i, .'.'.O.. ~ a .s. 3 e t.. arc d nsenton). " d i n c. 3ie rsecircu.ation L: s v: era i n,' ca:e. v' *.M.3 'e . l 0. 71.. -( 2) ' General Electric C:: pan.y, ??uc'.sar ? wer Systems Divisien, "Quane Arnoic Er.ergy Center Single-Loca Oceratien", tiEDO 2:272, July 1950. (3) C::e Of.r deral ?egulaticas, Title 10, Part 50, A:pscdix A, "3eneral e Design Criteria for ficelear Power Flants",1981. (4) 7:::.... s.c. 2 7 o.1 c. 71, " C. 4. '6.a r i a #. c. F -^ *.s..'. i. a r. < y s '.s.. c

  1. . - -.". > c. 'i =.= - 3.w s..

.v G. c. =..- =. '. i n .C. 'u = 'u. a. a. c ",..:. s. "

c. 7 '..

4 s 6 o 6 9 I_N-l t- ,. m_ ~ r**>- r y

y pn atLuq); p UNITED STATES fl 1 ' gg 7 e n NUCLEAR REGULATORY COMMISSION y v ,,,4 WASHINGTC.*J. D. 0. 0C553 {

  • ve 4

y %,'C' f ., Q,, y m* FES 2 ES4 8 Q / MEMORANDUM FOR :'~'G."CTGiFai','EAssistant Director ^ ' ' fir"Op'erating Reactors, DL FRCM: L 5. Rubenstein, Assistant Director for Core and Plant Systens, DSI

SUBJECT:

SLO OPERATION SER'S As discussed in our nesting of January 25, we are withdrawing our SER aoprovals for all the plants currently requesting pemanent SLO. This decision is based on new data which indicates the potential for local thermal hydraulic instabilities which would not be detected by only monitoring APRM flux noise, which we previcusly recc=m:.nded. He are continuing to evaluate this problem and expect to establish criteria for acceptable SLO in the near future, & Lu /t J L. S. Rubenstein, Assis~ tant Director for Core and Plant' System.s, DSI cc: R. Mattson D. Eisenhut L. Phillips R. Label

Contact:

G. Schwenk, CPE:DSI X-29421 \\f' A g j 1 T fV F1. J q) a ~ .}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20091K568&oldid=4335897"