ML20085A958

Summary of 790723 Meeting W/Duke Power Co Re B&W NSSS, Including Nuclear & Fossil Operations,Integrated Control Sys,Feedwater Sys & once-through Steam Generators

ML20085A958
Person / Time
Site:	Oconee, Crane
Issue date:	07/30/1979
From:	Esleeck S BABCOCK & WILCOX CO.
To:	Linda Allen, Embrey N, Womack E BABCOCK & WILCOX CO.
References
TASK-*, TASK-06, TASK-6, TASK-GB GPU-0540, GPU-540, NUDOCS 8307070430
Download: ML20085A958 (8)

Text

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THE BABCCCX & WILCOX COMPANY N 5. "' " ~

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POWER GENERATION GROUP.

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DISTRIBUTION I/'

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Froe S. H.

ESLEECX - MANAGER NUCLEAR PROJECTS MKTG.

C:x.'! 2 805 443.J pM*,

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File No.

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Date NOTES FROM JULY 23, 1979 DUKE-B&W MEETING JULY 30, 1979 l.'..

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_DI STR I BUT T ON :

' f. I' D DY-7 NS.I i

4.-5 Embrey D. H. Roy M

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o L. A. Allen J. C. Deddens lJU N

S E. A. Womack R. M. Sall Q

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N C. D. Russell B&W Attendees J

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The :,ubject notes with the list of attendees are attached.

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The objective of the meeting was to obtain first-hand cc.- ;

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operator-owner opinion and assessment of B&W's NSS's operations.

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..his information is part of the background preparations for a ashi

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positive presentation relative to B&W NSS Responsiveness as

$d requested by Mr. MacMillan in his letter to Mr..Embrey of

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June 4, 1979.

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_ FECTING AT. cur'r 'C'JER CO M NY OM jut.Y 23. 1979N. 'r. -.'-,

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.c folicwing are the S&'d cr piled notas of cocnents. by Cuke personnel in respense.

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written questions. of July 16i 1979 'and ou.t. discussio.ns o.f.. JdTy 2_37: -2. '.. ".

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' e-al Cbservaticrdalative-to Nuclear (MW and Othard and fossil OMrations' -. -

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.1 U.P.. and R3 boilers require core operator attenti n than ruclear for long.---.., N - i.

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. term steedy state opera tions.%.J, C. d..,d ;i -,;., ;Q'..;j 6,.f :....

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The ad=inistrative 1 cad [cn'oserators is'=uc5 gireater on ' nuclear 'c. lhnts.-.7.

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.2 There is no 1 cad tr cking with Oconce Ir2 or 3.. Duke believes ali HSS

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-s::;:pt ters and utilitie.s. restrict load track ng because of fuel lic:itatiens

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Vnen Icad. tracking with nuclear.it. seec:s that1cnething usually happens'rW ' - '

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r whic.5 requires fixing and the' followup ad=inistrative require::ects tecc s

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!.4 Salews Creek (2 MW U.P boilers at 1140 We each).c:ay core down every.

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.;..q-. :- :a night on load tracking and hold:with 2. boiler feed,pu:".ps (appr,ei.' EM Tcad)g "

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1.5..%ct.ese plants regire :rore.att:nthW thanCfcssA13 znts%& haviann=

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c.2 gpa steam leau.

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1.6 ' Load tracking with nuclear requires feed and stes= handling syster.'s that e

have.twice the-transient c: ass =cvecent' of that 'cf af sir.ilar power fossil

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. plant, f.e., Eelews Cree. k.at 114C We each have.a r,c=inalisteam ficw of -

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- 7.9.mi.111cn pounds per hour,.'.the sace peser fdxi nucleare would req' irn? :. 7.3

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.w a;:proxicately.15 cillfcn pounds per he::ri. (M ! note: Jnis ~cbservation

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U-l and realizatien by Oake.is key.in the overali discussion of feedwater-J c.

.. ~..... ~. -.. c syst4.n sizing and c. sign for rm.. t.f ty and response,.).

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' At base' load the(Ocs:me units have generated'11ttle berated water for

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-reprocessing. Duke does not want to Icad.follcw (and could not at end of..

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life) because of.the bleed.volu:nes..Nasen:::;Qg of._tn.Tr"pnt.ics.ephg.e,s a -

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Two Oconee units are now basically chem shim units., Th1: Duke operstors it e

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s s also noted that planned load maneuvers result in less feed and bleed-W e TrN". 7. T E

[.g"9p[k volume for processing.

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Y 1.7 Ouke has not yet operated a W or CE nuclear plant but have received pc./f r a -- p a.

operator training in same and can conpare design features.

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1.8 B&W NSS has a distinct advantage over W and CE in higher red worth.

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B&W has "best". rod worth and~ requires less boron change.

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l.g For full load rejections: Duke reports that prior to Belews Creek only f

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p, GE turbines could handle full load rejection without overspeed trip.

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Duce stated they can get a drum boiler back on the line in fifteen minutes. A U.P. boiler may take several hours, water chemistry require-

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rents are a big drawback on the U.P. return to power following an upset.

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Oconee plants have been able to remain operational for load rejections up

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v......S't to 40 percent. Oconee plants have been able to remain operational for the (F. :

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following in-house upsets.

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t.oss of one =ain feed pu@.

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t.o;s of one RC pug (no longer the case)..

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Drop rod.

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l.10 For o to 15 per cent range of. operation.. Duke does not see any relative t.'Jr.: :t.

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differences between B&V,.W or CE nuclear systems. The W and CE units C.. :.~.. - -

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present difficulties in the manual control of.the steam generator water

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level. [ B&W units present difficulties with varying secondary pressure M.- i-kW ' :.

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$(d.Ec.,

causing core pressure variation in the RC loops. Example, a perturbation

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(small) in the sain feed block valve resulted in a Tavg drop in the RC bm. -

r.s loop of approximately 6 F, a significant contraction and pressurizer N[

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outsurge. There is involvement in manual set point changes surh as k -T,.'. ;

1 turbine bypass pressure and OTSG level and in the oscillation of control r ;;;.; u, l

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k& :.,?.:4Sf. -

rods in the control of Tavg.

The transition in mode control could occur at 13%.to 15t, i.e.. manual

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to fully aut::atic. fhever, because of sensitivity and feed va1Ye

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leakage Duke prefers putting the ICS in. fully ' automatic ai217 'rathei-7 '.

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for 15.to,TCO per cent'.. range o f' operation,- th, e. B&M..syste.:t is. :

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~ -,. superior".- to the W:r Cr. uni ts."..-T.ha: feed.f.orward aspe_ cts. of 'the IC5'.'i :.;6 ;..-:... e-:..

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There appears to be some fundamentai differences of. professional opinions.. 37,,,,..,.,

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,..a between design and cperations regarding the ICS and the full utili:stica '..... ', -.., M.. ;.lE7D

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^ cf.the B&W MSS with ICS.for full Toad rejectien..".The 'predcminant philoscphy~

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.E at Duke is to base ' load their nScl.e,.ar pla.nts..,M... isTi5tW; t

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% 2.1 Prior - to the'TML.2.' incident. Dukt was atte.,. ting to-tune and 'adiust T

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.u-their.0cenee. units to accept a full 1 cad. rejection with reactor run, '..i-. '

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., "..~-.... ck. j' However."it. wa.s. a s, low. process. (low priorityT.and was no.t. ".' -

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The.re. is a train of thought U.[.

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.%.T cc=pleted before Ma,rch.23.,.1979.,.

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..,.. Duke that any. tire you trf;r you :re putting. additional' wear and tear.:.E..,

.,2..

br..

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-.....a on the syste:r :.'. :1.. * *&. ?: %. : _.: &. ::....:.1.

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k b..

2.2 The McGuire pTants. (2-W a*.1180 rse each).'have 85 percentJsteam du..:p,.

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. '...'of~which' 40%. is to the condensar.and 45 to atmosphere via. PCRV's.. '..,.,...' E.

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Duk'e prefers leaving the PCRV cn. the pressuri:er for pressure. boundary' _ < .

p

-1'. protection only not. 'for progra: red trips. J.:. :,. r. - ~

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sc,-

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. /'...;N e,

Z.3 ' The ICS can handle soce transients that operators cannet..'t.ef, the W ' =. Y

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., q.y loss of feed is handled best by the ICS versus manuti or boiler.

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.following type of control fort or CE,...-

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,,Mr. B - a

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-2.4. The ICS require.s fine tu,ning often. Discussions in.dicated ICSJfine:.

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. tuning is acccqlished inz the.co.n.tml room i.n. -a cou_ple.of.instru:nent.

.(

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2

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L

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. cabinets, whereas the tuning of the rest of the systems reqtrires;. * ;:. *.:

~.,

...n-~

C*

p-s

.a Y..: c.+

.c.~.,.y :...s.

.. :. n acti.vi ty' 'in.oth.er areas,,..o f the 'pl ant..c....a ~,...e;,

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.&., e..1.u. s.T ; ". ~w.., ?.:

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. ~....,.. The Duke operators [ Indicated that there,is'.'a'. differe' ce in'

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...,.w,.m.

. v...

n t.

E i.-

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t.j and at high power....

"T;

sensitivity of the tuning at low power levels.

n a

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. levels, also, the systes: characteristics change with time and pow:r-

, level...

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Operator kncwledge' requirement i.s greater.for the ICS. Duke'quickly ' '

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. i. i-pointed 'out that operator knowledge,' both. : functional and phys + cal.i

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.s..

j.

J @; r

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cf any control system is, required and the more kncwledge they have....

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2.+,. '.a..~ * '...+ +L.+

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3.0 Fr&ater Svstem and once

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q.

'. s.

4..

.g.

y F.e,e W 'J3 Duke has.,

y haCthe fo'ilow.ing r.mter ef... reactor tri

..,..#:.. '. c R :.

. 105s of. al.1.feedwaters.. ;.c. :%.:~. Tu %,........ y; ps as a '.resul t ci.

W.i. ",

• ", >...,., :'.p.i: I: '%..

7

c S

e

~

P-

......'.i.

.L..:... A.;

7..

?

e...c.. n.

m i.~. '

..a....... t... 3%...

.4. 0. +- -

9-

... e.;.,.r..;

r

-J..' -

.e

.c, s

.i Oconee.T.~,- 19. tri ps.....:..,.ri ~, v:r.. :'. 7

3. -

.. t. 2.;.

m..

... ~.

... - -n

5. iI

2..

.y -.. ;., a h.

e

e O,.:.

Oconce 2 -4.6 trips. i. Z,... '.;..

J.

-..C. ".. v:.

t;,

t ;.

/-.

s-p... l

. :,.~Gconee 3 3

...... tri ps,?-.. :... m..,..

(

u., '

.. .In all but one or two cases. the reactor trip ~was initiated by high.

.i.

w.-.

.s..

....c s,

E

. r5.,

RC pressure.

In the other. case (s).-tt. wEs..Nitiated.by the operator.

. [. '1 #, W ~~

u.

..;.m.-

' ' 3.2' For 0conet 1, during the 19 reactor trips. fros *1oss of: aT1 feedwater -. t'$...-.

F -

. ~.

k 5.y at least cae CT5G w.s, tea.ed dry en "approxhcately 10 of the trips.;

E.

,.,. It take apprcxi=ately 1- ::inutes to steaa dry for this case..

.'M

.i.

r-)

~

A,:. -

(

Kotes C/

High pressure scra:n ices not occur for 6 to 9 seconds t/ r

.. -.... and CT5G in'rentory loss through reifef vahes for this ~

'L' t+

l.,

' integrated reactor heat input may be 15 to 20 percent.3 - -

p. ~

' 3.3f." Duke rade a strong pointthat bofling dry in the OT5G is-not a safetyl~. a

'.X..

h.

t v

l problem -'it is an operation an. d future maintenance problein.....,

.. a.

~.

.:.,..,, '....... e.

t.

..: r.

.. 3.4, Du.k.acreed the.tey to. S. tta..

..r a.o.ce ir, o

... s'.biTityt.. '.: a,..

l.

.c e

.ryt:..

-.s.. s.-.a.a.=perfors -.~.

c

~

~~m.r.e.. reH

.. v. I.,estet response ' o. f..the.feedwater..,systEC.

..~.n.-

" ~

i.

~

and 1

. F.'. '

-~....

.e-r-

. -~....:.-: :-;:

Jc.-

d.,,..,

,,,,w.--.A.g e,

,,q rw.

-.,.-:~. y.m q.

f....,

y

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• g,*.. * \\".{y? -..;#.

rI

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~-

7 3.5 Duke believes that for ths Oconee units, the fundamental feedwater system problem was their failure to adequately recognize both phisic$1

' [q j

and functional sizing requirements for nuclear feed systems which '

require almost double the water-steam mass mo'rement 'for a given plant 4

u

{

size relative to fossil power plant experiences (see Item 1.6).

I.]

-l 3.6 The basic feedwater system problems relate to the loss of NpSH at V

the main feed pump.

At Oconee the feed systeem is' a solid systen (no deaerating heater tank). At the main feed punp suct-!cn. approxi.

l::

- ~

.s - p w

mately 59 percent of' normal feed flow is coming 'from the hot well via the condensate booster pumps. The other 4T percent comes from the

~,. '

2 drain tank pumps which are handling extraction' steam condensate. On k

?

severe upsets the. drain tank pumps are unable to provide adequate

~

c s

A flow while condensate booster pumps move out on their head capacity

{

~

,a curve, thus causing loss of NpSH at main feed pumps. The loss of p

l the drain pumps at. both Oconee and Belews Creek cause severe feedwater '

!l N

perturbations.

i

<)

3.7 At Belews, creeek if the unit is. running on 2 of its 3 drain pungs

, ;)

(50% cap each), the loss of one will trip the unit off the line, some-l

• . h

~

..d times the automatic. start. of the-third. pump wi11 avoid the trip.

j t

=

~

ly.u.h

.,d 3.8. Duke continued to inake the point that their feedwater problems 6

Jj resulted from the necessity of fine control of a very high volume r

..5 system (the latter relating to mass rate of changes rather than -

l

\\

inventory).

./.x.

l l

.1 3.9, Relative to 3.8. one example was with a 16-inch valve they were l

.M trying to control a 6-inch level in a drain tank. They had to

-}

change control level to 16 inches and put in smaller bypass valves.

.y The Oconee main feed valves have been leaking since 1976 and,have

, [

3.10

,j l

now reached the point where they must be repaired.

l<

.5 3.11 Duke is reevaluating its philosophy relative to the use of deaera-i ting heater tanks-they have avoided using them (Belews Creek does not have them). Their phil5 sophy relates to the problem of pressure ll 1 1 control in the deaerator heater tank, they now believe that such-

...)

pressure control will be less difficult than the upstream control and fine tuning of the feedwater train (the deaerating heater tank j.

i would be physically located at the main feed pump suction).

/1 u

h

/;.-

. d.

,.p.,

Duke says they will consider deaerating heater tanks for future nuclear. J-'..

3.12 a

4

-and 1

p e.

6 e

Q

,' s ; e f g :.r

. e.

,9

.s 2 9 y

v..

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-f p

e t:

• f.

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_--__.__._____,__-m

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3.1.1 Duke points out that. inventory contrul of the B&'d OT5G would be

.i

.f ii F *#

l-j greatly enhanced with a deaerating heater tank -- they cantioned 'the -

p,

> r,g f

. possibility of some sort of an accumulator on the. main feed suctione.

p j

' ' ' i,,

i.

....... :)

~

?.~

p,.,y

[. - -

}

~ Mcwever #they are.,aho quick to point.out'that such'inventcry controp. [ -

- [*

.....-...~s..,:.

. w....:.. : :~..

.T...-..-... ; >,

I

. '...c.'.'",can be a'chieved wi thout'.the D./A. tank.~..

"~

~

.. W.,..:.. ;w.n. s. s

. 4..

.~.,. ~ } z:- T '. 3.-'.. C

Wi 9

4.0 General Cc. ents and Succestions by Duke %. a.-:.-M.;,..*.s.....

.....: :.... :......,.... :-;.,.m.. :.

-s

......a :.s -

4 s

s...:.

w..

... z.

.. /.- t. :-

..e..

• 9

....e....

m.,..,. %...?."..':..;n. '..

.~... ~.

... ~.......,

e. c.

'. 4 4.1. ' Bid blowdowns on the.0TSG should'be required du. ing low power: hot -

. m r

. ;..u

~.

standby, heatup and.ccoldcwn operationst.... Oc: nee-has. e:Gerienced 'de' lays -

~.

~

t while achfMng proper water chemistry.

~-

..w.

t. -

,... + y ;,...

s J

.g..,*:

.. r s.

7...-

.g

.. 4. 2; For RCS maintenance and ref0elirig. larger RCS drains are needed...

3.,

k.L.-;.

4

. s..

a

.....<. 4.3.

During operations,. Duke.has,..never had to override a. safety system

..i.;.p.e

,..p w...

.s

g.

J On rapid shut'down.as~the pressurizer. level. drops,'the. _cperatorm.

. g{..,

-J ay turn

.4

... s u

.'I

.on the second HPI pump in anticipation of its n;eed'...,

. s y

C r

. ~.

.c v.

e.4.. ~ ',. : :... N;- b:.:.~L,%.... Z ?.".i.' & :.. w.>. :;. m. ?.i.:..:,4:-

1.

e..

1

. ]4, 4.4

.s.

y and Cfhave programed ' ressurizer levels 1100 't0 200 inches; 1

~

p The.. level ris,es with power ov.er the.15' t.o 100j.ercent power range.

~

.C?"

.]

-;-, n..;

.s.

;;. t, v

.p

.gc.3 4.5. BN should censiderf a enarging-pw..~.p. for.RC?tseal:injectien in. V. ~ ~

~

J u

~-

p-d;

.~

3. -:..- r

, addition to FPFon? fu.ture plantc..,.W..:rf.ti:1. ~ 3:.. ~..4W M.>

~

~. _. m:m.

w. n y.-s 1

[

' 4.6 ' Duke ' thinks we sfch7it'EsTF@nt[Ydit?d?h:f9TMR h?g ' '

- S..,

. ; m

. -.. :..,. r.....c..~...-

k.

if

..,W an3... t =$..F. +p gif.f.r.d..

t' e W They believe this will be a.

p. #

...t.y;. -. -..

a

~

y difficult design probicn when you cinsider the phys'ical support

f. o.

f,

..J r.:

u.

}

d.,. :.,,f.. of the system with.a. valve, seismic require 5ents, ar,d quick dis - '

i..

J,.-

. connect ieature....;.... f..

. ;; Y..........

.e.

..)

. :.9

. '.):*. i.L....(..

.?.

~' ' ~ '

..i.

-. 3

,,".: ':, 4 7. Prior to 714I-2, and' reinforced nc%.i- --

j.hi; t.t ad(t.i. d.T~#..r.......-

ka ca estdr.i.rc.r?

.. ~

C

.12 -

.,1,Drer,,i.s 7.ced?d. - Heater capacity seems CX,'.but s5:uid En..'i. ':'.d'..i2 J ;

v..

.. ~.-

.9-

,1

.)

':..i..u ' Load.shet';i5Gr'"s 5f{.7

.:. _ -.... ' '-- -=

..s p

... ~. r e.t.ter v-=. tir.g. o f :r.ow....

. __, l.e_s

... ~..-.,, -

(

B..........:,.....

4.8

.i

r.censr.o../..f.e. c.=...th.e pi essurizer..i

.n

(..

E.'

i 4.9

~ ' '

YorF~iMihlN.. _:ssrc.ce.;:acityitn'.3.?%..". 's'.3,.5.'.T.~.ip.,'.

, '~

j n ---- --

.t_

......' 4.10 Ma.ke.

..... _..... ~....

. eased.S

,up a,nd td.o.wn.r.

..4

.. s.. s..t.e c.apac.:. t.y.,.sh.o.u. l.d.,. W'.h_cr.

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~

r-p 3 r as 7_-

4.11 Ct.ke r.ade a strong point that our pMIssef:Md4"" TOTO 6.'sE6. u e'"~. M P

uTN

~

1,

s..

-y_

--u

,r ( vT,p.. _ _. -,c,reased.; both. steam and water volune; too,nuch fluctuation in.

u.,

v.

V f Ge,.

.}

pressuris.er water level.

d

..u...

=:.O.n., ;.

-~.e.:

a

.p

.~.:.,.,.....a:%,.,..,.....-.

s w......-. c... e.

.:s

.,s-.

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3

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e.

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n. ;.. x, _ _ _ _ _.

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4 12 Lii.h. time eng experience. Duke

-',~...e-.-

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3 4

s

~-

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.. =.

.e beca:e c: ore wre--

1-cf the folicwing.

Y..

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~

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.- m,-

o

..... : ;. 1. t.

.-a... Feedwa.ter sensitiv1ty'.

' * 'L. C * - ;':--.-.

....... :!- l

.'. T..

• ; ~ ';W'

~

y.. gIfficulty wim n 3*3 %"*"' or indicati

~.

~

... -.. nutk.

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'V:.:4 h l%

.,7. =.Ybe pursued fur.

ent

- m. ar..claetricatten.

-.

- m m...n y 3. ; -..

k........ ~ C".~ ?IES SUVI Zer si zin g... -I b. *.'...*. y '..,.5.~ S...$.. =* *.'.d.'i.

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h...,'d.,.A. *. ~. '2. *.' C.

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.- -~~. i.,;-:u. :..... p.. ;.; ;.. 3 -(;-

- ~ :. sen--o- ~w:.:._

,3,

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- aces et sejy with Duke,*s;ecp

.. -resultin91n an ~vera11 sensitive 873

. _ inven+"'t.surgin ca:.,1bn g&

• , Thera.1-I t t'~1** -'t.' '.W"v;.+:, '. :..g y

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4 m

-. a...

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2-F-1...y..... -

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. g75.ecs and the s. eta gengras_gy' '

-ne. candasate-geedwater. P +. -v-w. M s

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L-.

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h W-sensitive ta 0TSG Ieyt;* j., -

C M - & c.s m _ 2..._-

-=. - ~ ~.

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r

• u 53 particular dur, crin9 transients a M in - "

IY'- ' # b T 5

, pressurizer-Te f ats Mich 'aiso icpact-ca i

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[

4-.

M. J

• t. P.

• EVre.

• ....,..N,-..

...;3 -.'. a'..,r;. ;,..,

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Ute p.3dg a gg7gn9 Pofut trg.._

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geg, g,,._ __..- M..?;%.-Ca tm D,.ey oCe3

.a. e3

=--~<e-

. '.. ~ ~ -......

e

~ ' - re has besn'a *re:d '.

." ~ > M.<

. sess comunications betueen Ek. an

- - - *- 5: *

.... d Duu e5.5n7fnearing.cesf "'.-

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o r.

5 y_.'..

-t

.. depar ~ents, '. They ~Mn a..

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" = * ' ~

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- tMSe 11nes of c,~.:

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. $ ^~ 2;1.-me.#,..5 ? 6 ~

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W Bacc1ch, Jr.:.Q...:.' Y. 83:. 'W Y.N; --..$. 'C.l.3:;,~.:...g -

6

- -... :,. --^' ' [. '. a ' U;.@ ~.

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. Paul H Bar*g ~ ( ['y '# ~N ~

~-Q' y * [.. y' feg..S h y

- C 3 ' '. y...-[ ~l'

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]

• f. Ken Canady.

. ' ' ' ' -. (:- _.;; Systn oper & hint.

h.

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CTay L.i ttl e,

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=-

x-m ' a-es: %

. & J :.'%. W..

.:a ~Projegg, & ' Licens f ng : 6.u-

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r

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.... ~. %....s.,, ggy. z-M..H.G.- '.:. . '.:.T.:Ps.tead }L,.

e..

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. John cale..-

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*.. :... '.' Steaa. !&'C' m

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1

• - 7ed MC& tkin L-. : ogg, -..'

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C L. Sansbury

' ' ogy, ',,k.

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+.

)

_J'g' c,r1*cn

_ Des 190'Eng ya

-i'}

l f>

,b_

.. Design Eng. YL't

-.SG G.E. Rambo

. 4.... ~

SG.,.!

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2

'. Power sys.*=5 & Controls..V.2 A. [*

5..

y :-[.-l..cevelopb'"* E"91"cering unic Y

N.

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' H J Gavio11 (Hive}.-".}

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S.A. Holland ~

t '.S'h '.

.* * ' Projec+' SUI *erYi sor

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n y Currant

~

Duke-S.H. Es;eeck

~

- Operation-L.m$g--.

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- FPGD En91necting Tech.dogy

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