ML19224C197

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletin 79-08.Forwards Results of Review of BWR Sys Designs & Operational Procedures
ML19224C197
Person / Time
Site: Cooper, Crane  
Issue date: 04/25/1979
From: Pilant J
NEBRASKA PUBLIC POWER DISTRICT
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 7906290341
Download: ML19224C197 (4)


Text

%

i g

s '

\\

/- %

. -=

(

I s_c cM m NuctE 4 m si A iCN 70 ac x ex

_w.

ra s s u u m i.ebraska ic rower o.istoct y

f =< = ~ c. m s.s m m L._

. = = = ===

= - -.

,=

=-. = = = - -.

- -- -=

= - - - - -- -

3.,e

,a*,

'. d r i.

.),

a:o:

/

/

/.

r' a

v...

.c e.. :. 4.., w..

C.O,

[

.4 1 y.

w y..

~...e..

s.i U C.7ea!

e pia 0 0 r f LC ='2.S S 1CC f

C." :.. a., :

u n d' e.

6m..e-

.., S e C e 4.,

w..

..p w

a j

,(h h To -4.-... g.

a 1. *.

2..,.,

=. =., _,.-

{

x,,Q %. '.!*k4s'}

-e s

s o

y,h. ;h

.c.,,.vV9 4.

4 4. t.

2

. e 9...,.._; y s

7 4_ q i._7

..c i

Y f

-s,

.u,.,,..<,....,:._ r c.

c,,, o

..m v,-..

s eM r..

e... e..

O,. a.*.-2...

.w

,4. a_.

e, a' a. e.

g y

..t T.'e a C * * '.* C

'. # # ".

  • 4.# 4. A d

%. ' ~. #.n 0

'.6."5c. a.

V. #. 7 a.

~

  • *kQ

-.-g..J.

..g.4A3 c7

.s

.p..

V....

.C, e *f.# '." #. *. *.

%v g.

s

. '.15 aatte r 15 Vrit*en 15 a response 00 *he Subject b le-in which 3 c_._,, g., ; -...... -....

r_3_...

n afao_

e 3

..c a.. c.

5

.c

.c..c.

~....

3.

_...-._.,~..c_,s..

_fc.a

_ 2 r... g 3.

...g

.1.,..e..,,

4.,.3 i

. '. m u 3..,w 7 p a c e;., e - c C. 2.

. 3.

...a

.w.

m n

.n.

i

. a

...sy

.p_.,33..A.

... ? ?

.3 L, 7 7 o.

4..,.

.u3

.. ~

u

. 0.

. '.e Ce Sc rip 1Cn o f CirJU. S tance S teScribed in inclosure 1 Of U.

. 7 7 o. e.,. J C. _ Q.t

.h.

3.,14 4.3.v

,..O.0eu n.e

. k.. m w T.

7.

i v-.Cn..:,

aw - -,

.y

.w s

.u.

9 C, C. oC,:C'a.

9

..C.._...3A 4,

r, r.1. S. e..,,... 0, 9 _ e. a.,., c. _,).c..s*

L.. -., o.

.w

-r n

w

.e, 4.g..e g

.y

..t.1 7 7.f. a ".. S e d C "fG. " a^ ' 0 ". S cnd

  • 1

_.'~..a'"--E"***-

oeo,
s. -

^

f.-

6

/--

w.. e.,. e.,. w y' e '. ~ ' # *

  • a.' ~. ^ S *f' ". 5. h d.' #. *m*.#
  • S.

. f e ". c

.# .'.a.' * * " #' C '.,*. a l.

4

..c v.

w

~~

f..s x.

.o.-..e u

a,

a., S...

, A n

.~

..w s

u CVe, 1Ce cL.. -.3.a.. c C : -.- n... n s c -..

ou 3 0.,.

q.. g o v. a. ?.

a c. a...

u.,.y.og

~

.9 g :> g

s. v..
4.,..U p ;

m,a_.....e,_

a. n.. ;, :

_.. c a_. a k v.

u.

r E ga-u..g

. 411

.-p g g.1

-....p 4.

... S a. e

.,1,,...

ga.s.--;

.-....e.e...,

a A. (q)

C.

.,,j...

f.

12he CperatiCnal deCiSiCnS haSed SClely Cn a Single plant paraneter indication When Cne Or ~2078 CCnfi-~".atory indicatiCns are available unleSS it is e CUn " hat the action places the plan

  • in a Safer C ' 'i.' # * ' a '. '. C '. _

~~

6-

-,Ane COntal~nlent ISO.3ation initiation CeSip anC

, ar00eCures : ave f

.Oeen reV*eVec,

.00

-A e Ch n ic a.3 e

opeClt1 Cations rec,uire that a l,.

nanual Contain ent isolatiCn valves not re e a4 te be open during accident C nditiCnS be cicSed when Contain ent iS requireC.

.neSe talves are CICSed and Sealed.

All autenatic valves nuS! ' e : p -.

e -

u. e,

w e a u-

.<. a. 8 C'

<O

- '.. e.' S C ' c-w e 4 4

fe d

--e..e...

_..e c-a.<-

COntainnen". iS Cla tion Val'le S iSClate priCr CD or Concur;=nt gi,h One initiat1Cn Ct. One Sataty SysteOS.

0;OCedureS are in effec; to 4 -. ' a g e.. e

". g e %. %. 4

, 3

c.. e C 2.:.4..
2.,,..

,.,,;.n,,..

-r.--

f

w. c..

f..,f.

') d1O 9 (/ 7)) cr/

(

790g~,903 %

l l..

u 9.,., y.

e..,.. c. 4.
r.., 4.., 95,

.? c, q

i r.

o Page 2.

3.

.ne 21gh Pressure Coolant In'ectica (F.?CI) and the 2.cac:or Core Isciation Cooling (RCIC) Sys:e=s functica aunc.atically as aux-liiary heat renoval syste_s if the main feecrater syste is not available. Tne EPCI System initiates aut aticall) on high dryvell pressure or ics reactor Jessel va cr level.

Tne RCIC Systen in-itiates au:c=aticallv. en icv reacter vessel level.

2,.a a><c _. >e u.se =...u.-.

=-,..a

=~c. - e.. n. =_ _.s

.. i., ~..

.a,; <-.- a.

~

a.

.....a

'cv reactor level and continue to pt p water until the high reac:::

4-e,.

._4

... p p m.n c. u....,..

.u.e

.__,e.,

.d. s.".a..~_ a,. ' _"_ d,

a.

u g...:. u.

.u..e uc.,

e,.,-

-..a,,~. :~acs".e Cow'=~...

'...'a...'-.1 v....

c.. c., -2

._.a2 a

..u c.4.. o.. a m. - _. e a _.

v a...-.. <.,. 3

.3 4.-..

w e -w

. _. 3_1

-; ~_

t'c.c EF"' Syste: vill restart au--,-4 rally 2: the low level se:-

point if s:eam is aw.ilable.

Tae RCIC Syste

=us be rese: locally c.

.es.-..c..

..,. e

.-.,..D..

w--

v.

..e,v.,.,.,,..... :.. o w.o..:C.e

.4.3,.

a Cpera'O: Can take Canual Con:!ol Of one or both systeOs

-='n-

._4,

. e,, e,.

.,m....o-.-.

8 3 -. v,.

.c.

-c

( yne (w, o1 2,,.c;a p

.g

.,.e

.-:.5_ac.;

u.a

4.. 4....a.a.

2 c. - _. ; C u,.'.* n

,y p

-n..

.a_..e,-..54 g.a e

-5 e.

...5 s

-4 eh. e $ a,

p?.

4,

.-a c.J. e.:

..v

...-a.

1.,c.4

...m....

...3_.

a u.

. %.. e z..g. p a_, : u-e,c

a.,.,. :

2 2. e..-,.

s.,4..
u.. e s,..u : - %.,
i....a a. n. u-. a_

.a cfc

,.e u

a

-m..

locally, are ten independent level indicaciens in the Ccntrol Race.

C erators are trained to lock at all the indications available and 7

this is also noted in Jarious procedures.

...e o,.e.,.,_

.vceru.So c.. c.. a '.. '.. 3.- y..e.=

s

",.=va.

's e a.... =_ ". '. a "- e #.

.-..e, f

o c -

-^

o

  • insure operators are directed not to take Canual Control of engineered safety feature s;ste c "- ass continued operation would result in unsafe plant conditions and that they are instructed to eXc. 4.e c.s..e

,,u_n.

a - e.e s <.

,,.a.,c.a-.s.

p., c-4..

C-.C.

4-..s.

f.

f

.c

.3

c..

.r.s'-.ns c# sa#e ".ala*-ed

'.as

-.a c o.... C ' e d - '.. 'n e.d.'. a_.

e a

.1 centrol rec = position indication or valve pcsition seals.

Fol-

~

loving.aintenance, valves in a syste= are prcperly pcsitioned, then surveillance procedures, perfc::ec' before retu ning the systes c service, verify t,ie positten c:. :nese va es nrougn ac:ua3 sys:c= cparation.

.nese tests a.,so nave spec 1:1c stees an, checy-ef f s when certain valves are : ved to an abnc- :a1 pesi:icn.

Valves e.u...os.

.w c'

S. e s u -,. 4..'.' -..u e

...e

-..ye.

s'..'c.. as c a

w a..

pr:cedure, and a s o., e c,.,ic s t e o.

enector: is rec.u1 red.

.. sa:e:v.

e..

az

-,.a

.s a s

_.i....<.eg c..

y.e. e c. c._ -.

u-

-;s..a.c..,g s

a;

.e e

,c_..

nl.

. o. s s a n d

..c- '...e. c n C a_

, s a.# a. - svs a s c-.a.

A.

e.".."a

he concurrence of the Shif t Superviscr.

,, r r g)7 L

)

5. J O h

f,gh/MU em&N e

a

.- 3

n...ec..c.4.
u..
1. -. <-.1

".C,

1 ^. *i.Q c

Page 3.

7.

Here are three ain syste s which could transfer potentially

., m: ' c, -. _* ". a_ r~ oes u d 'i"A'ds ou. o' -.'_c-v,..-~..~.-.._.c-.

-.a_

.f the ?' co r C rain, Iquipment Drain, and '.'entila tion Sys:ces.

'"h e drain systers isolate on low reactor vessel level before the ECCS initiate and en high drywell pressure concurrent with ICCS in-i. ' a m* n a...

'u.*_..g._mc.o.

e a.,

_4-..,

.k.. a_ " a_... '_ '_ a *_ c.. s " s % - 's m

.se_u

,.a-c

.,,.< a. c, n. a <._ e n.,.,

o e c -..m u..., -.., <.. _..,

_so a.es cr the r o conditicas described above and on high radi2:i:n lavels

a... e.. e.y. a _, - - <.,. e v.'.., ", s.' -.. e s.

o

',s

-aa.

=.....~ ; a i. a -

...e

.=..d'. y

_ s6v also initiates on any of -he three condi:icns describef above,

,i..,4..g 2

,,3,1.<ve p.es2 e <n sec...>a-,

c...=.a.. en.... a.

_...a.=-

th e e x".a u s t.

hare are also drains frc: earicus au.<11iary syst::s

. s.. e.,.m.. 2_. e.-... 2_,. o a.

u... e.eac.,.

_,,,,n.. o"s me.-.

2 ~- e ". e.,

"a

-f

. ~ -

drain valves en these systers isolate ca low reactor water level er s _3..a, s " sea, e.,.."

, 4 4..

0.,,.

-., s s u,,.-.

.,.e

, c 3 -. 4. C.,

o..d _..s u.8 4,,

,s

.a

.cu

-.3 w

f-i.

-, o.s.. a A,.

%i;..

gnu-g e e,. p e C 7 2.., %.

as.<,.r.

7.. e <_ e n,s.a.-..
v. a.n e. <

.e... s,

n n

.w.

s.

c eras _1:v.

ozic an,_ 1eas rates cre testec cer:ccica_3,v as se r

forth in the Technical Specifica:icns.

On this basis, continued operability of these isciati:n features is assured.

3.

We have re'.ieved. cur Sta ica Rules and Prac: ices and c:her Ad in-

.e,. ced" es *..., _'as" e ".. e v,

. a_ c ".'.- a - (' )

. a_.. _# #_ _ a-. #.... c#

o.c y

the operability of the required redundant safety-related systens prior to the renoval l a safety-related syste frc: service, (2) ee-ificatica cf the jerability of a safe "J-related syste fol-icuing its return to service, (3) notifica:ica of operaticnal

c. ersonnel -tien a safe:v. systen is re cved frc: cr returned to s e r'. _ C. A.

3.

We has. reviewed :ur prc:p. reper:ing procedure for NRC notifi-tation.

,ur c.roce,ure.,or..on cal, c.ersenne.., orovides an ac-ec. tab, e ce r.noc c:. assurin that a reso.nnsi:_e person is aval,ac.e l

3 c establish continuous cc cunication with

".e TRC, if required, withi: the one. hour time. period.

10.

We have reviewed our operating ecdes and precedures to deal with sig.ificant arounts of hydrogen gas that ay be generated during a transient or other accident inside the pri=ary syste: or be re-leased to the contain ent.

-'he pri:2ry centaincent is.nerted with

~~

nitrogen during reactor cperation, precluding a hyd:cgen explcsic:

inside contain=ent.

he A::cspheric Centainmen A::csphere Dil-

~

u:icn (ACAD) System is installed but presently avaiting NRC li-ca_..s'.n a-r, va'.

~.~..'s s": s -e-.

.". ' ' a ' s o d e = 1

. '. ".. '-. " d.

e-o_.. o_

-=

s ersted during an accident condition.

,) p.

k h

p b N [c)at i

aa

Mr. T.a r l ". Seyfri:

a.-...,__,, 4e,

, a.,)

.s Face 4.

a n c u. _, feu 'c. ate 2.n j quest:.cas ::nce r.ing :nis res;:nse, ;;a2se centae: ne.

Sincerely 9 88

^

,VT G Ww

/

T..

v. -. ; <

n.

.-a Dire: or of Licensing and C.uality Acaurance

.M. -. T C T Office of Inspe::ica and Inforcenen:

Oi.isien of Rez::cr Cperations Inspe:.icn "ashington, D.C.

20555 m

9 e

~

4

}QhThY

~

W

. q,:

5 O

s q% s-..;

4

.y..

/

6 -

L..

L., J em