ML19248D010
| ML19248D010 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/06/1979 |
| From: | Ross D Office of Nuclear Reactor Regulation |
| To: | Deluljak J AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML19248D011 | List: |
| References | |
| FOIA-79-98 NUDOCS 7907300400 | |
| Download: ML19248D010 (2) | |
Text
~
h g
3 40
/
~
y p
2&
/
d7 -
DISTRIBUTi:N:
Chairman hendrie E Hagnes HR Denten M Groff (C656C) 3m-r
,#,DF Ross SECY Mail Facility s
CHelteres (3 cocies) 79-1352 JUL 6 ~c#c H Sha:ar 53 Chren File E Case SB Rdg File DSS NRR Rdf F Sqhroeder RACa pra D Eisennut 0 Muller its. Jean Oeluljak
.cl r..,,,
j
.aa. _fu Euclid, Chio Cear :4s. Celuljak:
Your letter
~-Gune 13, 1973, to Chairman Hendrie, ha: taan r2farred ic Oc for resi. Y ce etter requests tha: Oavis-lessa !ucisar P:.,er Stati:n, Unit :lo. 1 (;3-1) n. :e allowed to resume operation un'il ycu and oth.-
- ha anc. al public can ba assured, by cans of a pu lic haar",
ce :ers a:
that Toledo " n Ocapany and Cleveland Electric Illt7icati13 00c;sny (the licansae:) can operate the facility safaly.
As /cu ar2 undcubtsdly awara, the nuclear reac cr of 25-1 was desi;nad b; the Cabcock s Wilc x C;m:any (Blu), whien is tha same basic desi n as :na reac:ar of Three dile Island, Unit do. 2 (TMI-0). Becausa of tais sisilarity (al though :nere are 3 ce significant di f ferenca: in tne de:2iled desi;n: Of hese units), ne ex;erience a I;I-2 has raised car:ain questi:n 2r:n; cur
- ennical s:sf' :: to the ca ::ility :f 23W desi nec units to adecus:al, r2 penc *o cartain transiant plant ::ndi icn:. As a resui; f cha:? ::ncar.:,
tae C =cissicn i: sued an Crder en "ay 15,1979 to the licansees, cire::in;
- bem to take certain actions witn res;ect to CS-1 Inc!
- sure 1 is a ::;y O'
- ne lay 15 Ordar. Psragraph (1) of Section IV of the Order directac the licansees :: taxa certain ictediata actions to increase the ca;acility and r:113 bili j of C3-1 to res;:nd to varicus transier.t ;vants. The Crcer a'.s2 directed tae licensees to main tain C3-1 in a sha::o-n ::n:i-ion until 'r.ess immediata acti:ns sere satisfactorily :::cleted anc ::afircec b/ tie Cira;;cr, Cffice of Tiuclear Reacter Regulatica.
The staff of :ne ?,uclear Regulatory Occmission (!RC) ha: ::ccle'.ed its ravii..
of the actions taken y tne licansacs to c:caly with pari:ra:n (1) af Sac:icn 17 of the "ay id Cr:er and has found them to be accep*able. To d:cument One support its revicx of the 11cansees' c:=plianca.41:5 the Orter, the staf" 3 1ssued a Sa fety Evaluation dataa July 5,1973. A ca:y of this Safety I/31.a-
- icn is incluca: :s Zaclosure 2 to this le::ar.
I'.e Di rec Or, O f't:2 of duelaar 'eactor 2.:gulati:n ::ncocted a C rm.issi2n briefing ca July 5, !?73, and informed *ne enmis:icn 0,3-ne 4a satis fiac.ith
- na licensee:' :::: liar.ca.ita the Orcer sad tha: ne 4cu14 lu..cri:e 23-i c resu::
- cwer 0
- era:icas sncetly, i
1
-~:i-
_ i _. _ _
,1 I,M. pg1 r~ r ri
- 4.*s bp OR I tl 3
1 L
i NJ A.
I q, qp ts...se.i n viri
.t :. :m a
- 5 m:4 :.a n
.au--.--.~2-u~-.-
sis
/
19
~
.c-,3 d'
JL fi
. :s. 'ean Zelul f as.
I.i adai-ion to :he i rediata actions re;; ired ':j the Crdar, th: lican:ec:
have also been directuc to carry cut precptly, cartain adaitional long-tam codifica.i:as to 25-1, to fur:ncr enhance t:ic ca;;abili*y and reliability of t.e facility :: respond t: various transiant events. The license 05 ::::
subait to the.GC staff, within 30 days, their senedula for c:mpletica of these long-tem acdification:. Tha:e =cdifications will also be reviewed by the 2;.'.C staf f for their accaptability.
'Jith respect to your concern about a public hearing, hearings en Ceders cf this type are not schedulad unless the licansee or a meabar of the cublic, hosa interast may de a ffect:c by t.*.e Crdar, re<;ues. a hearing. State Sanatee Tin
.icCar ack has filed suc. a eoue:: si:5 the Cc rai:2ien by lettar: da:cd ':ay 3 and vune 7, i n s.
anc C :=ission has dir:ct c tha Chai-an of the At ic Safety anc Licarsiag Scard panel to salect a board :: ::t n Carat:r cC:r-aca 's pe:i;icn and ta censuc: any nearing: as a resuit Of,is ;e:ition.
I us: poi-.
out, he,,ever, tha: the filing of this petitico does not, of it:alf, staj c:ers-tion of the piant. Enclosure (3) is a c:py of tha Oc-.ission Cedar.
If I ::n :e of fur har :::istance, please c:ntac: re.
Sincerely, M.T M ar d D-
=,
- e m136S Cenweed F..icss, Jr., ;ccuty Director Divi 3i:n of Fr jact '2nagement Offica :? :iuclear Reect:r.:.e;uiaticn incl :grts; ns ::at:d KTR OHL O'A :*-- j *,v 3
0.a. ce 3.g,-,
e p..-7 j
see -g.
s
- ~* ;,t = "
i
. - q _. 2.. 3..-
.- :w;;
---3 r3
-v
--7 3.-e.
3
._ {
I f
N' ~
.~C iiL '
i8 4
' X Ct
..)
,...s.3a.,..........,,,m,,,,,,,,,,,,,
FQO O u c.4 4 8 L
3, S//6/7 f n
~
UNI"'D STA TS CF AMER.~CA ecet?
p u s e-
,1 xx:. EAR Pzcutx: CRY Cr.ISs:a1 g y 7 373 >-
- r. -
c-
,m
..s..,...
o s.s s.
In de Matter of
)
h
)
%l J id 3E TI.ET, DISO1 COdSANY MO
)
3E CIF.IRC EI20' RIC r'"'M.INA"'DG
)
Eccket No. 50-346 COdSANY
)
)
Davis-Besse Nuclear Power Station,
)
Unit No. 1
)
CrCER
"'he Tolede Edisen Ccepany (TECO) and W.e Cleveland Electric Illt:nirating Cc::pany (the lice. sees), are helders of Facility Cperating :icense Sc.
NPF-3 wnich authorices the cperatien of de nuclear pcwer reacter kncwn
=..
as Oavis-Besse Nuclear Pcwer Statien, Unit No.1 (de facility or Davis-Besse 1), at steady state pcwer levels net in excess f ~72 ega 2rts tner.a1 (rated pcwer).
S.e facility is a Bacccck & Wilecx (E&W) designed pressuriced water reactor (?nE) Iccated at the licensees' site in C tawa County, Chic.
..12.
- n de ccurse of its evaluatien te date cf the accident at t..e W.ree Mile ~slard Unit No. 2 facility, wnich utilices a S&W designed PWR, the Nuclear Regulatery Cxraissien staff has ae-a- -~'
' ' - = - "&W designed e,
4I hhmb JUll Uh 3,IlJ LL a.,o i. f m -
7590-31 e
reac.crs appear to be unusually sensitive to certain off-necal transient cenditiens origirating in de secondary system.
S.e features of the B&W design dat centribute to this sensitivity are:
(1) design of the steam generators to operate with relatively scall ligaid volumes in de second-ary side; (2) the lack of direct initiation of reactor trip upon the occur-rence of off-nor=al conditiens in the feedwater system; (3) reliance on an integrated control system (ICS) to autcratically regulate feedwater flow; (4) actuation before reacter trip of a pilot-operated relief valve en the pri ary system pressurizer (which, if the valve sticks open, c[
aggravate de event); and (5) a Icw steam generater elevation (relative to de reactor vessel) which provides a s:raller driving head for ratural circulatien.*'
Secause of dese features, B&W designed reacters place more reliance en de reliability and perfec.arx:e characteristics cf de auxiliary feed-water systen, the ICS, aM 2e energency core ecolirx; system (ICCS) pe r-for ance to recover from frecuent anticipated transients, such as less of offsite power ard loss of nc=
feMwater, can do oder PG designs.
S.is, in turn, places a large burden en the plant eparaters in de event of off-nceal system behavier dring such anticipated transients.
n is nctec that al eco;h featres nu:oers 3 and 5 de not apely to Davis-Besse 1 to de same extent as they apely to other currently licensed 3 W designed reacters, the etner featres are fully apeli-cable.
rm11.8 aas
7590-01
. As a result of a prelir.1.ary review of the Sree.w.ile Island Uni No.
2 accident chronelegy, de NRC staff initially identified several ht:.=.n errors t'.at occurred during the accident a.d centributed significant.iy to its severity. All holders of operating licenses were subsequently instructed to take a nu=cer of i.m.ediate actions to avoid repetition of these errors, in accordance with bulletins issued by the Cor=issien's Office of Insoection and Inf:rce:nent ( I).
In addition, the NRC staff began an ir:nediate reevaluation of de design features of B&W reactors to dete=ine w :ecer additienal safe:v. correcticns or improve::ents were necessary wid respect to these reacters. Bis evaluation involved nu: cerous meetings vid 3&W and certain cf de affected licensees.
'"ne evaluation identified design features as discussed above whid
=-. _ _..
indicated dat S&W designed reactors are unusually sensitive to certain c.'.'..o... =.'
=..s. e... c....'.#..i.. s -..',.*. =..'.~., '.. ~_'. a_
se
.d.=.-v.
s v, s._a.
A.s =. a_ s _', a.. a.d. d.'..' c. '.' 'cl.' a.. i.. w=s.i suad. 'v, w"..'..". i..s..-".
- a. d o
... d. a..- s. # -:e.=. 4...c..'.' - a.s e s
.#.- :aw.-=.=..-es
=ka_
...a--.
a
..i..s, inclriin: i: _ediate dan:es t.: d:<rease de reseter hic.h eressure :-ip peint and increase the pressurizer pilot-operated relief valve setting.
~.e.~.,
a s
.. s._.,.
.,..,. ew..,,.. : _.,._.., v. e. s.,,, 4 2,.. :........ec
_4
.. v
.m o d er safety conce =s da: warranted additional short-te= design and precedural cha.ces a: cperating facilities having S&W designed reac crs.
559119
}h
~
7590-31 These were identified as ite:.s (a) throo;h (e) en page 1-7 of the Cffice of Nuclear Reactor Regulation Status Repert to de Cc _issien of April 25, 1979.
Af ter a series of discussiens between the NRC staff and the licensees concerning pessible design modifications and charges in operating pro-cedures, the licensees agreed in letters dated April 27 and May 4,1979, to implement preeptly the following actions:
(a) Review all ascects of the safety grade auxiliary feedwater system to furter upgrade ecmpenents f:r added reliability, and perfe.cance.
Present modifications will include the additien of dpamic braking cn the auxiliary feedpe:r.p turbine speed changer and previsien of =eans f:r centrol
. =. =.
rocm verification of de auxilia.f feedwater flew to the steam generators. "his means of verificatien will be provided for one steam generater prior to startup frca de present rainterance cutage and for de other steam generat:r as soon as verder-supplied eqcipment is available (esti ated date is June 1, 1979).
In addition, the lice. sees vill review and verify de adegaacy of the auxilisry feedwater system capacity.
(b)
Revise cperating precedures as necessarf te elimirate de cetien of usirq de ~ntegrated Centrol System as a backup cuans fer centrelling auxi'iarf feedwate r f' cw.
d d s).L fw
7590-01 um (c)
I=ple ent a hard-vired control-grade reactor trip that would F/,y77 be a-m* u en loss of =ain feeNater and/or turbine trip.
(d)
Ca:plete aralyses for potential mall breaks aM develop and i=lenent eparating instructices to define operator action.
All licensed reactor cperators and senior reacter operators (e) vill have cocplete:! the "hree M.ile Island Unit No. 2 si=clater trainirs at B&W.
(f)
Seinit a reevaluation of de 500 aralysis of the need for autxatic or aininistrative centrol of steam generater level setpcints during auxiliary feedwater system e-
.i:icn, previcusly subnitted
5=
by 5:00 letter cf rece=ber 22, 1973, in light cf the "hree
..ile Islard Unit No. 2 incident.
w S/'/ II (g)
Subtit a review of de previcus "'ICO evaluation of the September 24, 1977 event i:volving eg.:ipnent probless and depress-urizatien cf de pri=a y systec at Davis-Gesse 1 in light of the "hree F.ile !.slarri Unit No. 2 incident.
In its letters the lice. sees als: stated dat the actiens listed in (a) through (g) above.culd, except as reted in itec (a), be ccepleted prior to star u: fra:
2e curr:ne. rainterance cetage.
a O d d _A.fs A
, In addi-ion to these cedifications to be implemented Freeptly, the licensees have also prepesed to carry cut certain additional icng-tera :nodifications to further etance the capability and reliability of the reactor to re-spend to various transient events.
2ese are:
- te licensees will continue to review perfomance of the auxiliary feed-water syste= for assurance of reliability and perfocance.
- Se lice. sees vill sdcit a failure ecde and effects analysis of 5.e ICS to de NR" staff as socn as practicable.
"he licensees stated that dis a:ulysis is nov tmderway with high priority by
- er.
- Se react:r trip follevi.9 less of main feedwater and/or trip of the turbine to be installed premptly pursuant to this Order T.==.-
will thereafter be upgraded so dat $d c:ma::nents are safety grade.
"he lice:. sees -ill subcit this design to de EC staff for
_7 view.
- Ccatinued attention wi'1 be given to transient analysis and procedures for =a age ent of s all breaks.
"he licensees vill centinue reacter cperater training and drilliry cf rescense procedures to assure a high state of preparedness.
e m.m.
003.12.,2
. ~..
l 7590-01
. %. =...
V.$ ~!!..
'2.'
W.e Cc:=issien has concluded that the prompt actions set forth as (a) through (g) above are necessary to provide added reliability to de reactor system to respend safely to feedwater transients and should be confir=ed by a Coc=issien crder.
"'he Coc=issien finds that cperatien of Davis-Besse 1 should rot be re-su=ed until the actiens descr ted in paragraphs (a) through (g) above, with the exception as noted in item (a), nave been satisfactorily completed.
For the foregeing reasens, the Cennissien has found that the public health, safety arx! interest recuire that this Order be effective i.=edi-ately.
Copies of de following doc =ents are available for inspection at the Cc =ission's ?dlic Dec=nent _ Roc = at 1717 H Street, N.W., Warr.'igten, D.C.
20555, and are being placed in de Cc:=issi:n's local public doc =ent roem in the Ida Rupp Pelic Library, 310 Madisen Street, Port Clinten, Chio 43452:
(1)
Cffice of Nuclear Reacter Regulation Status Recer en Feedwater "'ran.sients in 3&W Plants, A:ril 25, 1979.
Q O v.s.t a
m (2)
Letters frec Lowell E. Rce (TECO) to Farold Centen FnR) dated
. =... -
April 27 and May 4, 1979.
(
IV.
Acccrdingly, pursuant to the Atocic Energy Act of 1954, as a: ended, and the Cecedssien's Rules and Regulations in 10 CR Parts 2 and 50, IT IS r--en e= v. CG.a..r: e D s. s-s.
(1)
"he licensees s'," *=ke de f=110 wing actions vid rescect to Davis-
= esse 1:
(a)
Review all aspects of the safety grade auxiliary fes2ter c. a as n..,:.+ n.z.y s
g.;g..
asu..s.g u ~.m.,;.
..~e..
... a and perfor=a.ce.
Present modifications will include the additica cf dynamic braking cn Se auxiliarf feedpe:.; turbine speed changer and erevisien of means f:: centrol reem veri-ficatien of the auxiliary feed-2ter flew :: de steam generatcrs.
n....: g a., g o. y e. : : : ~.~..<., y..,., y,
~.a.s a
.c..
- n.. a.
- g.. n..
c a
e..
generator prior to startup from the present =ainte.ance cutac.e and for the eder steam generater as seen as vender-su plied egai; ment is available (esti:ated date is Jr..e 1,1979).
In addition, the licensees will review and ve.rify the adeg,.:scy of the auxiliary feedwnter system ca:acity.
(b)
Revise c erating precedures as necessarf tc eliminate de epti n of using de Integrated C:ntr:1 Systec as a backue means for cont lling de auxiliarf feecwater sys.__...
559124
(c)
I=plement a lurd-ired centrol-grade reactor trip that would be acttated en I ss of rain feedater and/or turbine trip.
(d)
Coc:plete analyses for potential s:all breaks and develop and i=plement operating instructiens to define operator action.
(e)
All licensed reacter operaters and senior reactor operators wil.1 have ec cleted the Taree Mile Islanf Unit No. 2 sir.ulater trainirq at B&W.
(f)
Scheit a reevaluation of the ~ECO a:alysis of the need for autocatic cr ad:ninistrative centrol of stea. generater level setpoints durits auxiliary feedwater system cperatien previously
" ~ ~ ~
sdcitted by TECO letter dated Cece6er 22, 2 978, in light of the
?.ree Mile Isla.M So. 2 incident.
(g)
Succit a review cf the previces ~~'CO evaluation of the Septe.ber 24, 1977 event involving equi,=ent pr:ble-s and depressurization cf the p-irary syste: at Oavis-Sesse 1 in licht of the "hree Mile Isla.t Unit No. 2 incident.
(2) The licensees shall raintain Davis-Besse 1 in a shutdewn cendition until itec:s (a) drou:h (g) in paragraco (1), except as noted in itec (a), abcv are satisfact rily ec leted. Satisfact:rf czpletien will recuire ecnfi ration by de Director, Office of Nuclear Peact:r Regulation, tnat me d d d.L N d
7590-01.
actions rpecified have been taken, the specified analyses
- v. -
are acceptable, and the specified implementi.g procedures are apcropriate.
(3)
The licensees shall as prceptly as practicable also accx.plish the long-ters ::cdifications set forth in Section II of this Order 4..
V.
Within twenty (20) days of the date of this Order, the licersees or any _
persen whose interest may be affe::ed by this Order may request a hearing with resce:: to this Order.
Any such request shall not stay the i ::ediate effectiveness of this Order.
r7 "5E h"JCJ' AR REGUMSEY CCMe.IS3ICt; if
,. <. s/ '
( (6, 2 L Samuel J. O,j.1k Secretary of the Cc==ission Dated a'U day ei Fay 1979 nim :en, D.C.,
e-
=is 16 e
559128