ML19346A028
| ML19346A028 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/29/1981 |
| From: | Gallo J ISHAM, LINCOLN & BEALE |
| To: | Semmel H ANTIOCH SCHOOL OF LAW, WASHINGTON, DC |
| References | |
| ISSUANCES-OLA, NUDOCS 8106040398 | |
| Download: ML19346A028 (4) | |
Text
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ISHAM, LINCOLN & BEALE COUNSELCRS AT LAW 1920 CONN ECTICUT AViNUC, N W, Sueft 325 WA S HINGTON. O. C. 200 36 ftLEPNONE 202 833*9730 cwecAco arrect CNC rimat =AfioNAL PLAZA May 29, 1981 e,',c",%','*u "*.'. o."o2 NIOIb f r 6cP=ONc si2 ess-,soo
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Herbert Semmel, Esquire y
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- O Urban Law Institute ~
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%me,D' t-% u., Mr;D% - l Antioch School of Law A
2633 16th Street, N.W.
\\g Washington, D.C.
20036 g,
.U die RE:
In the Matter of Consumers Power Company (Bi'gt-Rock Point Nuclear Power Plant), Docket No.
50-155-OLA (Spent Fuel Fool Expansion)
Dear Mr. Semmel:
On May 19, 1981, I sent you' Consumer Power Com-pany's responses to your clients' General Interrogatories 1-5.
On page 17 of that response, it was indicated that two documents would ba provided under separate cover, namely, an LER for Oyster Creek and the NRC Staff Assessment of Amendment Number 30 to the Big Rock Point Operating License.
The so-called LER or Licensee Event Report for Oyster Creek is an erroneous identification.
The correct reference is an " Abnormal Occurrence Event; Indication of Low Water Level in a Boiling. Water Reactor," found in 44 Fed. Reg. 50925, dated August 30, 1979.
This Federal Register notice and the NRC Staff Assessment of Amendment Number 30 are enclosed.
Please call if you have any questions.
Sincerely,
/ JosephrGallo One of the Attorneys for Consumers Power Company 0
Enclosures l
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cc: Big Rock Point Service List l
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2 N%1 Ite:: islet / Vo!. 44 flo.170 / Thursday. Au;ust 20.10 0 / !!r.h:
- dsys, wlU bo held at the Federal Judicial anclysis of the substanco determined it described *calow. Chilar c:r: ar.1:a to be sodium bydro:dda. As a result of also institutad at VEFCO'o Ncrth m.:a Conter 1520 H Street.N.W.
Tha meeting will deal with the work this analysts and the uncartsinty of the Power Statics.
and role of courts of limited lurisdiction, extent of dama< s., the licensee is NRC-An TCCIE Security In:;mact trends in the volume and mix of tort returning all th :ssemolies to the was dispatched to the sito cal.hy O.
cases in federst and acate courts, and vendor for teidsishment.The licensee 1070. AdditionsHy. t'.'e Reaion II Sanior deternuned that there were no Investigator, ths ?.egion 11 Security teform efforts aimed at incrassing Indicatione of damage to the spent fuel.
Section Chief and a llealth Phyc!cs f
ocr. ass to courts for resolving disputes.
The meeting will be open to the public, nor was there evidenca of unauthorized Inspector were canita to ess!:t the ICC i
and nunutes of the proceedings will be individuals gaining access to the vital
. Recident inspector end to provids onsita area.
assistance to the FD!. NRC IE Security made available upon request.
Fuel se the Surry site is stored in the Inspectors have ekamined tha corrective Additionalinformation may be Fuel Duildmg. an area which is locked Utsmed from Mr. C. Ronald E111caton.
and alarmed, and to which access is Y
g fic f r im t in th NRCIE Information Nouca No.70-ta dm trati n oflu tics. Uni ed States controlled by the use of specially coded
" Attempted Damage to l'aw Fuel Department of lustice, Washington, D.C.
. act.i sa cards. Authort:ed indivicasts.
wiu are permatted access to the Fuel Assemblies" was lasued on f.!ay L,.
20s30' Telephone (:02) 633-3593.
Eudding using the specisily coded 1970, to ciert all NRClicensees uno
"*"Y ^*8'*"* "
- becess cards, are afforded unimpeded store new fuel assemblics of th!s Adamistratoc. rederal/ustice Research access to both the new and spent fuel.
prob!cm.
Progrwn.
Since normally conducted inspections NRC IE Dulletin No. 70-10. " Vital At:s o c.a rs. coa ni.4 ews so.at by the licensee detected the damage to Access Controla" was is:ued on July 7.3, s m.o cocaseie.ei."
the new fuel. there is litt!a chance that 1970 to require specific actions by ths these assembhes-damagsd in this licensces. including a repcrt by IJUCL2AT4 REGULATORY f[Yy
'fje#
September 9.1970 of actions taken and q,nces C0.:t.11SSION uf this incident had no cifect on the pisnned.
pubhc health and esiety, the incident Dated at Washington. D.C (his ::J day of Abnormal Occurrones Event; Damage did represent a potential threat an that it August 13 0.
telia.v Fuci Assemblies occurred within a vital ares where For the thc! car Regulatory Co=unission.
Section :08 of the EncruY sabotage te ' wh new fuel and spent fuel 84*"*3I Reorgaruzation Act of 1974. as urnended.
was puanble.
requ res the NRC tu disseminate Cause ur Causes-The cause was an Secrcroryof the Commission.
mformation on abnormal oct."rrence9 alleged i.nmmul act. On May 7.1970. the tili c.a r> iu ni.4 waam s o.mi il 4., unscheduled inudents or events in enwe nut.fied the FCI of the damago cur:o cces tswei-u w hich the Commisuun determmes ar" to the new fuel. The FD1 conducted an sigmficant from the =tandpomt nf publ.c m c imation wluch culmmatedin two health amt. safety). The followmq pl.mt worke ni wrreadermg to Surry Abnorm.1 Occurrenca Event; t:.nmt, authorittes un lune 10.1979. A Int.*! cation of Low Watcr LQvolta a incident wVs deterimned to be nn v
ubnormal occurrem e using the i t'teria c.oni piry hearma was beid in Surry.
Dot!!nD Water Reactor pubbened in the Federal Regislar on Voguna on j alv u. tu?9. triot is February 24.1977 (4 FR tuMt.
to be.e.l.d for Ontole r 10-12.1970. The Section ca of the Enen;y Rentgomtation Act of 1974. as amended.
Appendia A (Examplu I C2) of th" mo wo6 lier =. ande r.sdwe from their Policy Statement notre that a
..iin,.iry h.ne ri fus. d tu denrnbe the reqmres the NRC to disseminate.
substantiated case of actual or deiadu..I the safrey issues whia h information on abnnrmal occurrences attempted * *
- sabotage of a fariht) rrp.ir%hh moinated them in commit (i c.. unscheduled incidents or events can be considered an ubnormai the.u.tS.
whir.h the Commission determines are occurrence. The followmg description of
.h trons ra4cn tu Prevent /lecurreur.e a:gmficant fri.m the steadpoint of pubh ;
the esent also contune the remedial Lu. nsce-As a result of the incident, health and s(fety).The fo!!owing incident was deiermmed to be an actions taken.
and ta assist the Fill m its investigation.
Date and Ploce-On May 7.1979, the it.e bcensre considerably reduced the abnormal occurrence usma the cribria NRC Resident Inspector at the Sur y number of people permitted access to published in the Feders! Re ;! stir on Power Station was notified by the the Fuel Budd ng and stationed a February 24.1977 (42 FR 10%a).
licensee (Virgmia Electric and Power secusity guard mside se Fuel Duildia.g Appendix A(ExampleII.A.1)of the Company-VEPCO) that whde to venfy access authoruation. These Policy Statement notes that exceeding a conductmg inspections of new fuel for were prompt temporary actions. The safety limit oflicense Technical Umt :it was found that 62 of 64 licensee has completed a thorough Specifications. (10 CFR 50.30(c)) c:n ba ass.elies were coated with a white review of their access control program.
cons dered an abnormal occurrence. Tha crystalline substance. Surry Units 1 and and one now more selcative in followin8 escription of the event clso d
- are pressurued water nuclear power determinmg whether uriescorted access contains the remedial actions tahn.
plants located iri Surry County, Vltginia. should be provided. The licensee has
.Vature crad Probahre Consequences-made the Supertatendent of Date andPlace-On t.Isy 2. tD7D. the.
On May 7.1979. E. ale conductisfg Admmistrative Services responsible for NRC was nottlied by the licenceo (Drsey routine inspecticas of new fuel. the coordmating corrective actions. imd to Central Power and I.fght Camp:ny) of hcensee discovesed that a foreign ensure that weaknesses are corrected an event at their Oystt.r Crcok facility.
sabstance had been poured onto 62 of even if noted by someone, not normally The Oyster Creek Nuc!est Plant utili: s I
the 64 new fuel assemblies stored in the responsible for that particdar a boiling water reactor end is located in contains both new and spent fuel. An are consistent with the NRC :E Dulletin h
Fuel Budding. a vital area which professional discipline. These actions Ocean County, New Jersey.
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Fedcral Redster / vol. n No. m / Theday. Ausst 2. g.,],p::
2 C,*3 feedwater transient. Animmediate
. on the outemad: depressuri:st::a.
fJatura and Probable Consequenssa attempt to restart the1A foedwater.
system cnd alat=s in Qs esstroirccs Summary '
pump. powered by the live 41c0v bus to c!stt the operater.
Aloss of feedwater transient st'the (1A). was t= successful becausa of
%e tr:pla-lowIcVelin the c:ro cht ud
' Oysm-Creek facility on May ?. im, failure of an auxillary oil pump to start-area resulted from the restrictica cl Ga Y resu ted in a signiacant reduction in The lube oil pump is intericekod in the Cow path betwean the annulus ned the j
water inventory above the reactor core feedpump start sequencs.%12 was the
. core re; ion by closure of all area os measured by one set of water only equipment fadure during the recirculation pump dischcr;;o valves.
With the recirculation pump di:charcs level lastruments (triple-fow level).
waile the remaining two sets oflevel-Subsequent to the rt;1ctor scram.
valycs closed (dischargs'pi is over :,
lastrumentation in the reactor annujus reactor waterinventory initially feet in diameter), the only w pad I
Indicated waterlevels above anY decreased due to steam flow through the back to tha coro re;; ion was via ths 2 protective feature setpoint (Figure 1).
turbine bypess valves to the main inch bypt.ss (Inca cround the dischatc2 The waterlevel ruessured witnan the condenser.This lose together with the valves, no efket of this flow restrictica core shroud area fell below the triple-void collapse associated with decreased was to reduce the water levelin the core low level setpoint. a safety limit of S.
temperature of the cora inlet coelant and region and to increase the level la the feet. 0-inches above the top of the fuel.
the subsequent loss of feed Cow, reactor annulus cres.
Subsequent analyses by the license
- resulted in a rapid reactor water level Reactor prc:sure was controlled by have conservatively determined that the reduction to the low water level alarm intermittent c=1.us! oper: tion of the two minimum waterlevel over the top of the setpoint of 11. feet. 5-inches above the isolation condenscrs. At cbout half an fuel was 1 to 1% feet. Coolant sample top of the fuel at 13.0 seconds.The Mur into the transient a rceirculation analyses and offgss release ret s operator manually 1,aitiated closure of pump was started.Ro operator tripped all main steam line isolation valves the recircu!stica pump witida : minutes support t a conc usion t at no e
damage occurre (MSIV) at about 43 seconds into the when he noted a rapid decrease in tho
- transient to conserve wat:r.Tho -
annulas ! cycl (th: rt:freu!ation pumps Sequence o/ Events mmimura indicated water levelin the tako suction from the annulds). About 5 Oyster Creek is a non.iet pump BWR, annulus was Meet Mnches abon de tainutos later, a fecdpump was started, with a licensed power of 1930 MWt.
top of the fuel (the low. low setpoint is 7*
At about 40 minutes into tho event, a.
immediately prior to the transient the feet 24nches abou de top oMo fu0 prima'ry recirculation pump and n' reactor was operatmg at 98 T, power After closure of the MStV. ca isolation reactor feedpump were restcrted for with the reactor vessel water level at 13 cundenser was manually placed in continued cooldown of the reactor. From t
feet. 4 inches above the top of the fuel.
service for core decay heat removal.The about 40 minutcs onward, tha water The "D" reactor recirculation loop was asuiation condenser was condensin3 level within tha core region was normol.
out of. service because of a rectreulation steam from the core and returning the The plant ottoined cold shutdown pump seal coo ct problem and the "S~
condensate to the reactor annulus condition within 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
startup transformer was out-of. service through a connection to a recirculation Rcview of the occurrcnco by the for inspection of the ossociated 4100 vult
.oop pump suction line (Figure 1). At licensco and NRC cstablir.hed that cabling.
approsimately a mmute and a quarter although the water levelin the coro The mitiating event was a falso high afier the reactor scram, the discharge shroud area went below the triple low reactor pressure scram. The pressure valuce m A and C recirculation level setpoint, the core remained
/ spike that led to the scrum signal was loups were closed m accordance wisl covered and consequently no fuct generated by the way on mstrument Standmg Order that was in effecf damage would be ex'pected.
technician was performing surveillance Clummg the A and C loop discharig P
testing on isolation condenser pressure valves hW been necessary to prevent hi h pressure scrom was instinted by a switches.The signal resulted in a C
simultaneous reactor scram and the madwtent stoppmg of the isolation c.
e oc curtanser due to forced flow item lss trippmg of all operatmg recirculation operatmg recirculation pumps being g
4 Pg 8
pumps. The titppmg of all operating sensed as if it were on isolation.
surveillance testing. tiowever, the j
rectrculation pumps is a safeguard to condenser line break. (This Standing fundamentar causes of the tesulting mitigate the consequences of anticipated. transients.without scram Order was no longer appropriate since sequence of events were:
an ATWS modification had been made (1) That operators essentially !solated Thirteen seconds after the reactor that tripped the rectreu!ation pumps the reactor annulus and core region from f
events.
scram. the turbine tripped at the low comcident with high pressure or low.
each other by shutting a!! recirculation I
load setpoint. The turbine trip initiated a le<el scrams.The necessary procedure transfer of power from the e'ouliary change had not been performed pump discharge valves.
a i
transformers to thy startup transformers. following the plant modifica* ton.) At the (2) Notes or Cottons against closing Because one startup transformer "SB" same time. the "D" and "C" loop all mction and discharge valves in the l
was out of service, two feedpumps and discharge valves were apparently rectreulados loops were not adequat<
two condensate pumps (pumps 18 and closed, m anticipation of restarting the Adons & MunWerence i
IC) on the associated 4100v bus (2D) lost recirculatfon pumps.The "D" loop power. The third feedpump (1A) tripped discharge valve had been closed prior to L/censee-The licensee performed a thorough evaluation of the event to due to low suction pressure during the the evsnt because the as:ociated pump determine whether any fuel damage had '
was out of service.
' n non.i.i pump owlt is ot aa.laer desisn.
The reactor triple low water level (5-occurred and developed fo!!aw up t.6-inches above the top of the fuel) actions. As a result of the evaluation Io*r~p"r I.".EUEN "o$t n$* ** W 'tpotnt was reached at 17: seconds and discussions with the NRC, the se ruusulauen e into the transient. The triple low level licensee took the following sigruficant concepi red.cne. performance. ra i.i pump m
dih numbereiesiernalcootent recirculsuaa loope to two.
setpoint activates one of the permissives actions;cs l
P00R D M M
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.._.c Federd Red. ster / Vol. 41. No.170 / T!!ursday. Au:;nst 1:D.1G70 / Notices.
,_L... S 1.The triple. low level was estab!Ished Cooperative and located in Monroe i
as a Safety Limit for all modes of reactor County, Wisconsin) are the only op.; ration.*
, reactors presently operating which are a A requirement was added to the suaceptible to e simdat event.
. Technic.al Specifications that the suction Imnedfate requirements si.nilar to those and disd.aese valves in at least two which were required for Oyster Creek
.i recirculevoa loops be open at all times.
(Te.hnical Specification changes 1 and The procedures were changed to
- 2) were implemented at these facilities f
implement this requirement.
prior to their start.up (they were both in
- 3. Operator training sessions were a shutdown condition at the time of the held the event was thoroughly Oyster Creek event).The third
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discussed and the revised procedures requiremest willbe implemented as reviewed.
soon as practicable.
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NRC-Following notification from the Two other plants (Dresden Unit 1 and f
licensee of the event, an NRC inspector Dig Rock Point), which are presently in E
was dispatched to the site. Additional extended shutdowns, would also be NRC personnel arrived at the site on susceptible to a simdar.svexit. However.
May 3.1979 to review the situation and it is planned to impose appropnate determine the status of the plant. Fact requirements on thest ?ro plants prior f
finding by the NRC was supplemented to their startup.
by information obtained from the In addition. on May 23.1979 the NRC licensee, the reactor vendor (General issued IE Information Notice No. 79-13.
Electrict and fuelsupplier(Exxon). A -
detailing this esent, to all holders of 5
safety evaluation report (SER) of the operating licen:es and construction event was prepared which discusses the mimmum water level experienced in the pennits.
Dated at Washuiston. D.C. this ::nd day of reactor vessel and the fuel conditions.
Avaa.: 19,3 tlc following three requirements wery For tite Lcl var Regul.atory Commission.
addel to the Technical Specifications:
- 1. T he triple low level was made a Samuel [. Chuk.
Safety Limit for all mode. switch Srwturr ut the comm.ssion.
l positions.
e ws.ococerseeoi4s 1 At least twr recarculation loop l
discharge and suction valves must rematn in the full open position.
- 3. The time duration of the low law level signal was required to be not greater than that used in tha safety analysis for the limiting lossof.
inventory transient.
The NRC staf.f also :ecommended that the licensee consider the surveillance
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prograrn and level instrument improvements.
It wa concluded that no evidence of fuel damage was apparern. and that the facilty could be safely returned to operation.
Based on t!'e satisfactory actions taken by the licensee, on May 30,1979 the NRC authonzed the licensee to resume operation.
l The possible generic luolications of the Oyster Creek event have been
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considered. Nine Mde oint Unit 1 c
(operated by Siagara N.'ohawk Power l
Corporation and located b Oswego County. New York) and I Zrosse i
(operated by Dalrylarl Power g
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' At the uma of tb event. the licensee's technacal j
g a
.l specincations deflaed the tnple-law weter level as e Sacrty tanut what the reactor mode switch wee na lJ the "sHttrDOWN" mode only. A ilauting safety i
sysaem settins was also associated wnh the double
- tow water level whos the mode switch was in the
.rRU.N" posiuca. Even thouah the mode swuch had been placed La the RErVE1.* posinon by the operator shortly after tattisson of the transient, the l
event wee rosarded by tne hcenese as if a Safety Limit had been violate:L 9
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
1 WASHWCTON, D. C. 20555 October 30, 1979 VFD
..v V 5lg79 Docket No. 50-155
.,UCLEAR LICENSING TGpr:nr1 pr p Mr. David Bixel Nuclear Licensing Administrator iET2I.? 19 8 Consumers Power Company w __
a 212 West Michigan Avenue L.JL M LS U V Lbl b Jackson, Michigan 49201
Dear Mr. Bixel:
The Commission has issued the enclosed Amendment No. 30 to Facility Operating License No. DPR-6 for the Big Rock Point Plant.
This amendment consists of changes to the Technical Specifications in response to your request dated September 28, 1979.
This amendment incorporates in the Technical Specifications restrictions to reduce the likelihood of uncovering the reactor core during certain plant conditions.
Copies of our related Safety Evaluation and Notice of Issuance also are enclosed.
Sincerely, f
A r-Dennis L. Ziemann, Chief Operating Reactors Branch !2
. Division of Operating Reactors Enclosdres:
i.
Amendment No. 30 to License No. DPR-6 2.
Safety Evaluation 3.
Notice cc w/ enclosures:
See next page
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DCCC75"i CONTF.0!. CENTO C'" ***
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Mr. David Bixel October 30, 1979 0
cc w/ enclosures:
Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Pcwer Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
EIS COORDINATOR Judd L. Bacon, Esquire 230 Scuth Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Hunton & Williams George C. Freeman, Jr., Esquire P. O. Box 1535 Richmond, Virginia 23212 Peter W. Steketee, Esquire 505 Peoples Building Grand Rapids, Michigan 49503 Sheldon, Harmon, Roisman and Weiss 1725 I Street, N. W.
Suite 506 Washington, D. C.
20006 Ar. John O'Neill, II Route 2, Box 44 Maple City, Michigan 49664 Charlevoix Public Library 107 Clinton Street Charlevoix, Michigan 49720 Chairman County Board of Supervisors Charlevoix County Charlevoix, Michigan 49720
- 0ffice of the Governor (2)
Room 1 - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment Division Office of Radiation Programs
( AW-459)
U. S. Environmental Protection l
Agency l
Crystal Mall #2 l
Arlington, Virginia 20460
- w/cy of CPCo filing dtd. 9/28/79
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UNITED STATES O
NUCLEAR REGULATORY COM, MISSION o
WASHINGTON, D. C. 20658
- s...... e CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. DPR-6 1.. The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated Septa ber 28, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth
- a 10 CFR Chapter I; O.
The facility will operate in conformity with the application, 8.
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (f) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Apper.aix A, as revised through Amendment No. 30, are bareby incorporated in the license. The licensee sh411 operate the facility in accordance with the Technical Specifications.
3 This license amendment is effective as of the date of its issuance.
FOR THE tUCLEAR REGULATORY C0iMISSION dh ?!-s\\ 9 Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors O.1
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1979 N
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ATTACiMENT'TO ' LICENSE AMENDMENT', O. R
- ' FACILITY ' OPERATING ' LICENSE 'NO. 'DPR-6
' DOCKET 'NO. '50-155 Revise Appendix A Technical Specifications by removing pages 4-3 and 4-6 and inserting the enclosed pages 4-3 and 4-6, These revised pages include the captioned amendment number and contain a vertical line indicating the area of change, 6
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~.,1!1(Contd) 4 (i) Operating Requirenents 1.
The average rate of vessel temperature change during normal O
heatup or cooldown should not exceed 100*F/h when averaged over a one-hour perind.
2.
Control rod withdrawal during power operation shall be such that the average rate-of-change of reactor power is less than 50 MW less than 20 MW.t per minute when power is less than 120 MW '
t per minute when power is between 120 MWt and 200 MW, and 10 MW. per minute when power is between t
t 200 MWt and 240 MW '
t 3.
Reactor vessel pressure shall be limited in accordance with Figure 4.1.
4.
The reactor shall not be made critical, with the exception of physics testing, at temperatures below the criticality limit shown on Figure 4.1.
5.
The reactor water level shall not be permitted to decrease below the reactor vessel low water level set point. at which reactor safety systems are actuated (Section 6.1.2) whenever fuel is in the reactor vessel.
This requirenent shall be considered a safety limit and decreases in reactor vessel water level below this set point shall be subject to the requirements of Section 10, Administrative Controls, Sub-section 6.7, " Safety Limit Violation."
O2 eri rx ceei #t aecircei tie svst,
The primary coolant recirculation systen shall consist of the reactc< vessel, the steam drum, the reactor recirculation pumps, the interconnecting piping and valves, and the safety relief valves.
(a) 'Desian ' Features Shall Be 'as Follows:
Number of Recirculation Loops 2
Number of Recirculation Pumps per Loop 1
Approximate Internal Volume of 3830 Systen Excluding Reactor Core and Internals to Isolation Valves, Cubic Feet i
Approximate Volume of Coolant in 2689 System During 157 Mwt Operation, Cubic Feet l
' Steam' Drum:
l Length, Overall, Feet 40 Inside Diameter, Inches 78 Wall Thickness, Exclur'.ing Cladding, 4-3/8 i
Inches Cladding Thickness, Minimum, Inches 5/32 Design Pressure, Psia 1700 Design Temperature, *F 650
4.'l.2(Contd)
Minimum T'ime To Put Systen 30 in Full Operation-Following O
Signal, Seconds Core Spray Systen:
Type Sparger Ring With Spray Nozzle Capacity of Sprays, Gpm 400
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Nozzle Pressure, Psia 115
' Backup Care Soray System:
Type Sparger Nozzle Centered Over Core
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Capacity of Sparger, Gpn 470 Nozzle Pressure, Psfa 11 5
' Core Sor5y System Recirculation:
Number Pumps 2
Number Heat Exchanger 1
6 Heat Renoval Capacity, Btu /h 8 x 10 0 28.4*F Log Mean Temperature Difference (b) Operating Recuirenents A minimum of one reactor recirculating loop shall be used during all reactor power operations (ie, recirculating pump suction valve and 20" discharge valve shall renain open and pump shall be running). The maximum operating pressure and tsuoerature shall be the same as the reactor vessel.
The controlled rate of change of tenperature in the reactor vessel shall be limited to 100*F per hour. All other components in the system shall be capable of following this temperature change rate.
The safety relief valves hall be set appropriately for all planned reactor s
operating pressures so that the allowable pressure of 1870 psia (1700 plus 10%) in the nuclear steam supply systen is no: exceeded.
The energency condenser shall be operable and ready for service at all times during power operation.
However, should one energency condenser tube bundle develop a leak during power operation, it will be permissible to isolate the leaking tube bundle until the next outage, Both bundles of the energency condenser shall ':e available for service during cold to hot plant heatup for power production.
The shutdown cooling systen shall be ready for service during power operations with the 480 volt circuit breakers for isolation valves MO-7056, M0-7057, MO-7058 and M0-7059 checked "open" when reactor pressure is above 300 osig.
The shutdown cooling systen shall be operable and ready for service during refueling operations and the breakers for M0-7070 and MO-7071 shall be tagged "open".
The primary coolant shall be sampled I
and analyzed daily during Amencment !d')(.,h J,30 4-6 Change No. '
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UNITED STATES 8
NUCLEAR REGULATORY COMr.ilSSION i
I WASHINGTON, D. C. 20S55 O"p*...*/
s SAFETY EVALUATION BY THE '0FFICE'0F NUCLEAR ' REACTOR ~ REGULATION SUPPORTING AMENDMENT NO. 30 TO FACILITY OPERATING LICENSE NO. 'OPR-6 CONSUMERS PONER CCNPANY BIG' ROCK POINT DOCKET NO. 50-155 1.'O INTRODUCTION By letter dated September 28, 1979, Consumers Power Company (CPC)
(the licensee) requested changes to the Technical Specifications for-
,the Big Rock Point Plant.
The proposed changes would add restrictions to reduce the likelihood of uncovering the reactor core during certain plant conditions.
The proposed changes are in response to an abnormal occurrence event report related to the Oyster Creek Nuclear Plant (Federal Register, Volume 44, No.170, August 30, 1979).
h 2.0 DISCUSSION AND EVALUATION On May 2,1979, a loss of feedwater event occurred at Oyster Creek Nuclear Generating Station, which resulted in a significant reduction of water inventory above the reactor core.
We detennined during our review of the event at Oyster Creek that four other boiling water reactors, including Big Rock Point would be susceptible to a similar event.
Big Rock was in an extended shutdown at the time of the Oyster Creek event and we stated in the' Federal' Register notice noted above, that we would impose appropriate requirements on Big Rock Point prior to its startup.
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l We identified two additional Technical Specification requirenents appropriate for Big Rock Point.
These are:
(1) a Technical Specification on the minimum number of non-isolated forced circulation loops is required, and (2) a reactor water level safety limit Technical Specification must be established.
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The event at Oyster Creek resulted in a substantial decrease in core water level because of partial isolation of all recirculation lines during the transient, The major concern which arose fran tnis event is that the reactor core 'could be effectively isolated from its source of reactor coolant, the annulus region.
Therefore, because of the desfgn similarities between Oyster Creek and Big Rock Point, we have concluded that a Technical Specification on the minim'gm number of non-isolated recirculation loops is required to assure adeouate comunication between the core and annulus regions. We have reviewed analyses of natural circulation through loops similar to those of Big Rock Point and have also evaluated the specific recirculation loop and reactor vessel internals configurations.
Based on'these evaluations, we have concluded that one open loop will provide adequate comunication between core and annulus region. The requirenent for the non-isolation of one recirculation loop, under all conditions where possible depletion of core inventory may occur, has been incor-parated into the Technical Specification 4.1.2(b) on the above bases.
(This specification is in effect during reactor power. o.perations..which.
corresponds to all conditions where reactor core outlet tenperature is greater than 212*F,)
A second requirement is to establish a reactor vessel water level safety limit.
The licensee has specified actions which are aporopriate to safety limit violation in the event reactor vessel water level decreases below the safety systens set point.
This specified action reauires (1) an imediate shutdown, (2) notification to the USNRC, (3) a written report
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and (4) an NRC authorization before startup.
These requirements are specified in Section 10 of the plant Technical Specifications, Administrative Cor.trols, Subsection 6.7, Safety Limit Violation.
Based on the discussion above, we conclude that' the proposed changes to the Technical Specifications are appropriate requirenents and would reduce the likelihood of a significant reduction of water inventory a
above the reactor core, We, therefore, find the proposed changes acceptable, l
3.0 ENVIR0tNENTAL CONSIDERATION l
We have detennined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this detennination, we have further concluded that the amendment involves an action which is insignificagt fran the standpoint of environmental impact and pursuant to 10 CFR 251.5(d)(4) that an envirorrnental impact statenent or negative declaration and envirorrnental impact appraisal need not be prepared in connection with the issuance of this amendment, O
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4.0 CONCWSIONS We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the
- public,
.Date:
October 30, 1979 O
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,- l CONSUMERS POWER CWPANY
. NOTICE OF ISSUANCE OF AMENWENT'TO FACILITY OPERATING LICENSE i
The U. S. Nuclear Regulatory Commission (the Ccmission) has issued f
Amendment No. 30 to Facility Operati1g License No. DPR-6, issued to ConsumersPowerCompany(thelicensee),whichrevisedtheTechnical
. Specifications foi oporation of the Big Rock Point Plant (the facility) located in Charlevoix County, Michigan.
The amendment is effective as of its date of issuance.
' The amendment incorporates in the Technical Specifications a safety limit on reactor vessel low water level and restrictions requiring that a minimum of one reactor recirculating loop shall be used during all reactor power operations to reduce the likelihood of uncovering the reactor core during certain plant conditions.
The application for the amendment complies with the star;dards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Ccmission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment vras not required since the amendment does not involve a significant hazards consideration.
The Comission has detemined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR $51.5(d)(4) an environmental impact statement or negative declaration and environmen'al impact appraisal need not be prepared in connection with t
issuance of this amendment.
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7590-01 For further details with respect to this action, see (1) the application for amendment dsted September 28, 1979, (2) Anendment No. 30 to License Ho, DPR-6, and (3) the Carinission's related Safety Evaluation, All of these itens are available for public inspection at' the Camission's
' Public Document Room,1717 H Street N. W., Washington, D C, and at the Charlevoix Public Library,107 Clini:on Street, Charlevoix, Michigan 49720, A copy of itens (2) and (3) may be obtained upon request addressed to the U,' S. Nuclear Regulatory Consission, Washington, D, C.
- 20555, Attention:
Director, Division of Operating Reactors Dated at Bethesda, Maryland, this 30th day of October,1979.
FOR THE NUCLEAR REGULATORY CCMMISSION dh $ln 0
Richard D. Silver, Acting Chief Operating Reactors Branch 12 Division of Operating Reactors i
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