ML19346A105
| ML19346A105 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/14/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19346A102 | List: |
| References | |
| NUDOCS 8106050085 | |
| Download: ML19346A105 (7) | |
Text
.
(}~ [' c ua.
l
'o UNITED STATES 8
Il, NUCLEAR REGULATORY COMMISSION
{,*%
W ASHINGTON, D. C. 20555 y
CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that':
A.
The applications for amendment by Consumers Power Company (the licensee) dated February 4, and March 6,1981, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provi ions of the Act, and the rules and regulations of the Commissi C.
There is reasonable assurance (i) 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 common defense and security or to the health and safety of the public; and 4
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
'610 6 0 5 0 Di%
2.
Accordingly, the license is amended by changes to the Technical Specift:ations as indicated in the attachment to inis license amendment and paragraph 2.C(2) of Facility Operating License No. OPR-6 hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 43, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR HE NUCLEAR REGULATORY COMMISSION au-Dennis M. Crutchfield, en f
Operating Reactors Branch #S Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 14,1981 I
I
ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. DPR-6 1,
DOCKET NO. 50-155 i
Revise the Technical Specifications by removing the following pages and t-inserting the enclosed pages. These revised pages include the captioned 4
amendment number and contain a vertical line indicating the area of change.
)
l l
REMOVE INSERT 11-18 11-18 11-20 11-20 j
11-9 11-9
)
6-13 6-13 i
6-14 6-14 1
l
.I i
I 9
- c. uu.
t at e
s ut not a
- eh p
t ct n
en i <
L.
- r a t
s i b
e
+
v rt a + E.
l rt ee I t r
r t r
- gt L.
at.
s
- eehh hh e
ft m 6
r r
os pl t
t e
c ahdh c i
n e
- c. L wh a el 0 h
t ut t
e rii et rG u
el A sr o
oY
,ao s
o yr s
2 ek edl eigt
,d r
' r t nEl ns vi y t
t h gI n r l
5 aa rV r
s s n e h.
o e
l' e er e
a f
t ne t va d
d nerC aet. f riO yhl : n e l
e o3 i
u oaoI aea f 1 ct a a.
ees cwt t t
sl sai a
mri nat o1 hh n or i
a e
i.
t 1
s nrt l
l n
l ro et y
t.
- r. t
<n t r.
n1 suY p pa df l
o l
i n
l l t.
t r1 i e l ccl e yt g
u r.
u i
nrv aeh ee t
l l wl s h l
ah r
r o
r.
i n
t t
es m
n i
l h n eo l oaot eedit eut v c1 i a m e o. i e o a
p u
cti ch r eh cl cr nr L.
u ry%
pct et t t ni
- i. t t csit d
- aaed y
t p
v i
l u1 n n
ot t
t n
a i
t n
san o
n
)
i r
t n e
d r
e aoV aro
,syr u t snaa b'
el L cI it id n u
t m
t t
d mik moc skh o
- nom t p aa egnL eemwetl i n oi y
et pf e
n n
or of l cpi y l
mca snr h auo hh a
rr l i t
t d
r o
1 u
t 66 usn err ee et ooe t b s t t d l
een e
'l e
ur3 e i, l. d eh i
n nnt u
(
e y
ae aea c
ot t c c r i L.
i l.
p r
we c.
y et erst
. nl u td a h
l t
t i
enoou aol m an enner te i
s e
eih ert ernd a.
o b s h ncrb hiii h ayh guh e r I
E r
t, h pt h un h
l
- e. i l TL o t
l t i e
t o r
t t wn C
e t
t t oe t
t, t
t t ani c ron a
i s yp ss L f e
f v
a n o.
um e
i O
yot y
u yaamor y
oco yt smr yrpf ei s
t n
f se u
reuod
.I s
I n
l0 fi r r r.
fb c r i e.
fl l.
t t s yt r
t i
i ao i ae1 i
i l e t
et i
iot t.
t 3
eruG>u l
)
)
r a. n rws rdd nat rnet u.
rer
,h rt l
eaol h eel e h. tet e>n ennht u eir nt l
l Is S
et p
t i
E
(
(
V sl V pi V ainsb V mF as ais Vbt ut L L l
I Vt I
i e
W v
U r
)
)
)
)
)
)
u c
d e
r g'
h I
S Y
(
(
(
(
(
(
C NE G
t El M
I
)
S.
0 i
1 l.
1 1
1 1
e.
l gs l
rr c
l
- o. o a n us
)
i nay l
)
ne
, oht b
yvn a n t l n
bi g i
t t
i
(
l ro h o ol rv i
(
r n e pi siht ch si naa h s ua b et vcn a
n h. s p e l.
t h
st adDh c a. s i i a ae) wt ad pst esrai n
c l xt nthl r1 oi n
n c
y ar r
u wnu l esocwo t
( d wna urA l
o a
l, a o
ee w
pe anon w
.l 5
wh w) o) sl y h set erc m h.
et.) o) s r
p p u
3 o oud oeat snh cr o
, t nuad ar et
( u wu1 O
oh(
i ot a y
m d) d(
(
t n
s ev mi a
,r of s S.
t, S. h oo o
. S. t 5. l o
At 1 3
u
- e. i I o na non u
l y
u( t t f u
s1 i
l i
e nnwm e P. h 2.1s eb n t
e a rh u 2. h 2.1: ec sd ioi snti at t
b s
ud oseh s
u
)
o
,d r
iwt 1
3 2 i
t d
f -
ns1 1 2 ca yn oil d
h yl et l p p
n re
- 2. lyo d
e' so e
t e
ennngsr cnl l o d
S. d wl nnng t.
aLmc y
wb uoee t
uoaon t
O o
o r A rnb oaonn ii p
e C
th ei i
iiot rl oasch n A u d h l.
r
(
at sdhl t st wic eld r e
,ti h e. s t st w uyS o
r nrt l cr cot e t at ert a
nst crco rr
's S
er ooiaeuel ar t
up pnr o
areuel r e. in yi oS oSl et whS oSl rr arh oh eid i
E no i
s h
oea b esncc tl t t h
o t L s
C ef t t t
d n
nrp d
iixt g aricn nf nt d n
i g
a es n
i i I e
od nnd h el n cenai) l e
c meri) o l
i di e 2
e n
b oul uw ui l t i
r t o 2
e l
i u
l
, se r r rd1 dh udi oat d1 dh gu ol i
l S
ea t
oe e( et nr nice ( et oo t ec nneb l
f su l
i l
c al yeor e
b eb b
dic eg e
t ab b
d l
i r
s 3
se eaicieinl t b grki e
el hi ein i l n
E rvrieh saneat t e.
pal t rvri t
ue 4
o W
dd p,na C
O a
S.i cl ch nc rit t iht S ml cl ch I
l d
e :n esest ri eert d gs r ad sest l'
e t
i is 2
h e f eeiew eieh h puaedi y f oh newei gY Tb m
r nsadtd w Ol a 4
mbt dt d wr w Todbhams I
I C
i.
IJ f,
t i
t f
m G
3 Is S
6 7
i.
l
)
t E
1 1
o 2
N b
t 3
ne S.
m d
1 n
e 1
u A
1
ILeses:
Hommut station gewer can be provided by the ste: Lion t.urbine generator, the 138 kV transmi:.sion line or the le6 kV ilne.
These courcea un e adequate t.o provi.te emergency a-c gover. When none of these sources is available, a single energency diesel generator rated at 200 kW starts automatically to ps ovide einergency a-c gover to 180 V lheu 211.
The 6
1 weekly starting test, la based on Manufacturer's 15ulletin 337 :3-1 for relubrication protect.lon of w>ving parts. Diesel genetut.on init.lution und output circuit breaker closure is accomplished by two volt. age sensoru: One to detect, loss or normal tower on this 2Bi and, the othes-1.o provide nastirance of generator output prior to automatic closure of t.he generator out.put. breuker. Addit.ional breaker interlocks are provided to assure that the normal Duses I A und 2A une isolated prior to closing the generator output, breuker. This prevent,s overlonding or the genernt.or during t.he switching period.
The operability of the dieuel Inst.tery and charger is verified by t.he weekly starting tent. of the diesel und by the weekly veri fication of t.he electrolyte level and overall bat Lery voltage.
The diesel fuel oil tank in ulzed for ten-day t ull-load operation.Three-day supply is considered adequale to provide l'uel makeup.
A single utution bat.tery supplies lower for normal ct.ut.ioit services und is sized for emergen, y uses including valves anil controis of loss of Coolunt Accidents. The baLLery can be charged from the emergency diesel generator output, if normal slut.lon tower sources are not available.
The primary core sprny valves und the primary containment, spray valve are operut.ed und cont. rolled by gnawer from t.he ulution bat,tery.
Tlie backup core spray valves und leckup containment spray vulve are operat.ed by power from naimal stalloan power sources or t.he emergency diesel generat.or.
Itid uninterrupt,1ble lower supplies (tliU) A, B, C, ned D (each connist.ing of a bat.tery, bat.t.ery charger eind nn inverter) s.upply. each division (except, division 5) with electrical lower.
Each tilU has out.put.s of IPO V n-c, 60 !Iz, and 12's V d-c.
One of t.hese bat.teries supplies control power for t.he emergency diesel generator output breaker. Divisions 1 & 2 and 3 A 4 Erwilly receive power from 1:80 V a-c Buses IA and 2A, respect,1vely. In the event of lous of power t.o eit.her or tot.h bones, lucinded for supplying inrat power from 180 V n-c Ibss 2B which is t, led to t,he emergency diesel genes nator.
pro v i sion lu 6
Ir all 180 V a-c gover is lout, t.he BDS UlU is capable of sust.aining it.s output.s for one hour. The ut,at.lon buttery hau i
ade.pante capacity to carry normal loads plus an asstuned failure (locked rot.or current.) of t.he d-c lube oil pusup for 9 minutes without the battery charger and still provide sufficient lower for equipment, required t.o operate during a IDCA.
If steps are t.aken t.o reduce nonessential loads during a loss of off-sit.e lower (such as part, of the emergency light.0),
addit,lonal Liree (up t.o five hours) con be gained from the time of t.he loss of the charger unt il the but.t.e:ry would no longer have sufficient, gewei for equigenent. requi red t.o operate during a IDCA. The stat,lon bat,t.ery and the four (l ) lild i
letteries will be considered operable if they are essent.lally fully charged and the battery clearger is in service.
Addit.lunally, prior to the ut.artup following the 1977 rerueling outage, successrul completion or service t.est.ing and perfotmance discliarge test.ing within euch operating cycle and each uixty mont.hs, respect.tvely, will further establish lutt.ery ret labillty.
A ienenent tio.,#, 42, 43 11-20
_~ _
Tables 3.5.2.H 4.5.2.h Instrumentation That Initiates RDS Operation 3.5.2.H - Limiting Conditions for Operation 4.5.2.H - Surveillrace Requirement Protective Minimum Operable Conditions for Instrument Instrument Channel Parameter Channels Set Point Operability Trip Test Calibration Tri p l
Low Steam Drum 3
Above or Equal At Power Levels Monthly Each Major Level to 17" Below Whenever the Refueling Center Line Reactor Is (Tolerance Critical With Limit -5") ()) the Head On or When in Hot i
Shut'down l
Fire Pump (s) 3 105 psig i Ditto Monthly Each Major l
5 psig Refueling I
Low Reactor 3
? 2'9" Above Top Monthly Each Major Water Level of Active Fuel Refueling j
(Tolerance Limit
-1") (1) 120-Second 3
5120 Seconds Fol-Monthly Each Major Time Delay lowing Low Steam Refueling
{
Drum Level Signal Monthly Input Channels 3
l A Through D Output Channels 3
Monthly I Through IV Monthly Monthly i
Fire Pump Start 1
n OReference Specifications 3.1.4 and 4.1.4 for Bases.
j II) Level instrument set points shall be as.specified. Level instrument calibration shall be based on normal operating temperature (582'F) and pressure (1350 psia) and instrument reference leg temperature of 250 F or lower as measured to maintain an actual trip level greater than that assumed in accident analyses (2'8" above top of active fuel for reactor vessel level trips, and 25" below steam drum center line for RDS actuation). Set point drift between i
calibration checks within the specified tolerance limit shall be corrected but need not be reported under Specification 6.9.2 l
f 11-9 Amendment No. M, f,)d",
43
=
m 6.4.2 (Cont'd)
(b) Two of these nineteen area monitors shall be located in the vicinity of the fuel storage areas to provide gamma monitoring of the fuel storage areas and refueling operations. Local alarms shall be provided for these monitors, and alarm settings shall be in accordance with the provisions of 10 CFR 70.
Ilowever, notwithstanding the requirements of Section 70.24(a)(1),
alarm settings may be raised abo're 20 mR/hr as long as the overall detection criterion in Section 70.24(a)(1) is satisfied and the requirements specified in paragraph 6.4.3(e) below are met.
l At least five environmental film or TLD monitoring stations shall be (c) provided for determining the integrated gamma dose rate in the site environs. These stations shall be placed on an arc of about 1,350 meters from the stack.
6.4.3 Operating Requirements (a) At least one of the two air ejector off-gas monitoring systems shall be in service during power operation and set to initiate closure of the off-gas isolation valve as described below. Alarms normally shall be set to annunciate in the control room if the off-gas radioactivity reaches a level that corresponds to a stack l
release of 0.1 curie per second. At stack releases above 0.1 curie per aecond, the alarm shall be set approximately a factor of two abovetheexpectedoff-gasreleaseratebu5'19n event ab v that level corresponding to a stack release of 7 curie per second where E is the ageg9ge gamma energy per disintegration (MEV/ dis).
If the limit of y curie per second is exceeded, reactor power the limits. The shall be immediately reduced such as to meet monitors shall be set to initiate closure of the off-gas isolation valve (after a time adjustable from 0 to 15 minutes) if the off-gas radioactivity reaches a level that would correspond to a stack release rate of ten curies per second. Off-gas samples shall be taken monthly during power operation and analyzed for calibration i
of the off-gas radiation monitors. The automatic closure function of the monitors shall be tested monthly during power operation.
The stack-gas monitoring system shall normally be in service.
(b)
Adequate spare parts sha31 be en hand to allow necessary repairs to be made promptly. The alarm normally shall be set to annunciate in the control room at a level that corresponds to a stack release rate of 0.1 curie per second. It stack release rates above 0.1 curie per second, the alarm shall be set approximately a factor of b ve the expected stack release rate, but in no event above 5"27 y curies per second.
The calibration of the system shall be checked at least monthly.
The particulate filter and iodine filter shall be analyred at least weekly.
6-13 Amendment No.. g 43
=-:
y
--ww w
ir er.
meg e
v
,-e-y v-v g.wwg-g
--y-+p.y r
e
+*w-@
q w.+,.
9