ML20062A581
| ML20062A581 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/06/1978 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0473, RTR-NUREG-473 NUDOCS 7810160104 | |
| Download: ML20062A581 (76) | |
Text
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i nf w,,,,9 October 6, 1978-Director of Nuclear Reactor Regulation U. S. Nucicar Regulatory Commission
(,)
Washington, D. C.
20555
(
NRC DOCr T 50-32 0-366 OPERATING LICENSES DPR-57, NPF-5 f
EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 COMMENTS ON NRC DRAFT APPENDIX I TECHNICAL SPECIFICATIONS Centlemen:
(
Georgia Power Company is reviewing the draft Appendix I model Technical Specification issued by your July 11, 1978, letter. We under-stand that the NRC is working to revise the draft technical specifications and will issue the revision in the future. We have performed our preli-minary review of the draft and have developed some specific comments.
I We believe the results of our review, along with other industry comments, may be beneficial in the development of a revised draft.
The attached mark-up of sections of the draft NUREG-0473 contains the specific comments as they would apply to Plant Hatch. Application of the specifications would, of course, vary from plant site to plant site, depending on the specific needs of each.
Comments on the remaining sections will be provided as our review continues.
Should you have questions concerning any of the comments attached, we will be pleased to work with you in this area.
Yours very truly, g
A c
r Chas.k w ]V
(
F. Whitmer RDB/mb xc:
Mr. Ruble A. Thomas George F. Trowbridge, Esquire 7t/cKaml P
g,e lll
............ -..-.....-..--...... --..~
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.[.j l 1.'O DEFINITIONS CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy 6
to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL. FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequen-s.t.
tial, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST l.11 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify 0PERABILITY including alarm and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
d' SOURCE CHECK s
1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
T1 ESS CONTROL PROGRAM l
1.30 AP S CONTROL PROGRAM shall be the operating procedure and process paramete.
within which SOLIDIFICATION of radioactive wastes from liquid systems is as ad.
SOLIDIFICATION CT l
1.31 SOLIDIFICATION shall be the convers' of radioactive wastes from liquid systems to a nomogeneous, monolithic, 1 bili:ed solid with definite volume and shape, bounded by a stable surface of di ict outline on all sides (free-standing) and containing less than 1". free id, by volume.
BWR-STS-I l-1 i
l.,,,s.
n 1
I TABLE 1.2 1
-FRE00ENCY NOTATION FKE00ENCY i
NOTATION i
- . q At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4 S
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D At least once per 7 days.
W At least once per 31 days.
M At least once per 92 days.
Q At least once per 184 days, SA At least once per 18 me.iths.
i R
S/U Prior to each reactor startup.
"ithir, ' hoacs frior to each release.
P N.A.
Not applicable.
s 4
5 BWR-STS-I 1-8 t
r' t
INSTRUMENTATION
,RADIDACTIVE LIOUID EFFLUENT INSTRUMENTATION
[
LIMiTINGCONDITIONFOROPERATION The radioactive liquid effluent monitoring instrymentation 3.3.3.8 channels shown in Table 3.3-11 shall be OPERABLE with their alarm / trip setpoints *4hir, the speci fied limR+,4* Tera;ne/ <*st accst/.uce 44 p/daf froce4res, p/.f l
firebres sQ ; cId: meritohleg to assure TLT tia /;,. ifs q 3.n./. / me 4 u"y-
)3 APPLICABILITY: As shown in Table 3.3-11.
A(TION:
With a radioactive liquid effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than the cal =
n Tab 4-3.3 ", 4 mediate!y, suspend the release of veptrrJ
+hc= i radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, u-With one or more radioactive liquid ?f'luent monitoring b.
instrumentation channels inoperable, take the ACTION shown in Table 3.3-11.
The provisions of Specifications 3.0.3 and 3.0.4 are not c.
applicable.
SURVEILLANCE REQUIREMENTS Each radioactive liquid effluent monitoring instrumentation 4.3.3.8 i channel shall be demonstrated ODERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST l operations during the MODES and at the frequencies shown in Table 4.3-11.
[
I 1
i
- e j
BWR-STS-I 3/4 3-44 D
.e,
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s.
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_ TABLE 3.3-11 l-i RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION d$
v, os MINIMUM f.,
CHANNELS ALARM / TRIP MEASUREMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION
. Itis TRUMENT 1.
Gross Activity Monitors Providing Automatic Isolation 5
a.
Liquid Radwaste Effluent (1) 1(
cpm)
(1-10 cpm) 18 Line 2.
Gross Activity Monitors Not Providing Automatic Isolation Control w
a.
Service Water Effluent (1) 1(
cpm)
(1-10 cpm) 20 2
y line 3
bdar 6ld Close s
b.
&mpo at Cooling Water (1) 1 (_ _ cpm)
(1-10 cpm) 20 System I'
I
- During releases via this pathway t
i-b
}.
t.
.' - 1. *
~a.
- 7...
t
?
I.
r.
TABLE 3.3-11 (Continued) i m
i E.
RADIOACTIVE LIQUID EFFLUENT MONITORIllG INSTRUMENTATION _
w I
w i
Y M
MINIMUM
~
j CilANNELS ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION l
l 3.
Flow Rate Monitors 6
>(
gpm)
(0-gpm) 21 a.
Liquid Radwaste Effluent (1 )
i Line P,Te
<(
gpm)
(0-gpm) 21 b.
Discharge Gand (1) d.
a.ctivity Recorders-u 5
N.A.
(1~10 cpm) 43-1
.a.
Liquid Redeaste
{1-}-
-Effluent Line u
e I
a i
g t
- During releases via this pathway 1
i
)
i
~
l
t
_.s...-
s i
I L
E TABLE 3.3-11 (Continued)
?
RADI0 ACTIVE LIQUID EFFLUENT M0flITORING INSTRUMENTATION i, -
u.
MillIMUM CHANNELS ALARM / TRIP MEASUREMENT TrsTmli1ENT OPERABLE APPLICABILITY SETPOINT RANGE 5.
Tank Level Mon tanks outside the buildings) 3 (l
ft )
(0-1000 f t )
22 a.
3 3
b.
(1) ft )
(0-1000 f t )
22 3
1(
ft )
O(Lf t )
22 (1) c.
3 3
1(
ft )
(0-1000 f t (1) 1.
i.
nl 4
- 0uring liquid ' addition to the tank.
c.....
i-f.
?
Y I
t-
I l
i TABLE 3.3-11 (Continued)
TABLE NOTATION t
I ACTION 18 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from the tank may continue for up to 72-hcur:
provided that prior to initiating the release: H d'F 1.
At least two independent samples of the tank's r
contents are analyzed, ar.d fLt ersonnel At least two techrA.[",4ent4y verify the relta y qu:1"f ed member: ef the 2.
f acility-Sta f f indeper rat: ::lal-et4cns and discharge line valving, otherwise, suspend release of radioactive effluents via this pathway.
ACTION 20 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to #tfays provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are analyzed for gross radioactivity (beta or garmia) at a limit of detection of at least 10 7 pCi/ml,kdos Cs-is7 wee.
ACTION 21 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, eff1qert releases via this pathway may continue for up to f'Tdays provided the flow rate is estimated at least once per 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> +, batcl; release.
- 22 -
With the number of channels OPERABLE less than re pir(d by the Minimum Channels OPERABLE requirement, uid ens to this tank may continue for o 7 days a
provide ank liquid level is E* ' ated during all liquid additions e tank.
f ACTION 23 -
With the number of e els O h Q ess than required l
by the Minimum nnels OPERABLE requi
, effluent releases v he affected pathway may continue up to 7 da rovided the gross radioactivity level is reco i
1 a
east once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l em l
BWR-STS I 3/4 3-48
]
o i
TABLE 4.3-11 E
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUt1ENTATION SURVEILLANCE REQUIREMENTS ag i
CHANf!EL MODES IN WHICll CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUtiENT CHECK CllECK CALIBRATION TEST REQUIRED 1.
Gross Activity Monitors Providing Automatic Isolation
(
- a. Liquid Radwaste Ef fluents Line e-P
+ t1 R(3)
Q(1) 2.
Gross Activity Monitors flot Providing Automatic Isolation Control a.
Service Water Ef fluent Line D
li R(4)
Q 2)
M b.
Efypenent Cooling Water D
M R(-3-)+
Q 2)
[
lbder 8ll;Cle,c System 3.
Flow Rate Monitors a.
Liquid Radwaste Ef fluent D
N.A.
R Q
Line j
1 B.
Discharge Canal 0
N.A.
R Q
I i
e
-m_
r i.
i i
~
3 TABLE 4.3-11 (Continued) 1 i
Ef RADI0 ACTIVE LIQUID EFFLUENT MONITORIfiG INSTRUMENTATION SURVEILLANCE REQUIREP.ENTS I
Y CIIANNEL MODES IN MMCf1
~
CilANNEL SOURCE CilANNEL FUNCTIONAL SUJVEltfANCE 1
i MGIEUMENT CilECK Cil CK CALIBRATION TEST f REQUIRED i
4.
Ac tivi ty ders a.
Liquid Radwaste D
N.A.
R Q
I Effluent Line 5.
Tank Level Monitors (for tanks outside the N.A.
Q a.
t' b.
D N.A.
R Q
i' 8
c.
D N.A.
R Q
D N.A.
R Q
dels[a 1
a e
~
p
J
(
q.
TABLL_4. 3-11 (C_ortinued)
.e TABLE f:0 TAT 10'!
- - Durinyr:1000 0 "'
this pathway,is To Le used or rvle4sc.
f
- -BerhyMqu?d--addit?cm tc t' : ta ri.
(1) - The CHAf!!!EL FUi!CTIO:lAL TEST shall also demonstrate isolation of this pathway and control rocm alarm annunciation cccurs if any of the following conditions exist:
Instrument indicates measured levels 'above the alarm / trip 1.
setpoint.
2.
Circuit failure.
3.
Instrument indicates a downsctle failure.
4.
Instrument controls not set in operate mode.
(2) - The CHA!!!!EL FU !CTIO::AL TEST shall also demonstrate alarm annunciation occurs if any of the following conditions exist:
[
Instrument indicates measured levels above the alarm / trip 1.
setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
Instrument controls not set in operate mode.
4.
(3) - The CHA!!! EL CALIDP.ATIO!! shall include the use of a kn
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r e.
. - _...n.u.-
z_Qg.,..,.,. w aY[Ms[cti[e bbbrcb+bcIi ibr.bd in b$bhrbdubbi[
M W ban fabfed ti
- withrespecttothesensorandl0E:itG4-9 bets an'd pc.mma radiation NB5 snue.Th with the fluences and energies in the ranges mensured by the km 5,m didll:
channel during normal operation.
i!t). Tkt CHkJr/EL CALISRATrod shti inelade rh use cf a. (s-157 some ut;ck L, beers csltbrate) to
!!6S soarec. Tits Cs-IST swee s!nllbe pas'%dina refrodacillc geesetry u% myeef 15 th sensor.
C.-
BUR-STS-I 3/4 3-51 c
s l
INSTRUMENTAT!DN l
_ RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION j
LIMITING CONDITION FOR OPERATION The radioactive gaseous efflupnt monitoring instrumentation 3.3.3.9 channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints within the-sper.Mied 14"4 ts,dar aelm eccadame u; A pli Grac<4*ics /la-f frecedores shil snelde meded.lun to aswa tM h I,ds of 3.or.).t are o.stSeded.
APPLICABILITY: As shown in Table 3.3-12 ACTION:
With a radioactive gaseous effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than the t' alee sq Aed show,8-Tabic 3.312, 4~ed?akQ, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
With one or more radioactive gaseous effluent monitoring b.
instrumentation channels inoperable, take the ACTION shown in Table 3.3-12.
The provisions of Specifications 3.0.3 and 3.0.4 are not c.
appl icabl e.
SURVEILLANCE REOUIREMENTS Each radioactive gaseous effluent monitoring instrumentation 4.3.3.9 channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequen:ies shown in Table 4.3-12.
6 6
BWR-STS-1 3/4 3-52
\\
~. - - -
~
s
~
,;~
=
y
.~
TABLE 3.3-12
,i RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION y
L cl dTc MINIMUM CitANNELS ALARH/ TRIP MEASUREMENT I
INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION 1.
Waste Gas Holdup System fosT-hstnE On -f<>
a.
-HeMc Cas Act h. ty 6
4 Monitor (1) 1(
cpm)
(10-10 cpm) e7 6
+
N.A.
(10-10 cp,)
.g3, S.
'bMe Gac ^cthity 9ecordcr (1)
+
N.A.
N.A.
47 R
c.
Iodir.e Sa:"pler---
fi-)-
N.A.
N.A. d.
Part4tu4 ate Sampler
(+}-
>(
cfm)
(0-cfm) f['
e, k g.
Flow Rate Monitor (1)
>(
cfm)
(0-cfm)
- f.
Samplee-F4cw Rate Mcr. iter (1)
C,q.
Ilydrogen Monitor (1) 1 (4%) by volume (0-20%) by volume EdY l
t.
Hydronen Monitor'(alternate) 1 (2%) by volume (0-20%) by volume
-30
- 1) a lann 7
=
I,'
2) a 1 (4%) by volume (0-20%) by volume 3&
1
- During releases via this pathway.
- During waste gas holdup system (treatment for condenser evacuation system offgases) operation..
i I
6
I.
..- a.
...........t..
4 TABLE 3.3-12 (Continued)
=
5 h
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRU!tENTATION P,
MINIl1UM CHANNELS ALARM / TRIP MEASUREMENT I
IttSTRUf1ENT OPER3BLE APPLICABILITY SETPOINT RANGE ACTD i
1.
Waste G p System (continued) i 1.
Oxygen Monitor (1) 1 (4%) by vo (0-25%) by volume 29
[
J.
Oxygen Monitor (alternate)
- 1) alarm (2) 1 ((2%) by volume(0-25%) by volume 30 1 4%) by volume (0-25%) by volume 30
- 2) alarm and initiate (2) automatic control function w1 2.
Condenser Evacuation System 0
a.
Noble Ga uvity Monitor (1) 1(
cpm)
(1 -
cpm) 25 6
N.A.
(10-10 cp,)
3 loble Gas Activity Recorder (1) d
- During releases via this pathway.
- During waste gas holdup system (treatment for condenser evacuation system offgases) operation.
i e
J
.h
.=
1
't TABLE 3.3-12 (Continued)_
E RADIDACTIVE GASEOUS EFFLUENT M0filTORING INSTRUMENTATION y
M MINIMUM ClAftNELS ALARM / TRIP MEASUREMENT INSTRUMErlT OPERABLE APPLICABILITY SETPOINT RAf(GE ACTION imMes1.4.u pI~.d sc-L neanical wee a,< pa.9 c2.3.
Main Stack System (c*iwis-d wnte s L %1ild) ofhiew 6
2f a.
Noble Gas Activity Monitor (1) 1(
cpm)
(10-10 cpm)
N 6
N.A.
(10-10 cp,)
93
+
~i b.
'! chic Cr ",ctivity Recorder (1) tV ;.
N.A.
N.A.
I bb.
lodine Sampler (1)
N N.A.
N.A.
c,4.
Particulate Sampler (1)
>(
cfm)
(0-cfm)
-2fr d a.
Flow Rate Monitor (1)
>(
cfm)
(0-cfm) 46--
^-
Y f.
Ompice Flow Rate "cnf ter (1) mw Containment Purge System 6
% Gas Activity Monitor' (1).
/
1(
cpm)'
(10-10 cpm) 23 a.
I 6
N.A.
(10-10 cpm) 23 b.
Nobel Gas
'vity Recorder (1)
N.A.
N.A.
28 c.
Iodine Sampler
)
N.A.
N.A.
28 d.
Particulate Sampl i
e.
Flow Ra onitor (1) 1(
cfm)
(0-cfm) 26 f.
ampler Flow Rate Monitor (1) 1(
cfm)
(0 _ cfm) 2,6
- During releases via this pathway. -
/
r-..-....
~
j q
t t
s TABLE 3.3-12 (Continued) m E
l RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION f
MINIMUM CilAfiNELS ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE APPLICABILITY SETP0lHT RANGE ACTION Auxiliary Building Ventilation System
<(
cpm)
(10-10 com)
[
6 j
a.
No 1 Gas Activity Monitor (1) 6 N. t..
(10-10 cpra 23 b.
Noble Gas Ac ivity Recorder (1)
N.A.
i. A.
27
}
c.
Iodine Sampler (1)
R N.A.
N.A.
27 d.
Particulate Sampler (1)
- f
>(
cfm)
(0-cfm) 26
- g e.
Flow Rate Monitor (1)
>(
cfm)
(0-cfm) 26 f.
Sampler Flow Rate Monitor (1)
Fuel Storage Area Ventilation System 6.
6 a.
Noble Gas Activity Monitor (1) cfm)
(10-10 cpm) 27 l
0 N..
(10-10 cp.n) 23 b.
Noble Gas Activity Recorder N.A.
N.A.
27 c.
Iodine Sampler (1)
N.A.
A.
27 d.
Particulate Sa e
(1) f
>(
cfm)
(0-cfm 26 e.
Flow ste Monitor (1)
>(
cfm)
(0-
' cfm)
Sampler Flow Rate Monitor (1) i
- Durino releases via this' pathway.
~'
,~~~}
i 3
TABLE 3.3-12 (Continued) s f
RADI0 ACTIVE GASE0US EFFLUEtiT M0tilTORING INSTRUMENTATION NY 1.
MINIMUM I
CilANNELS ALARM / TRIP MEASUREMENT 1
INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION Radwaste Area Ventilation System 6
a.
e Gas Activity Monitor (1)
<(
cfm)
(10-10 cpm) 2'7 6
b.
Noble Gas c 'vity Recorder (1)
N.A.
(10-10 cp,)
3 I
c.
Iodine Sampler
+
N.A.
N.A.
27 t
l d.
Particulate Samp N.A.
N.A.
27
{
e.
Flow R onitor (1)
>(
cfm)
-(0-cfm) 26 Y
Sainpler Flow Rate Monitor (1)
--(
cfm)
(0-cfm) 1 6 geter
(;u(46 hL:sc W rada.te H4))
3 R.
krMete Building Ventilation System g
6 4
a.
Noble Gas Activity Monitor (1)
<(
cfm)
(10-10 cpm)
W-b.
" cmc Cr f.ctivity Recordtr (1) 6
+
N.A.
(10-10 cp,)
g 1
bt.
Iodine Sampler (1)
N.A.
N.A 4
CA.
Particulate Sampler (1)
N.A.
N.A.
27 d,4.
Flow Rate Monitor (1)
M
>(_
s cfm)
(0-cfm) ffr Sampler Flcw Rate "cr.itor
(+)
>(
cfm)
(0-cfm) *
- During release via this pathway.
a
u... :...
p i
I 18 TABLE 3.3-12 (Continued)
P i
U Y'
RADI0 ACTIVE GASE0US EFFLUENT M0filTORING INSTRUMENTATION h
ddtk MINIMUM
~
CilAfiNELS ALAPfi/ TRIP MEASUREENT INSTRUMENT OPERABLE APPLICABILITY SETPOINT PANGE ACTION Rea,.l>:ner EL!. %% ton Spie, < (HnP-I) 9.
-Turbint Cland' Scal Conden:cr Vent and-Meeharical Vacuum Pump Ex!iaust g
2.j-a.
floble Gas Activity Monitor (1) 5, (
cfm)
(10-10 cpm)
W 0
N.A.
(10-10 cpm) 3-b
'!ch!c G?.s ^.c tivi ty P,ecorder (1)
M 4-2 l
b K.
Iodine Sampler (1)
N.A.
N.A.
21 N.A.
N.A.
27 C, ti,.
Particulate Sampler (1) w
.1 E.
Flow Date Monitor (1)
>(
cfm)
(0-cfm) 26 w
4, Wamf>1erflFw Ta te Monitor (1)
>(
cfm)
(0-cfm) 2p 1
1
- During releases via this pathway.
m i
,j d.
I i
l' TABLE 3.3-12 (Continued) l 1
5 TABLE NOTATIO?!
i 1
l ACTION 23 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases i
via the affected pathway may continue for up to 7 days provided the gross radioactivity level is recorded at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
i ACTION 25 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, gases from the condenser evacuation system may be released to the l
d(
environment for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided:
9 f
1.
The waste gas holdup system is not bypassed, and
]
2.
The waste gas holdup system noble gas activity rionitor is OPERABLE:
otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 96.5 With the number of channels OPERABLE less than required 1
by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for--up tc 7 days provided the flow rate is estima'.ed,4t-least once per '
hour-s.
A ACTION N -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent f
releases via this pathway may continue for up to " days provided grab samples are taken =t least cnce per ' Scurs and these-t rples are analyzed for gross activity at i
least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
AETT0t20 WitjLthe number of channels OPERABLE less by the Minimin-Ctan ^ S NM equirement, suspend telea loactive effluents via th b pt May_
25'
~
ACTION 29.-
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to 14 days provided gas samples are analyzed at,least once a
per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ALT!.
With the number of channnels OPERABLE one les re
" the Minimum Channels or
- requirement, operation of this ioidup system may continue for up to With both cnar erable, immedi-a.tel uspend operation of this waste gas holaup BhR-STS-I 3/4 3-59 I
l E
n 4,
TABLE 4.3-12 d
RADI0 ACTIVE GASE0US EFFLUENT MONITORIllG INSTRUMENTATI0fl SURVEILLANCE REQUIREMENTS 3
CilAtlNEL MODES IN WHICH CHAflNEL SOURCE CHANNEL FUNCTI0fiAL SURVEILLAftCE INSTRUMENT CllECK CHECK CAL;3 RATION TEST REQUIRED 1.
Waste Gas Holdup System bt L.L.,t ofi-p
- a. Hcble Ga Activ!ty Monitor
-P D
_p_ H R(3)
Q(1) b---Nobl e-Gas-Ac t-i yi ty-Retorder 0
M.A.
R Q
- c. Iodine Sampler g
u,q, 3,3, 3,3, M
<b--Part4ealate Sampler 9
mi. a.
u.a.
ua i'8 LR. Flow Rate Monitor
+D N.A.
R Q
f-Sempler-f tc Mariter 0
N.A.
R
,Q
[
^
C,g. Ilydrogen Monitor D
N.A.
Q(4)
M tr-41y4rogen_. Monitor (alternate)
D N.A.
Q(4)
M
^*
- 1. Oxygen Monitor U
"k
%)
M i
J. Gwy9ar.-Mu..iibr talternate)
D N.A.
Q(5)
M S
6
"c
- ?
TABLE 4.3-12 (Continued) i RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SU
'f' CHANNEL MODES IN WHICH
, INSTRUMENT CHANNEL SOURCE CHANflEL FUNCTIONAL SURVEILLANCE CHECK CHECK CALIBRATION TEST REQUIRED vacuation System
- a. Noble Gas Activity Monitor D
(3)
Q(2)
- 5. "oble Gds Acuvity Recorder D
N.A.
R d '1.
Main Stack System (41J+9 kbb M'
"*Pa ram M M M44 M kM~i )
/
I g
- a. floble Gas Activity Monitor D
M R(3)
Q(2) a fir-flofile-Gac ^.ctivity Recorder 9
M.A.
n.
Q w
l b K. Iodine Sampler.
D N.A.
N.A.
N.A.
c 4. Particulate Sampler D
N.A.
N.A.
N.A.
J h. Flow Rate Monitor D
N.A.
R Q
-f-Sr;'!cr Fic;. 95tc Monitor 0
mi. p.
o q
i
~
q.
y
...I
.~
.. lL',,. u..
L ' -
i
~ ^
j
'l i
i'
[
,1 5
i I
x A
TABLE 4.3-12 (Continued) 1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
I CHANNEL MODES IN WHICH l
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMErlT CHECK CHECK CALIBRATION TEST REQUIRED c
,l Containment Purge System l
a.
le Gas Activity Monitor D
P R(3)
Q(1) f
- b. Hoble G Activity Recorder D
N.A.
R Q
l
- c. Iodine Sampler D
H.A.
N.A.
N 2
- d. Particulate Sampler D
N.A.
N.A.
N.A.
l y
)
e O
- e. Flow Rate Monitor D
N.A.
R Q
- f. Sampler Flow Rate Monitor b
N.A.
R Q
I l
5.
Auxiliary Building Ventilation System
[
- a. Noble Gas Actvi'ty Monitor D
M R(3)
Q(2)
- b. Noble Gas Activity Recorder D
N.A.
R Q
- c. Iodine Sampler D
N.A.
N.A.
N.A.
- d. Particulate pler D
N.A.
N.A.
N.
- e. Flow e Monitor D
N.A.
R Q
. ' ampler Flow Rate Monitor D
N.A.
R Q
o.
s.-
y f
i l
ca t
[,
TABLE 4.3-12 (Continued) i
}[
RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICil CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED l
Fuel Storage Area Ventilation System cg(g)[
a,
,j a.
foble Gas Activity Monitor D
M R(3)
Q(1)
I
- b. Noble Activity Recorder D
N.A.
R Q
l
- c. Iodine Sampler D
N.A.
N.A.
- d. Particulate Sampler D
N.A.
N.A.
N.A.
- e. Flow Rate Monitor D
N.A.
R Q
- f. Sampler Flow Rate Monitor D
N.A.
R Q
7.
Radwaste Area Ventilation System
- a. Noble Gas Activity Monitor M
R(3)
Q(2)
- b. Noble Gas Activity Recorder D
N.A.
R Q
I
- c. Iodine Sampler D
N.A.
N.A.
N.A
- d. Particulate a pler D
N.A.
N.A.
- e. Flow e Monitor D
N.A.
R Q
s j
. Sampler Flow Rate Monitor D
H.A.
R Q
. t.
~ !
a, E
h TABLE 4.3-12 (Continued) s w1 RADI0 ACTIVE GASEOUS EFFLUEllT MONITORING INSTRUf1ENTATION SURVEILLANCE REQUIREMENTS t
CilANNEL MODES IN WillCil i
CHANNEL SOURCE CHANNEL FUNCTIONAL SL'RVEILLANCE INSTRUMENT CilECK CllECK CALIBRATION TEST REQUIRED Rader (i* lad (e to,b:neo.4 r.Jasic. vg; f
.3 &.
kr-bme Building Ventilation System g
3.
floble Gas Activity Monitor D
M R(3)
Q(2)
. "0ble Cas Activity "ecorder 0
ti. A.
R Q
l b s. Iodine Sampler M
N.A.
N.A.
N.A.
,s l
[
cd. Particulate Sampler VI N.A.
N.A.
N.A.
a d,u. Flow Rate Monitor D
N.A.
R Q
l I
. S=;4er clow Ritte Mor,itor 0
N.A.
R Q
2-Pcec. Liner 6th ve hletion system (!HT-l) 4 R.
TurMnc Gland Seal Condenser Vent and MccMnical Vacu= " ump Exhaun
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
I l
?
- b. " ele Ca Activity cccrder 0
ti. A.
R Q
a i
b t. Iodine Sampler W
N.A.
N.A.
N.A.
[
cA. Particulate Sampler W
N.A.
N.A.
N.A.
i E. fic. 9 ate Manitor D
N.A.
R n
e x -SamplerP1ow Ha te Moni tor 0
N.A.
R Q
._.__.._......_____.._.u..,_.,.
u.._.,,___,,
l
\\
i
,y.. :;
TABLE 4.3-12 (Continued)_
~,
TABLE NOTATION 11
- --Ourimy-releases-vu this pathwayf is to be u5c<lin f8Ie*5C-
- ----Dar-ing-waste-gas holdup system operytion,-
(1) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
~
2.*
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alam annunciation occurs if any of the following conditions exist:
4 1.
Instrument indicates measured levels above the alarm / trip setpoint.
I 2.
Circuit failure.
- e 3.
Instrument indicates.a downscale failure.
4.
Instrument controls not set in operate mode.
-i (3) - The CHANNEL CALIBRATION shall include the use of a known (traceable to-the-44t4ona4-Bureau Of Standawis--rad 4eion-measurement system) dd 6 g,g qawsus radioactive source,posi,tjoned in a reproducible geometry o bid t.
- with respect to the sensor and[eniitt4Wr beta and ganna radiation g g3,,,*
witti fluences and energies in the ranges measured by the channel gy during normal operation.
Tane dan k 4
CWR-STS-1 3/4 3-65
~ -
l
] ~,
".l t
TABLE 4.3-12 (Continued).
l g
TABLE NOTATION
- - i (4) - The CHANNEL CALIBRATION shall include the use of standard gas samples
~
containing a nominal:
and
-1.
Onewelume-percent--hydrogenAalance aitregen, i
(.
Four volume percent hydrogeri, balance nitrogen.
CHANNEL CALIBRATION shall include the use of standard gas s (Wh(tairitn con nominal:
1.
One volume percent o -
ance nitrogen, and I
r volume percent oxygen, balance nt i %
e i
a }
\\,
4 i
- g i
m BWR-STS-1 3/4 3-66 1.
~
i
~-
f
,3 4
- j
! INSTRUMENTATION
, :i
'4 l BASES e
1 J
.~l 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION l
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in l,' liquid effluents during actual or potential releases of liquid effluents.
The-a1 ara /.tr4p-setpcints for--these Jastrucents a re prov44ed_to-enwee_tha*
the-elarm/tNp-wi44-ocur--pr4er--to4xceedir.g the 1 M44: c f 13-GFLPar-t 20.
The OPERABILITY and use of this instrumentation is consistent with the l requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
,. 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION L;
The radioactive gaseous effluent instrumentation is provided to l monitor and control, as applicable, the releases of radioactive materials
'i l in gaseous effluents during actual or potential releases of gaseousTh
' ef fluents.
I: ensur-e-that the 44uc44rJS will occur prier to eveeeding the limite nf in l ' -C-fR-f'et-M.
This instrumentation also includes provisions for monitoring
.:: (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instru-
- ! mentation is consistent with the requirements of General Design Criteria Vi
- . 60, 63 and 64 of Appendix A to 10 CFR Part 50.
g.
I.
s' le s
s
- i.
=
g
'?
C
. j' t
l I
j i
l BWR-STS-1 B 3/4 3-4 6-e
--......c.-..
gs j
l I
RADICACTIVE EFFLUEflTS XPLOSIVE GAS MIXTURE,-(-Systems-designed-to-withstand-a-hydrogen ex i'
E I
LIMITitlG CONDITION FOR OPERATION dt w k n >{ Tl4 M< & &
The concentration of { hydrogen oe-oxygen}jin the waste gas 3.11.2.5 holdup system shall be limited to < 4% by volume.
APPLICABILITY:
At all times.
CWMW } b st%kg in the waste With the concentration of [ hydrogen oraxygen)3 gas holdup system exceeding the limit, restore the concentration a.
to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The provisions of Specificatioris 3.0.3 and 3.0.4 are not b.
applicabl e.
i SURVEILLANCE REOUIREMENTS
& & fN 4.11.2.5 The concentration of hydrogen oc-owyg% A n the waste gas i
holdupsystemshallbedetermin{edtobewithintheabovelimitsbycon tinuously monitoring the waste gases in the waste gas holdup system with the jhydrogen on-oxygen) monitors required OPERABLE by Tab i
of Specification 3.3.3.9.
(
e l
h I
l 3/4 11-34 BWR-STS-I i
f O
$Q 1hR e
... - -. ~.
4 I
i 8
RADIOACTIVE EFFLUENTS
/
. EXPLOSIVE GAS MIXTURE _ (Systems not designed to withstand a hyd
\\
'j LIMITl4G CONDITION FOR OPERATION
~
pe concentration of (hydrogen and/or oxygen) in the waste gas 3.11.2.5A 2% by volume.
holdup systems hall be limited to 1 s
APPLICABILITY:
t all times, n.
ACTION:
With the concentration of (hydrogen and/or oxygen) in the waste gas holdup system > 2% by volume-but < 4% by volu a.
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
With the concentrat on of (hydrogen and/or oxygen) in the waste b.
gas holdup system > 4%lby volume, imediately suspend all additions of waste ga'ses,to the system and reduce the concen-tration of (hydrogen and/or oxygen) to 1 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Theprovisions/ofSpecific\\
ations 3.0.3 and 3.0.4 are not c.
applicable. /
SURVEILLANCE REQUIREMENTS
~
/
\\
The concentrations of.(hydrogen and/or oxygen) in the waste gas 4.ll.2.5A holdup' system shall be determined to be within the above limits by conti'nuously monitoring the waste gases in the waste gas. holdup system x
wJt'h the (hydrogen and/or oxygen) monitors required OPERABLE b 4f Specification 3.3.3.9.
/
l BWR-STS-1 3/4 11-35 i
t
t'.
1 i
RADIDACTIVE EFFLUEliTS_
- 2.,
s
- i.
14Alti C0flDEtiSER i
\\
Ll!4LTIt4G C0tiDIT10ft FOR OPEPATI0ff r-i
).
The gross' radioactivity (beta-and/or-gama). rate of noble gases /e y,a 3.11.2.6 from-the main condenser evacuati.W,Jystem shall be 1.imit
?'ewI d,
on pCi/sec&: wM( g Rf M,
.f APPLICABILITY _:
At all times.
ACTI0tJ:
Uith the gross radioactivity 4 beta-and/orgamma) rate of noble ga
$W a
uCi/sec, restore,
+he main condenser evacuation system exceeding (340,000) 2 9,
the gross radioactivity rate to within its limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be au/J4 Au.c# ve in at least-liOT-STAtiDBY-within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. /fq/ff g&%Q l
Q],%p tad & <4u% M.a qy-f th c,,m y z
?
SURVEILLAtlCE RE0VIREMEt1TS The gro}ssoradioactivity (beta-end/cegamal rate of noble gases m
EE ^m7ed -
2.6 M,%he main condenser evacuation system shall be determined to be fror:r
- /
within the above limit at the following frecuencies by performing anpd4 isotopic analysis of a representative sample of gases taken at the
-J discharge -{ prior--to-dilution-and/or-discharge)-of-the main-condenser evacuation system: %@ c6L-g lZf M<dw h
At least once per 31 days M A TIr /
a.
J Within-4-hours hilowing an increase, as indicated by the b.
Condenser Evacuation System tiobleh4ctmt/4To~nitor, of greater than 50"., after factoring out increases due to changes in THER!4AL POWER level, in the nominal steady state fission
-4 gas release from the primary coolant.
4 e.
M BWR-STS-I 3/4 11-36 I
i i
L ~ ~e.....
..~........
- _ =.
i, t
RADIDACTIVE EFFLUENTS MARK or II CONTAINMENT (Optional)
\\
/
LIMITING C0t:0lTION FOR OPERATION a's or II containment drywell shall be purged through 3.11.2.7 The Mark s
the Standby Gas Treatment System.
f ej Whenever the drywell is purged APPLICABILITY:
/
ACTION:
With the requirements of the above specification not satisfied, 3
a.
suspend all purging of the drywell.
~/\\
b., The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1
Tpe containment drywell shall be determined o be aligned for 3.11.2.7 purging through the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during purging of the drywell.
l..
s ;:
s 9
./
s
.J i
.{
~~
0 A
BWR-STS-I 3/4 11-37 I
I
RI,010 ACTIVE U FLL*""JS OASE5
=C-
C~C
~
3/4.11.2.5 EXPLOS!VE GPS MD:TUS.E Thir. specification is provided to ensure that the cencent etic.~
potentia'.ly explosive g:s nixtures conceined (Automatic control features arc included in-the system to hydrogen ud-uygen concentratient fror reaching thse-f a These au cmatic control features incluce isc'iation o hydrogen,and/or-tnypn, autcmatic diver sicn to reccebincr
)
of dilut.:nts to reduce the concentraticn belcw the flanmability lim
!!3intaining the concentration of hydroc en ad-oxygoa below t mability limitt, provides assurance that the releases of radioac materiali uill be controlled in conforr.ance with the requircionts o General Design Criterion 60 of Appendit A to 10 CFR Part 50.
Mall! CONDENSER 3/4.11.2.6 Restricting the gross radioactivity rate of noble gases from d
sure main condenser provides reasonable assara ll 100 in the event this effluen:
('
fractior, of the limits of 10 CFR Part ih t treat-is inadvertently discharged directly to the enviro Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
ment.
~
AARI'. I CONTAIMMENT_ (OPTIONAL) 3/4.11.2.
de~s seasonable assurance that releases from drywell purging-opTrations will'r.ot-exceed the annual do This specifica g
3 limpf-101FR Part 20 for unrestricted ar;eas
)/All.3 SOLID Rt,010 ACTIVE 1!ASTE AMLITY of the solid radcaste systein.en ures that t ssing and will be available' Tor-u'se whenever solid rad <astes require p T
~
implements
^
packaging prior to beingsh4 qed offsite.' This specificat the requirements of 10 CFR PartMQpr:cgparameters includcd in Appendix A to 10 CFR Part-50.ing the PF.0 CESS C The o
j 1
l tios, waste type, v:aste,pHS:aste/ liquid /selidi fication age it/tatalyst r..
q i
oil content, waste principal chemical constituents, mixing u l
times', '
B 3/411-5 Gl!R-STS-I e
l
--w--
a man e e&
~..
h 3/4.12 RADIOLOGICAL EfNIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM
.t, LIMFTING CONDITION FOR OPERATION
..j 3.12.1 The radiological environmental monitoring program shall be
- i conducted as specified in Table 3.12-1.
n, APPLICABILITY: At all times.
,.,a' sisg4f &llm: 6CducN}
the radiological environmental monitoring program not M
a.
be4ng-conduc4ed,n specified in Table 3.12-lend-14 bw:,Tusutmot-to the Comtss4en in the Annual Radiological -Operating Report'.a=dsser4ption c4 the reasons for ast--c-end= ting the4e
[g
- k' 4
(twf 3/t/vehiI.jp)sogran-as-required-and the plans for preventing a recurrence 14 %sAs) c b.
1 veh of radioactivity in an environmental sampling L.-
.%.N mediu at one or more of the locations specified__inlable Q _;
.%_.._..CD fl2 xceeding the limits of Table 6A-2%n averaged over ' --
' M.S$p ny c-1 h
alendar quarter, -prepar-e-and submit to the Commission W
_ ithin 30 days from the end of the affected calendar quarter, M tt[+
w TTR~eport/.whaich includet an evaluation of any release M
dv,, NE
... g,/; f) a Spec a dinditions, environmental factors or other asp ~ects which m levf M,e t
~
6i's report
. u.9 caused the limits of Table &9-2 t exceeited.
T g.[,
^l 4
is not required if the measured level f radioactivity wasTot% --- s j
'A
. _./
t the result of plant effluents; however, in such an event, the Qgg /c y
-u)M4r condition shall be reported and described in the Annual Radio-gical Environnentalfpera-t4ag Report.
2-2.
n N able from d k. f 4tth milk or 1
te J
t t,,,,
A of the sample locations required by Tabl 3.12-1,. prepare-cem e i
dh. _..a ny~lE9i{ t. to..t fie C'o~2ElisToTwi_t hlit2{Q_d ay hg=,[I Aed
~
.aad rsuant to Specification 6.9.2, a Special Report which identifies _the 4, -
cause of the unavailability of samples and identifies'Mocations M
dik(w(f ded
[t'$tthm.- f or c@taining repf acement sampleh The-leca-t4ons. from-wMeh Isamples-wene-una.vai.lable may-then-be-del eted--from-Table -3 A-2-4 and-Figure--3rl2-1-provided the-locations-front which-the-replace-sent-samples were-obtained are added-to-the-env'r mental ca tvYO' f k Tk &.w.1 Co.w. w.d4./ %
ogram as replacement-locations-i.AJM ed
. manitorin
- n aAtM.gl 5:'C E U -t A !.,9) f.(4 d.
Tile provisicas of' Specifications 3.0.3 and 3.0.4 are not gy/ l
-j
. _. applicable.
lj.eL.,+t.[b?CfA'.-
( q.
$'f7_f.ly.Y4&
h n w (( h j! &af f.---.
[2b bM ff bw>WM Minhag hp/1r-e,v e [r 11" e
r I
' M A confirmatory rer.nalysis of the original,.a duplicate, or a new sample may be desirable, as appropriate. The results cf the ccnfit matory i ~
analysis shall be co..pleted at tne-. earliest titaa consistent witii the.
analysis, but in any case within 30;. days.
l c.3,Uf..._,./.2
+-
-.n y
e..
.q 8=4
'/j RADIOLOGICAL EriVIR0!iMEtiTAL M0filTORIriG SURVEILLAtiCE RE00lREMErlTS
\\
.i t
4.12.1.1 The radiological environmental monitoring samples shall be
'I collected pursuant to Table 3.12-1 from the locatiens-showr,-cr. Figucc-3.12 L and shall be analyzed pursuant to the requirements of Tables 3.12-1 and a
4.12-1.
4.12.1.2 Reports - The~ results of analyses performed on the radio-t logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental.Oper; tin-Report.
b%W
~
pj bd & ys '
sin 3. I 2. l..$- p QR3/4
) 2-1 When more than one of the radionuclides in Table M~~3,12.-2 are detected in the sampling medium, this report shall be submitted,if:
u s.t I fd N (1) concentret4en (2)
+'"*>1*0 limit level (i) limit level (2) i 3 12 '2 i
When radionuclides other than those in Table 6--9-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar y-sr limi.ts of Specifica-
~
tions 3.11.1.2, 3.11.2.2 and 3.11.2.3.
-/\\'
3 ri
.r..
s..--
l6 V-
..;r lv-l P4-72-2
=
l :m..
BWR-STS-I
~
......-....-..--...k.,...---*----
l
~
3/4.12 RADIOLOGICAL EfiVIR0!!!iErlTAL tiO'1ITORif1Go g/ It.- C A 3/4.12.1 M0filTORiflG PROGRAM i
LIMIT!f1G C0ilDITI0tt FOR OPERATIO!!
J 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Tabic 3.12-1.
APPLICABILITY: At all times.
ACT10t!:
Any significant deviations in conducting the radiological environ-a.
mental monitoring program from that as specified in Table 3.12-1 shall be documented in the Annual Radiological Surveillance Report; the reasons for these deviations and any appropriate plans for preventing a recurrence shall be stated.
b.
If the confirmed ** measured levels of radioactivity in an environ-mental sampling medium at one or more of the locations specified s
in Table 3.12-1 are determined to exceed the limits of Table 3.12-2 when averaged over any calendar quarter, submit to the Commission within 30 days from the end of the affected calendar quarter, or af ter confirmation whichever is later, a Special Report pursuant to Specification 6.9.2.
When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
level (2)
+.... > 1.0 level (1)
+
limit level (1) limit level (2)
When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or areater than o,ues
. " the EaTeitdar% or limits of Specifications 3.11.1.2, 3.11.2.2 and
'l 3.llT E3 D his report shall include an evaluation of any release conditions, environmental factors or other aspects which may have caused the limits of Table 3.12-2 to have been exceeded.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Surveillance Report.
lhis Radiological Environmental Monitoring Program serves both units at the site.
T l
- A confirmatory reanalysis of the original, a duplicate, or a new sample may be i
desirable, as appropriate.
The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case i
within 30 days.
l
E
. 3/412 RADIOLOGICAL ENVIRON"ENT/t f0NITORING i
,x t.,h 'lfC f! -{ c
~./, ;/
/
3/4.12.1 MONITORING PROGRAM
~l LIMITING CONDITION FOR OPERATION (Continued)
If adequate samples of milk or grass (during the growing season) from c.
any of the sample locations required by Table 3.12-1, can no longer be obtained, efforts shall be made to find replacement locations.
Pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies the locations to be deleted and any locations for obtaining replacement samples shall be submitted to the Commission within 30 days.
Sub-sequent replacement or additional locations shall be documented in the Annual Environmental Surveillance Report.
d.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
\\
~
I I
i l
3/4 12-la c.
I I
(.
Y
& f M >rs 9.&i w.t r. ih, stk4mtN 'M4W tt$
bj',
a pc h,J6 u 1r 4
m,rlo, fx &p L s gi m u ~.
n f
/ hts A
s TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
.. M I
m i
Humber of Samples
~
I Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency of Analysis 1
1.
AIRBORNE t
a.
Radiciodine and
-(44 cat-ion; 14}
Continuous operation of Radiciodine canister:
1 Particulates sampler with sample col-Analyze at least-sace lection as required by dust loading but at least Crw c4
- f, dew 1 pc ays for 1-131 I
once per 7 days.
Particulatesa;mpler:
gq g g g gg
- /, q d Analyze for gross beta t$ ( l cli h 0 1 & M.~ (5E -I.2 4 8<)
radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> foo"'ng Itcr change; i
.i$
Nj j yil[] hp (k 6 & - I' O a Perform gama isotopic analysis on each sample when gross beta activity N
{c,7]Jr.f h b y.
is > 10 times the mean of control samples; for-any.
ffl M,@ f y A r m f h MN - ll
- medium, Perfonn gamma i
1sotopic analysis on i
i iy
$4 0 gm,
3
- l0 compo5ite (by-loest-fo e
sample-+t-4 east-once-(
per-92-days. 4cd 4 2
DIRECT RADIATION (4:eeat-ions 1-0)
At lea:> i. um.e per 31-Jays.
. Gamma-dose,--At--least-
' M g.aM y g"m
> 2 dosimeters 0 9 i.,"
once4er--31-days.
ins-trument-for-con.-
T"'d,//M, O
b tinuous4y-meastming or At least once per 92 days.
Gama dose. -At-least-and e ording-dese
@ead-out--frequencies-eve
' fTIJ7 /df Mr.d (656-A14 ate-at--eactr deter. mined-by-type-ef-dost.-
onee-pen-92-days n
- yIM cl&Oe
" " " ' ~ * ' ' ' *
\\i ll3 ku 6 ~ % -(5-M 4 *** "
tm hv-I.0 4 t1
^*-Samp' e-)odatl-ops-are-sho)wn-on-F-isure-3rl2 -1.
,[.;
I1
. c.
-;- 7 7 y,3 ci r, p.
'l y,
,.fe
.1
~
. -, i '.. C - '
5 5
I l
TABLE 3.12-1 (Continued)
~
g RADIOLOGICAL EUVIRONMENTAL MONITORING PROGRN4 i
E i
,i.
G Humber of Samples E::posure Pathway and Sampling and Type and Frequency' S_ ample Locations
- Collection Frequency of Analysis and/or Sample a
l 3.
WATERBORNE p
a.
Surface
. Goed4ene-9-and-M}-
Composite
- sample collected Gama isotopic analysis over. a period of < 31 days.
of each'tomposite sample.
~ n i %Ign )f,f
- 37l]'l (r.
Mi 3 d,,
Tritium analysis of com-
~
e 4
posite sample,,at-Jea C o
i ~d' & ~ k )
ww-remay1C4f
%$,? JCRn : nm (ofj%& 3 b
Ground (boca-t4 ens-il-aM At least once per 92 days.
Gama4sotop4t-and-M4ubNpde,' 60 Nat/ddf/2M%ovdh<2r[fh,fp,/
tritium analysds of-eech-
- kNN
- lVt J/<[$t f
hf AfAYN S & Me$~
p 5
j.
-cy-Dr-ink 4ng noc-atwns / Composite
- sample collected 1-131' analysis
( over a period of < 14 days, of each composite sample;
~
3
{
if I-13.1 analysis is and-l performed; or
. jlomposite* sample qollected l
Gross b./
eta and gama xover a period of _31 days.
iso ~ topic analysis of
}[ Tritium analysis'of each composite sample, j
3 composite sample at least g
I; j.,
.n, N once_pe.r'92 days.
j
.i
.s
,2
}'
C, tL 5ediment from
{Locotivns1.,}-
Atleastonceper484 days)
Gamma isotopic analysis L.
Shoreline of m ch cample.
mbc$r' &$rn /}*l~lh (nl:l&
3 e & ~$itAm,)
-l
- ~ Composite.sampTes shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. M#dd h f!
^'Senyle lecei.iun5 &rc%n-on-F49ure -2 A 2 4. Q 9
.f M g'
l A p cdMa,w nJ^ALgrpaund,a 4 4,
1 -,
4
't t
TABLE 3.12-1 (Continued)
~.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f
j q
.j
[
Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations **-
Collection Frequency of Analysis i
4.
INGESTION a.
Milk 4 toc + tic.b 17-20)-
At least once per 15 days Gama isotopic and
{ ;I JMboh dtiv I sfkW f)e '
( $ @ - 6. LMde at least once per 31. days of--oach sample.
t' when animals are on pasture; l-131 analysis i
(; M MIE4w !,((#A 8ne'm (ENf-/Imth at other times.
5' b.
Fish-end
(-Loca44o63 Ei and 22T One j 6ple'i,n d sor., or at Gama isotopic analysis 1-nvertebrates least once'per 184 days if,
on edible portions.
not seaional. One, sample of Ah J/,)
t w /<tf4 /-
j ea.ch'of the following; species k'
tlAncbsa7g b
/~~~)'N.'"~'
ctf l/
?
M w"
f 1.
AhUw!
lstni 0
\\. __2,/
fX time of harvest,- Oiie Gamma isotopic analysis i s{ ample [of each,0f the fpl-g, food-heduet+-
(-becatioC3-20t f
on edible portion.
pg g 10.)n classes of__ food fgf Y"
5^ A Y edn) W "* "h'^^f~ M "" /~1 Y n a Y A cl 5 (] h : 4TI12. (A m, ly kau &c,,;-wns.(sy+l}AQ l~ih +*v~)
/
/-
/.
cd,
(4.uca U un 20 at t<imes r
p 1-131 anaNis.
$0.l Nt$ W 0)/SW -1.0~k] "kSt t$o_n ry~
i, We--tocations-ere--shown-en-F-igure-3el4-1--
i 1 % :l % S tih v,'..$ N.$ % T / s c $<r & T A cl h l 0 A W. 1 0 & Y A A Sc c $ h.e 1 & '
A-c.. x..a wA m...r,,,u,..;il b rL u,,,
a s t;6 9
... f' r
^~--- - - -=
~
i, 3.12 - 2 TABLE 6PJ:t 3
REPORTING LEVELS FOR RA010 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES A
G i
1, Reporting Levels Airborne Particulate Fish Milk Vegetables Il tm Analysis Water or Gases (pCi/m3)
(pCi/Kg, wet)
(pCi/1)
(pCi/Kg, wet) t q
(h6/4V 11 - 3 3 x 10 W
3 g
Mn-54 7 x 10
.l1x10.
2 4
Fe-59 IM x 10 31: x 10 D
4 Co-58 21 x 10 8 3.x 10
\\
2 4
"M Co-60
'71 x 10 A 'k x 10 4
Zn-65 I 1x 10 61 x 10 t
2 Zr-fib-95 C) % x 10 l-131 1M p. t-
~7 1 M x 102 Cs-134 (i(:30 3 0 +e 6%x.10 14m/f m0 ;
3 3
3 Cs-137
/ A5010 3 0 20 9 1 x 10
$ fJ0-10
& '[
2 2
Ba-La-140 y 2 x 10 5,3 x 10 yc/J.
- x.. u -..w m. w. - _... -
-........ ~ - -
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4 I
N N
s.
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s N.
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Figure 3.12-1
/
g Radiological Environmental Monitoring Sample' locations
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3/4 12-6
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BWR-STS-1
../
G.
6.*%
y.
g g e.y g g.. awe,
,gggg
,g
,, g
p.y I.
~
TABLE 4.12-1 NOMl//AL y
-HAtlHUft VALUES FOR THE LOWER LIMITS OF DETECTION (LLD),
r m
f6 ll em
.h Airborne Particulate t
- '('
Water orGa3 Fish Milk Food-Products-Sediment i
Analysis (pCi/1)
(pCi/m )
(pCi/kg, wet)
(pCi/l)
(pCi/kg, wet)
(pCi/kg, dry) l f
S K X 10-2 gross beta 2
3H 330<7090 '
i l54 Mn 13 130 1
j f
59 Fe 30
'260 Co 15 130 58,60 w
65 260
]
Zn 3g 5
95 Zr.t(b 19 30 I
OdW
-2 15 Or8
{
(02N D
7 X 10 134,1,3?Cs
- ._] 5 FJ_X_]0~_2 130 15 150 __
ISTG _
j3
( x f o L.. _
- 5 g-1r cso l
a 140 j
W Ba-La 15 75
.e s
GCI NC/)
bal ()
. k howtk c(ch d.h Cs u,0(j / Y
(
~
G 4'
thec br C'kl Y MY$
ild et(cd
% +P M
W })ph dth)A A u lActud Qutr/nsk$, $LLDlg d -)] ) d 1,5' f C /]
i, a~A tle LL O fe aw2a k}1 tk T 4l'- /0
P j
- l
..f f
TABLE 4.12-1 (Continued)
TABLE NOTATION _
Tne LLD is the smallest ccncentration of radioactive material in a sample that will be detected with 95% probability with a
only 5% probability of falsely concluding its presencet.
For a particular measurement system (which may include radio-chemical separation):
4.66 s I
LLD =
b exp(-Aat)
Y 2.22 V
E 4
where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) is the standard deviation of the background counting sb rate or of the counting rate of a blank sample as appro-priate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular sed time bet een samole c llection radionuclide
(
at is the
}& %d"fa4the cal ulation of lhe LLD The value#olf sb used i
& 1 C<
system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically In calculating the LLD for a radionuclide predicted variance.
determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally presenf-in the sampTes- (e.g., potassium 40.in milk p.
samples).
s-
~
ee
.T.-
7.
3/4 12-8 l
BWP-ST S-I em*
~
w
. en i
--,..t
,,. f. _, :. _.
n..
~
l...
i 1
TABLE 4.12-1 (Continued) 1 i
TABLE NOTATION j
l x
- m a nung e.
N LLDs for I-131in water, milk.and other food products correspond c __. -
to one-quarter of the Appendix I (10 CFR Part 50) design objec-tive dose-equivalent of'15 mrem / year for atmospheric releases and 10 mrem / year for.. liq' id releases to the most sensitive organ u
and individual'using the assumptions given in Regulatory Guide
'l 1.109 7 '
~
\\
d
- r-t-1:D-kMerfy vegetables r-
\\
0
- D(nb Measurements of principal gama emitters for liquid and gaseous effluent analyses shall be performed using measurement systems and methods which have the o
following minimum performance specifications:
energy resolution < 3.0 kev FWHM for the 1332 kev gama-ray of Co-60. '
1.
Gama-ray uti/mi for'Tc-99m and Co-60 t
d 2.
Interference-free LLQ capabilities.of 5 x 10 (liquid) and 1 x 10- pCi/ml for Xe-133 and Ar-41 (gases).
(
The LLD capability shall be attainable for the sample geometry, background. counting time, and counting cond'tions which are representative of actual effluent activity i
I analysis conditions.
Background count rate is calcu-lated from the background counts determined to be within !.; rn "WM energy band f
about the energy of the gamma ray peak used for quantitative n :ysis for that, radionuclide.
(
i l
1 BWR-STS-I 3/4 12-9 I
I l
0
.I
~..
l RADIOLOGICAL ENVIRONMENTAL MONITORING _
f 3/4.12.2 LAND USE CENSUS j
f LIMITING CONDITION FOR OPERATION (j'aw&
A land use census shall be,,gonducted and[shall identify the 3.12.2 location of the nearest milk animalfthe nearest residence and-the
/
nearest-garden *-of-greater-than-500-squace feet-produc4ng-fresh-leafy vegetaldes in each of the 16 meteorological sectors within a distance of r
five miles.
(Sor--el-ented-releases as-defined-in-Regulatory-Guide' h-ll4,-March-1976.
The land use census shall also identify the loca-tions of all milk animals ar.d al'-gardens-of-greater-than-500-square-feet-producing-feesh-leafy-vegetables in each of the 16 meteorological sectorswithinadistanceofthreemiles.)
APPLICABILITY: At all times.
i ACTION:
$.eN With a land use' census identifying. a location (s) which yields a.
a calculated dose or dose commitment greater than the values currently being calculated in Specification 4714.-2.3.1,
'J. //. 2. 3, prepare-and submit to the Comission within 30 days, pursuant to Specification 6.9.2, a 'oecial Report which identifies the Lwlocation(s).
u b.
Wi-tti a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit to the Commission within 30 days, fies pursuant to Specification 6.9.2, a Special Report which iden the new location.
The new location shall be added to the M
radiological environmental monitoring program within 30-days
-\\
, The sampling location having the lowest calculated dose or 7.-
Mt Vm dose commitment (via the same exposure pathway) may\\Te'ife~Ieted Q
from this monitoring program. affer -(13ctober-31)M-the yeaW wh.ich -this-4and-use-<ensus-was-conductedi The provisions of Specifications 3.0.3 and 3.0.4 are not c.
~;_.
applicable.
d.*.~.. w Broad l'eaf ~ vegetation sampling Say-teMmed at the site.boundaryin i
the direction sectacyith-the~ highest D/Q in Tieu.of-the'$rden census.\\
E e
h-BWR-STS-I 3/4 12-10 m
fY E
,D/
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s
~
yfn L.-
e m......... p. +.. _._...... _.
- -........... - - - -. - - - - -... - - - - - -., - ~ ~ ~
.l o
t RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 q
months between._the-dates-of-(4une-1--and-Octot'er-t) by a door-to-doormgf i
g local agriculture authorities, o survey e
survey c
4.12.2.2 Reports - he results of the land use census shall be included in the Annual Radiological Environmental. Operating Report.
4 4
0 e
9
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I.
e-*e ees e,
" Y l-l -
I 3/4 12-11
~
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- - + - *.... - - * * ~ - -
- __ [..
m.,
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i
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{
RADIOLOGICAL ENVIRONMENTAL MONITORING
,/
i
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3/4.12.3 CROSSCHECK PROGRAM
\\
LIMITING CONDITION FOR OPERATION
/
1 x
3.12.3 An.alyses shall be performed on radioactive materials supplied as part of the Environmental Protection Agency's (EPA's') Environmental Radioactivity Laboratory Intercomparisons Studies /(Crosscheck) Program that are als'o included in Table 3.12-1.
/
APPLICABILITY: At all times.
ACTION:
With analyses not being performed as required above, report a.
the corrective actions taken'to prevent a recurrence to the
\\
Commission \\in the Annual Ra'diological Environmental Operating Report.
b.
The provisions'of Specifications 3.0.3 and 3.0.4 are not applicable.
/
\\'
SURVEILLANCE REQUIREMENTS / \\
/
\\
4.12.3 The results o.f analyses performed as part of the above required crosscheck program hall be included in the Annual Radiological Environmental Operating Report.
\\
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174=l2-I2~
~ '.
BWR-STS-I t
S-e
,3/4.12 RADIOLOGICAL. ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring progr4m required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements th radiological effluent monitoring program by verify 4n0 that-the-measur,e able concentrations of radioactive materials and levels of radiation hQwMhaut higher-then expected on the basis of the effluent measurements, and
/
modeling of th_e environmeo_tA1. exposure _.p.alhways. JThe 1 _tTil-1 ecffied ino itoringgrogram will be eff5R.tfvPfor-atleast th 1rst three ears Fpil' wing this pe'riod,Trogram changes may be 6
!o commercial pe ra tion.
t__nitiated base son oper.ational experiencef The detection capabilities required by Table 4.12-1~ are ate-of-the-art for routine environmental measurements in industrial laboratories.
The spec d lower limits of detection for I-131 in water, milk and other A4f. i food products Goecespond-to-appr.ox4mately-one-quarter--GE the Appendix I to 10 CFR Part 50 design objective dose-equivalent of 15 mrem / year for atnospheric releases and 10 mrem / year for liquid releases to the most sensitive organ and individual.
They are based on the assumptions given
~'
((/ r' Tn'Wg~illit5Fy Giiidi l~.1097/" Calculation of Annual Doses to Man from
~
f I
Routine Releases of Reactor Effluents for the Purpose of Evaluating k
j Compliance with 10 CFR Part 50, Appendix I," Marsh-197&r-excer :-the-
+ha nge-fo r-a n-i n fa nt-co n s u mi n g-330-Mte rsfye a r--o f-d ri n k4 n g-wa t er-i ns t e a d of--510 -I i ten /ye ar, (p@ ltl 'l'),
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the result's of this census.
This census satisfies the requjrements of Section IV.B.3 of Appendix I lo._lD_CER._ Ear.t 50. fitestri.cting the census to ga73 ens oFgreater than
-T 500 square feet providet sssurance.that significant,eipo,sur.e pathways via\\
sizef s the minimum,r'equired to produce the quan'tity-leafy vegetables will,Ise= identified ar.J monitored /since-a garden of this
^
i vegetables assume,d 'in Regulatory Guide l.109'for consumption by a chird.
j-To ' determine this' minimum garden sizei the following assumptions we're H
used,1) that. 20% of the-garden was. used. for rowing broad'leafd egetation i
l.
(i.e., similar to lettece_and cabbageL. and 2 a vegetation.yi' eld of f~~.-
2 kg/ square meter. _
.. ' ' _ _ ___. _.- -+
i cap
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BWR-STS-!
L3/4 12-1 l
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' RADIOLOGICAL.EtWIRONMENTAL MONITORING f'
i
'N,
BASES
. i.
3/4.12.3 CROSSCHECK PROGRAM N
\\
The requirement fo/r participation in the EPA.crosscheck program is provided to ensureftnat independent checks on the p'recision and accuracy of the measuremen'ts of radioactive material in environi6 ental sample matrices are performed.a's part of the quality assurance program for' environmental nonitoring,i'n order to demonstrate that the results are reasonably-val,id.
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d BWR-STS-I STANDARD TECHNICAL SPECIFICATIONS
(
SECTION 6.0 ADMINISTRATIVE CONTROLS O
- s
- t b
e 6
=.
l
~
etcept for fertions 0-f rde.
r-adrofyiczl enviremmont2.1
}
mensweny q m a s desero b<4 helw.
1 4
6.0 ADMINISTRATIVE CONTROLS
.j
^
6.1 RESPONSIBILITY PJsnr 61u The ('"cnt SupHyer-ntendent) shall be responsible for overall
@.1 unir. operation &and sha,' delegate in writing the succession to this responsibility during his absence.
t (a,J.2 T e Manager crP Enran~curlA#13. n respusoft %r sup q
'"*"T
' 3 '
' k 62 orb [12AYI6N 3/4.12. ] ud -for c onduc tsn3 rf e 14 u s < c en su.s
'5N'
'" M* 'mim W.12. 2 0FFSITE 6.2.1 The offsite organization for unit managenent and technical support shall be as shown on Figure 0.21. 4.2.l-l.
UNIT STAFF 4, 2. 2 - 1 6.2.2 The unit organization shall be as shown on Figure 5.2 2 and:
Each on duty shift shall be composed of at least the minimum a.
shift crew composition shown in Table 5.2 h 4.2.2-l b.
At least one licensed Operator shall be in the control room when fuel is in the reactor, At least two licensed Operators shall be present in the c.
control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor, e.
All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsi-bilities during this operation.
Mn Fore r w,
n f.
Agit: F're Erigcdc of at least 5 members shall be maintained..
onsite at all times. The Fir Srigcdc shall not include -(4t-
= ber cf the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
resyon sible for aS>5cSSrng tbc M lr 3 Tl1e NucIcar Enjince r-os fc>dts cA tbc reduoloync14 enrcn,vental wurMI ny prog 7w und -lhe e ntq rhe u,,a:I rulwlogica an ysronme.,rg garve:He
- terwy, BWR-STS-I l
4 f.
PRESIDD;7 v
{g if EXhCtTrIVE VICE P'. SIDE'.*I i
/N SciIOR Q
I
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VICE PRESIDENT i Vi ch FM.'!51D8NT -
POWER SUPPLY !
L D*G! ([ 51RWc6 POW 6 Sil/M Y f 5 SAFEYRE'/IP!! TECHNICAL
!VICEPDESIDE v.A ;ACIT. of BOARD
[-; SUFPGRT lPOWERGENERATION--~~]cUALI-y 4SSrRA.;cEl c ;;,g,p,wg,, y,g l
Fr.ws4 s frp4 y l
S NW'6 MANAGER t..______.a.________,
POWER GENERATION l
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l w(,wtx hN v@*Ix AFM:sf e.
arwen 6 AD:xi i
PLANT otAL: y a
lg MANAGER
- r. - -- a. -.AS SLtSCI
).
i....___...__..........-----
v SITC S UP&RVISOR pSISTANTPLANT PLANT MANAGER
REVIEW BOARG 1
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itECiiLIST P.A;ERIALS H!AL E SU"*-
et -
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PUSICS
'ERhTCES'
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LRADIOCHEMI S,..,
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i i
- ...._..___..t...._____s_...--_.-t-_..--
, Eqi CP' LF l SIST,'}
usts os atsrewsiniute
.... psts or c w%otew Figure 6.2.1 1 4
OFFSITE ORGANIZATION HATCH - UNIT 2 6-2 9
i i
/
m p
l OUALITY[
tl.^Nf, n ASSuRANct
~ ~ ~~
srCuany
__._ m _
PfANAt:1:It 5;n L! PT l~
stre SurrRvnson ASS r.Ufd Y
Pl.AN r
_ _HAN A.CER -
3 I
I L
SETII0l{.N,
~ stiti."ITr~
I HATEMIAI.
SUP T. OITri,)
StIPT. P l.T..
J C l f.C.
I I
E II. P. d FORIMN@
. IAIN,Tl:taAN :n Ly4C.St.R[RD
~
RAulOt'IIDII SI)
Ol' ERAT I O*l.'O
-4 l
N M
l~
I I
I I
LABORA1t;li/g OPFHAIl15%~
'MA I NTI.H ANCl; [
lllElitU. l q SENIOR (
ENGIN.
REGULATORY ros;i.:IA?1 SIIPERVISOR SUPERVISOR AND TRAINING STAFF SPECI ALISL fN
_.1
( __.. _.. !.S*O lU r.ONT. SttPER.
SPECIALIST IL MAIN 1158 ANCI INSTittitlENT I E I M i[
SillrT CHDilS1RY TORI.flAll__
FOR0f TAN _.
FORDtAll TECllNICI AN lSitol lN k
9 Pl.htiQ RO MAI NTr.N ANCE..INSTRUMENd
_O_P.L.I:_A rnd_~
Mr.i_1__.N.
__T_F._r_il.N.I_C.I. A.N.S_
isnc 'te ase ae,= ice'"ent.
ASSIT"T Pl. ANT ~
No. In Classification
{
SRO - Senior Reactor Operator
, OPI'.H A10R RO - Reactor Operator N - None Required Pl.AN1}II r.Qlll l' HEN I
_ OPERATOR Either the Plant Manager or Assistant riant linnager will obtain a Senior Reactor Operator's License.
I.ines of Responsibility
.----------------- I.ines of Corcunication Figure 6.2.2-1 IINIT ORGANIZATION e
- i l
- q(
TABLE C 2 1 4,2,2 -f
- j
~
MINIMUM SHIFT CREW COMPOSITION
- Re sexor Pe" Comds t wn cri u mor 2. -
U m,r I
um Otwatum, Hot 5ts,dby or Har S 4uidavn W ortan LICENSE APPLICABLE MODES CATEGORY l
1,2,34 4 E 5 4 40 dt SOL 4+ 1
-+* 2#
Mgg OL O 3 4 '
.,. } h Non-Licensed
+3
+3
(
)
.. M_e
- Does not include the licensed Senior Reactor Operator or Senior Q
Reactor Operator Limited to Fuel Handling, supervising CORE E
ALTERATIONS.
]g
- A ssumes sQ individual is licensed on b6 kmts.
- Shift crew compositionamay be less than the minimum requirements o#f for a period or ume $t to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table in-B-b 6 2.2-1.
J C omdtten crP %r 2 - %r I in Cold SAaxion or Rdel Modt
~
Cond &
LICEN$E APPIICAllt E BODt.S C A Tf40A Y l; 2, 3 4AS SOL
- 2 I*
l' OL 2
2 U
Non - keen 3c4 3
3 M b'I ' " "' '
Cc>< dst wn d Un't l I CM'st APP).lc abs E h0DLs ch76holtY 12;3 4 M 5~
3 SQL' I
I*
BWR-STS-I
- rF l Von ~ L ut< nsed 2-I u
e u.
ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS fo/me.ber of he n'. s*4ff.ay eseci[ fed Mi im.
a if a on ANS N1.1-1 71 e f n ve 11 queJifi at' n s ate en re ere cin or 1 er at y y ec yi i
ivi ual po iti n ali ca ons G er-1, e
ir o m tho is re era e; o ver, t se nd.eth d i d
19 o hqse u it taf s r qui in sp ia qua ifi ati s teme s t)/c.tsej6f uryiou or niz tio al tr ctu e.
Each member of the unit staff shall meet or exceed the minimum 6.3.1 for comparable positions, except for qualifications of ANSI N18.1-1971W m ;e-) who shall meet or exceed the quali-i fe diatic-D-etect ca t
e tions of Regulatory Guide 1.8, September 1975.
Hesit ) Physrcust-Radnochemos+
l
-(
Semor M<ekts ud Tmq tatus+
S 6.4 TRAINING A retraining and replacement training ogram for the unit staff 6.4.1 shall be maintained under the direction of the (p :iti;n title) and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
N<. Pron.e.tsem 6.4.2 A training prooram for the circ S-f;: S shall be maintained under
} and shall meet or exceed the require-a mentsofSection27obp;5fticrtiticode - 1975, except for Tir: Srig:t fi<< pro the direction of the e "Da training sessions which shall b eld at least once per 92 days.
S ensor R ularwy Speus hst-9 6.5 REVIEW AND AUDIT T
the by w 'ch ind enden
.evie and au t of f ility eratio ace,lish may e one f sev al for The icens may ei er ss' thi uncti to a organi tiona unit s rate d indep dent f
the roup sing rp ponsi ity f unit eratio or may ilize sta ing co.ittee mpose of ind' iduals rom wi in and utside e
lic see's ganiz lon.
Irres.ctive the m hod us
, the
'censee all sp' cify t detail of ch fun.ional ement ovided or the ndepen nt rev' w and dit ocess 3 illus+ ated iy he fol wing e.mple s _cifica ons.
6.5.1 U":- ",:'/::' : :Ur 'U1:P Pl.A N T REYJEW BOArto (PR/3)
FUNCTION Mut % er PRB 9
6.5.1.1 The (Uri 1:.ica C. ap' shall function to advise the3(Fl;nt p
Sv;;rintcri..t} on all matters related to nuclear safety.
6-5 l
BWR-STS-I l
\\
.o.
- j s
.j ADMINISTRATIVE CONTROLS
.i COMPOSITION PRB 6.5.1.2 The (Ur't ".ic;. Crcup) shall be composed of the:
Chaiman-(Pl:nt Superintendent) Pla,ir Mmpe Mede kne. C4urwaw (Operatj n: Supcryi: r) Assiseant P/we Ma=P Member:
(Tcchnicci Supervi:Or) o p rartc u S f a M N '
I Member: Supw.n t ud44 r
{M inten:nt: Sup0rvicer) PI'af 64' " 'T " '*#
i.rN((Plant Instru ent :nd Control Engin;;r)oe-Member: Ma,rtus f.,
~
Plant "ucle:r En;inecr) Cowe<di frecislist
/
Member:St.,or out,,7 JHealth Physicist 7 AsdecAsmst Member:
ALTERNATES
[
6.3.1.3 All alternate members shall be appointed in writing by the M6 4AG4. Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in (UP.:) activities at any one time, IRS MEETING FREQUENCY PR6 6.5.1.4 The (UCC) shall meet at least once per calendar month and as convened by the '".:) Chairman or his designated alternate.
No i
QUORUM PRS PRS 6.5(.1.5 The minimum quorum of the $RG-) necessary for the perfortrance of
(
1he10CC)-responsibility and authority provisions of these Technical Specifications shall consist of the Chairman er 'i: d :#gn:ted :ltern:tc and Ms. members including alternates.
T4ree RESPONSIBILITIES l
Plant Revuew &an$
l 6.5.1.6 The 1" a ' t % " ' c': N eup) shall be responsible for:
Reviewof(l)allproceduresrequiredbySpecification6.8and a.
changestherete(2)anyotherproposedproceduresorchanges j
Plent ;
- -tendent}- to affect thereto as dete mined by the (Phne Ma;napr nuclear safety.
I b.
Review of all proposed tests and experiments that affect nuclear safety.
excep Fbe rkse. pwc.cchres us 6 8,t.b Ad +=
- u,aee clue. y,um a r42. Pia: n,ye.r, BUR-STS-1 6-6
4 i..,
i ADMINISTRATIVE CONTROLS I'
(
1 g
i Review of all proposed changes to Appendix "A" Technical
'/
c.
j Specifications.
y d.
Review of all proposed changes or modifications to unit systems s
c or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications 4t e.
including the preparation and forwarding of reports covering t
evaluation and recomendation's to prevent recurrence to the p
(Super'-tend;-t of Dr.cr "1;nt ) and to the (C =p;n) ':::l r -
t f
":,ie :nd tudit St-ca;Q, $&y Ren,< BM Oga).
b.
f.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
Review of unit operations to detect potential nuclear safety i
\\
g.
hazards.
Plae Munw h.
Perfomance of special reviews, in stigations or analyses and reports thereon as requested by th (P1:nt Sup;rint nd:nt) or the (C:mp;ny *:ucitar ".r;ic,. and Sudit Crcup). Sad.
1.
Review of the Security Plan and implementing procedures and shall submit recomended changes to the (C: p n3 "uci:;r P.r.ir..
- r.d
- ud i t Cr;up'. SR6.
Review of the Emergency Plan and implementing procedures and j.
shall submit recomended changes to the (C:mp;ny ':ucic;r "r.ir, and Audit Crcu;).
S#6.
AUTHORITY _
(
6.5.1.7 The (L'rit 9c'/in Crcup) shall:
b to fle Plw Mu wremy:nt Suptr'. tend:nt)yw-itt:n approval or s >s
(?.
Recommend tc th:
a.
4 disapproval of items considered under 6.5.1,.6(a) through (d) above.
b.
Render deteminations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
/1u yretOwv Seweestm Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the3(Super intendent of ":.;: "1:nt:) and the (C:rp;ny ':u& 9:'/ir 2nd-540 c.
tudit Crcup) of disagreement between the -R-RC-)Ynd t
(. :nt 4 'nt nd;
}; however, the (P1:nt Sup;-int ndent) s all Pl w M q.c-
.. = responsibility for re ution of such disagreemen s pursuant to 6.1.1 above.
. pjg,,e Mgviger-g 6-7 BWR-STS-1
- e..
l ADMINISTRATIVE CONTROLS r
i RECORDS Pkr Essw 8024 6.5.1.8 The (U 4t oceic> C cu;} shall maintain written minutes of each Pf6
%E) meeting that, at a minimum, document the results of all -{Wes) PK6 3
activities perfonned under the responsibility and authority provisions of these Technical Specifications.
Copies shall be provided to the (Sere 4-te-deat c' 0 'e
$'Irt:) an heA(Ccrp ny "uck r h is cr.d
%di t Crom;). Mevy ot 6 y Ge. wane, VSaky Revics d.M.
SAFETY RLVIEW GOAK D (SRB) 6.5.2 CCf'PA* " t:U '.: ' n:v :L'," C AUCIT CnC"r (: :nAC)
FUNCTION srb
- 6. 5. 2.1 The3(C:np ny 'a:1c c nc.ne,, ;c.d AsJ-:. 1 vsg) shall function to provide independent review and audit of designated activities in the 1
areas of:
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radi:; chemistry d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices (cther ap; cprin: 'iclu:
- cci ::d ith the u-ique ch:r
- ter r'4 : c' tM uc' car p wcr p':.t) 4 i
l l
l m
l 8
BWP. '.,TS-1 6-8
6 ADMINISTRATIVE CONTR01.5 COMPOSITION SR6 6.5.2.2 The (CNC} shall be composed of W. a wwwuw of Seven persoe who ss a yrwp provde ric cepertise to rc<new s4 eadst the efeterten of. a muc. leer ;
(Poe it4cr. Titic) p.n 5< r/ur. tac c.Aa,,we, w) y,cc c4-w
-Directe -
r 14embera (Pos.144ea T4 t4) ed or4<< me Ac"s 5 4a/I de, appmR4 by tie.
(%s4ticr 'iti:
St aie c V8 CS Pr*5'd. r; / W., L pply or (PoMt4cn Tit!:lChguy
- P. ember -
, suc 4 ar4er perscw as 4c S4& / a/e+9mrc..
/
Mer3er:
Me-be--
(Sc:1ticr Titic} T4e compa ser'aw of rfe fnd S42/1 we efe reeworements cf A NS1 N if. 7 ~l S76.
ALTERNATES All alternate members shall be appointed in writing by the absent 6.5.2.3 w he r (C"C) Ci ::ter to serve on a temporary basis; however, no more than two alternates shall participate at voti";
e-be"? in 'C""".C) activities SNO at any one time.
CONSULTANTS SRB Cf wmn ew 6.5.2.4 Consultants shall be utilized as determined by the (CNTJC)
Di-~ to-to provide expert advice to they(ggg.Ch CNY ece (.haiv m 3 MEETING FRE0VENCY SR6 The (CNIAC' shall meet at least once per calendar quarter 6.5.2.5 during the initial year of unit operation following fuel loading and at least once per six n.onths thereafter.
(
QUORUM SRO SR6 6.5.2.6 The minimum quorum of the-(CN.0) necessary for the p_erformance of the -(C?nAC) review and audit functions of these Technical Specifica-tions shall consist of the40#-ect:- er hi: designated :lt rn:t and Tat leasW CD^*C} members i-d eding alte--ste:.
No more than a minority of e quorum shall hav line responsibility for operation of the faci'4t; j"'"#
- 3 540 C4wws, or Vic.c. Chw*ew i
l l
InM.,Tf.-I 6-9
. e.,
ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The 44NRAG4 shall review:
a.
The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed
(
safety question as defined in Section 50.59, 10 CFR.
d.
ProposedchangestoTechnicalSpecificationsobthisOperating
- License, e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating cbnormalities or deviations from normal and expected performance of unit equiptent that affect nuclear
- safety, g.
Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems,
(
or components that could affect nuclear safety.
e 1.
Reports and meetings minutes of the ("r.it Pc'/ic.- Creup).
Ph,c Revw Bo24.
{
l 1
1 BWR-STS-I 6-10
I ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit activities shall be perfomed under the cognizance of the -lCSAC). These audits shall encompass:
SR6 a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire unit staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The perfomance of activities required by the Oper:ti:r.:1 Quality Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months, The Emergency Plan and implementing procedures at least once e.
per 24 months.
f.
The Security Plan and implementing procedures at least once per 24 months.
c g, g:
Anyotherareaofunitoperationconsideredappropriateby they 1,0) or thEv( '
I dgt
- r
- 0 g h:
The Fire Protection Program and implementing procedures at
(
least once per 24 months.
h #.
An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an,outside fire protection firm.
ig.
An inspection and audit of the fire protectilon and loss preven-tion program shall be perfomed by an outside qualified fire consultant at intervals no greater than 3 years.
jA'.
The radiological environmental monitoring program and the results there of at least once perA+ months.
v 1
BWR-STS-I 6-11 L
e ACMINISTRATIVE CONTROLS AUTHORITY beme Voce. hobn Arce SRB h fY f
6.5.2.9 The (CNPsAC} shall report to and advise the4("ica Presid;nt Operation:) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS SR6 6.5.2.10 Records of (CNPAC) activities shall be prepared, approved and distributed as indicated below:
SR6 Minutes of each -(CMPf.C) meeting shall be prepared, approved a.
and forwarded to th TVicePresident/per:ti;n:}within14 days following eac eeting.
5"L /'y
/
S eno r-Se,, e b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and for~arded to th {VicePresident-w 0 cration ) within 14 days following completion of the review.
f!**hPf1
%<e hppIf mpassedbySec[. ion 6.5.2.8above,shallbe I
my c.
Audit reports e forwarded to th Vice President t it' car) and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
The Commission shall be notified and/or a report sutraitted
(
a.
pursuant to the requirements of Specification 6.9.
r' Pt.6 b.
Each REPORTABLE OCCURRENCE requiring 24 ho r notification to the Commission shall be reviewed by the and submitted to the (CNPf,C) and the ( perint ndent of Pe m Pie..;5).
y y
pfu.,s p o f Rower Ge.ee n ri ~
SRS i
l BWR-STS-I 6-12
~
s
s ADMINISTRATIVE CONTROLS 6c7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety Limit is violated:
S*4 T DowN a.
The unit shall be placed in at least HOT ST"' M within One LCu-Two bOV?S.
b.
The Safety Limit violation shall be reported to the Comission, th
'Suce *ntendcat Of "c::cr Piants) and to the (CMPff) within 24WM19se & hwer Ccww"
^ SRB PRS c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by th ftE3t.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
S d.
The Safety Limi Violation Report shall be submitted to the Commission, th (C"P*C) and the.S(Supc "tendent of I; m -
'!:rt:) within 14 days of the violation. 'Magw df 4" A*'f*
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced belov:.
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, ~i.cc,, ':70. l Theary 1977.
('
j b.
The radiological environmental monitoring program.
c.
Refueling operations.
d.
Surveillance and test activities of safety related equipment, e.
Security Plan implementation.
f.
Emergency Plan implementation.
g.
Fire Protection Program implementation.
h.
Offsite releases of gaseous and liquid effluents containing radioactive materials.
i.
The PROCESS CONTROL PROGRAM for solidification of radioactive waste.
j.
The OFSite Oase C>lcalma 412wW -Fue calcw /2m> s to cun-STS-I hanrafe cep h2 =cc. 6-M with to cR 2a, / fp 4 J co 4
lo cFR 50, Q 40 cpg ago, a
s 2tupr kr riss yrocsdyre.) <& C.B. l. b w k oc h e,<r <. cw M nder 74 e coq mcs=ca,r9 v4c. Pla r hu y,
ADMINISTRATIVE CONTROLS PRB Q Pl u r M M
- f 6.8.2 Each pro edure of 6.8.1 above, and changes theret, shall be reviewed by the (LZ'i and approved by the}-?lcn'. Mi. intendcat) prior to implementation and reviewed periodically as set forth in administrative procedures. The Newnm riocedgres & C.B. J.b +d cAa9carkeroSM k rem.sd N symc4 by 14c. %gr & S mem tal k% er r4e hdm fyww q 6.8.3 Temporary changes to procedures of 6.8.
bove may be made pro-3-
vided:
The intent of the original procedure is not altered.
d.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
PRO The change is documented, reviewed by the -(F4} and approved by c.
mr! M:r"terdcrt) within 14 days of implementation.
the (Plz.cr flun29er 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable recortino requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that.may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions o'r characteristics obtained during the test program and a comparison of these values with design predictions and specifica-Any corrective actions that were required to obtain satisfactory tions.
Any additional specific details operation shall also be described.
required in license conditions based on other commitments shall be in-
~
cluded in this report.
6-14 BWR-STS-1
j
)
ADMINISTRATIVE CONTROLS
.i i
6.9.1.3 Startup reports shall be submitted within (1) 90 days following corFpletion of the startup test program, (2) 90 days following resumption or comencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does i
not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of cortmercial power operation), supplementary reports shall be submitted at least every three months until all three events haye been completed.
1/
ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be subnitted prior to March 1 of the year. following initial criticality.
Reports required on an annual basis shall include:
6.9.1.5 A tabulation on an annual basis of the number of station, a.
utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their.assogated man t
rem exposure according to work and job functions,-
e.g.,
reactor operations and surveillance, inservice inspection, routinemaintenance,specialmaintenance(describemaintenance),
waste processing, and refueling. The dose assignment to varicus duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.,
1 b.
The rc: ult; Of st = g ncr:ter tub: inscrtic: inspecti:n:
per'e-ed durin; +he repe*+ pe-4ed (CE.u t Rtu,,n4+e nnlyi barrel me'/=:nt monit:r%g :):ti"itie:
c.
The :: ult: Of the :Or per4ad (cEen4+e anly -
per#ce ed during the reper+
JAnyotherunituniquereportsrequiredonanannualbasis.]
I b #1' 1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the station.
2/- This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.
SWR-STS-I 6-15 l
' j i
, i ADMINISTRATIVE CONTROLS
'l MRVElLL MCE.
N ANNUAL RADIOLOGICAL ENVIRONMENTAL 20M'rr REPORT-PlM SurvesII>,,es 6.9.1.6 Routine ra ological environmental eper:U ng reports covering the operation of th nie. during the previous calendar year shall be submitted prior to May 1 of each year.
The 4-iti:1 cpert : hall bc A 9"([e t&4 ttad rier to "2y ' of th^ y=M Mo
- de W-1 tritiality.
r f0110 inc in'ti:
rwr1 hl4rls tfe ree.nregemrs %
6.9.1.7 The annual radiological environmental cpe est]nu.2.ing reporty shall Surr 3
include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveil-lance reports and an assessment of the observed impacts of the plant operation on the environment.
The report,r shall also include the results (bc] of. land use censuses required by Specification 3.12.2. I' h r-ful eff=t:
4 cuidem e c' 4 ~e'ec :4b!c dem:ge are detn t:d by the onit:rin;, the report th:11 provide :n :n:1.,si; cf the gi ubb end a piomed cuur :,e J ectier to e'!cviate th^ probitr.
TafrVti/I3 ace The annual radiological environmentalgp t# ; reportg shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as ec 45'c4 n a supplementary report.
i ern mls Thc cport: :h:1'
!:0 '
!ud: th: fellcain;.
- ; a :ry d= cripti:n of th; ;diclogici cn.ircr :nt:1 m;nitoring prc;rcr includin; nmplin; nthcd; fcr ach 30mpic typc, sin and phj:icci chrccuristims of cch nmpic typc, ::mpic ; reparat f or m;thods, pn *'ytial
- th;ds, and x; urin; ca ip-c.ent u3ed, c m p Of all nmp!'ng 10= tion
- ty:~d to : t;bi: gi.'ng dist: ce:
cod dir= tion: 'rc~ One ra ttor; the rc; ult; cf icnd usc ccasun; rcquirc4 t., the Speci' int #c-3.12.2; and the result; c' ' inn:= particip;ticr i r-t++ nvircnmental " etceti - ige-cy': E-"4rc-c-te' "ad4cact4"4ty Lebe-stor.y c
hitcrx pari;=: Studic: ' Crc: x h=h) "r;;r:r cqu ucd by :p ni'i cticn 3.12.0.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE rep 0RTM 6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. -%e reicd c' the #4-st report ea begi-
' ? t t d; u 0' '-itial critiality.
-'3/
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at th' e station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
BWR-STS-I 6-16
8
/
TABLE 6.9-1 f
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Docmat No.
Reporting Period Location of Facility ICounty, State)
Nutrdsor of Type and Lower Limit location with liighest Annud Mesa Conbot L lone gggy AllIndicefor Lp* tions Meifium or Peshway Yotal Numter of No-u,,, g,,6 u en lg 0CCURRENCES ueen(g e
s.msed on Anniv Deiecoon ts Heage (Unit of Measurstnentl Performed (LLDI Rea9 Disience end Direction ny Air Particulates (pCi/m )
Gross 0 416 0.003 0.08(200/312) fAiddletown 0.10(5/52) 0 08(8/104) 1 3
(0.0 5-2.01 5 miles 340*
(0.08 2.0)
(0 05-1.4of 7-Spec. 32 Cs 0.003 0.05 (4/24) smithvitte 0.08(2/4)
<tLD 4
I37 I
(0.03 0.13) 2.5 miles 160*
(0.03-0.13) o
~%
l E
140Da 0.003 0.03(2/24)
Podunk 0.05(2/4) 0.02(1/8) 1 g
(0.01-0.08) 4.0 miles 270*
(0.01-0.08) at n
m e
<LLD 0
O
%r 40 0.002
<LLD N
o e,
h
<LLD 0
- D Sr 40 0.0003
<LLD Fish pCi/kg (dry weight!
7-Spec. 8
<tLD 90 (1/4)
O 137
~
Cs 80
<LLD
<LLD
<tLD 0
Cs 80
<LLD Co 80 120 (3/4)
River Mile 35 See column 4 <LLD 0
(90-2001 Podunk River
' Nominal Lower Limit of Detection (LLD) as defined in table notation s.of Tehes4.121 of Specification 4.12.1.1.
I I'Mean and renee t>eind upon detectable --
_ - ts only. Fraction of dew unseeuremente et speelfled locetions le Indicated in parentfieses. (f) dNote: The esemple date are provided for illustrative purpoems only,
(
i 1
ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a sumary of the quantities of radioactive liquid and gaseous effluents -
and solid waste released from the unit ai outlined in Regulatory Guide KW. Iq 1.2% " Measuring, Evaluating, and Reporting Radioactivity in Solid d'3Thes and Releases of Radioactive Materials in Liquid and Gaseous Ef fluents from Light-Water-Cooled Nuclear Powcr Plants," with data sunnarized on a quarterly basis following the format of Appendix B thereof.
The radioactive effluent release reports shall include a sumary of the meteorological conditions ccacurrent 'ith the
!:::: Of ;;;;;;;
- ffluent during each quarter :: Outl'aed
'a hgel:tery Sid: ' ?!,
the fomat of with data summarized on a quarterly basis following /.
Appendix B thereof ap #epfsmy Sude /.2 /, ge.v.
The radicactiv u luent "e'eese "eport! rhel' include an !sM = nt of tha vadda*4 c-deser #-c radiractive efuents to individual: due te their ::tivitic: incide the unrestricted :rt: boundary (Figu. c
.1 1):
duriag the report per4cd_
n assu'ption: u: d 4-
- E4 9; th:::
- m:nt: (e.g., speci'ic :ti"ity, exposure tie and leration) : hall f
be included 4-there eports.
The radioactive effluent release reports shall include the following information for all unplanned offsite releases of radioactive materials in gaseous and liquid effluents:
a.
A description of the event and equipment involved.
b.
Cause(s) for the unplanned release.
c.
Actions taken to prevent recurrence.
d.
Consequences of the unplanned release.
l 7x w tw<.
]
The radioactive effluent release reports shall include ang ::::m:nt of rfe.
l i
%urm 4"1 radiation dosesefrom the radioactive liqui.d and gaseous effluents Mgulet-,gthe unit during each calendar quarter, H
.5 released f Re Sidc 1.21.
In addition, the unrestricted area boundary E
noble gas gamma air and beta air doses shall be evaluated. -The-J
' eter*rlogical cond4 +4cns cracurren* v4th the *e'earer c' e##1uents thcl' bO U:ed fC" de*e"~i"ing the nageggy 73thugy dcger, The 3:Seg;=ent c' radistica dore: chill it perf:;- cd ir :::rdant
. ith ".' REC 0133.
The 2.ssey,mW ($ fadiarm doso diall be. pWeA rn seud %CC.
wsrb de CW S,te Da cdwfum Mwel.
6-18 BWR-STS-I
E
^
s i
3
,j ADMINISTRATIVE CONTROLS q
N.;-]
MONTHLY M OPERATING REPORT 659.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and program Analysis, U.S. Nuclear Regulatory Cecrnission, Washington, D.C.
20555, with a copy to the Regional Office of Inspec-tion and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES 6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence.
shall be reported to the NRC.
Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confimed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days.
The written followup report shall include, as a minimum, e completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a.
Failure of the reactor protection system or other systems subject to limiting safety system-settings to initiate the required protective function by the time a monitored para-qeter reaches the setpoipt specified as the limiting safety J
system setting in the technical specifications or failure to complete the required protective function.
b.
Operation of the unit or affected systems Mhen any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.
c.
Abnomal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
s l
I l
Bv'R-STS-I
~
6-19 o
f
(
e ADMINISTRATIVE CONTROLS d.
Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to li ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifica-tions; short-term reactivity increa,es that correspor.d to a reactor period of less than 5 se:onds or, if subcritical, an unplanned reactivity insertion of more than 0.St ak/k; or occurrence of any' unplanned criticality.
e.
Failure or mifunction of one or mort components which prevents or could prevent, by itself, the fulfillment of the functienal requirements of systen(s) used to cope with accidents analyzed in the SAR.
(
f..
Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systens required to cope with accidents analyzed in
~
the SAR.
g.
Conditions arising'from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety sys*. ems, or other protective measures required by techrdcal cpeyif 7c4 ions.
s Errors discovered'in the transient or accident analyses or in h.
the rethods used for such anal /ses as described in the safety analpsis raport or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
i.
Perfonnance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in
,. s a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require re'nedial action or cor-l l q rective measure.s to prevent the existence or development cf an l
[
unsafe condition.
~
5
~
0 :;rren;; of er anssu;l cr imperient tv nt th:t ::u;;; c 3
ciy ' :3rt e 4-cr ert:1 4 ;
c*,
- hat
<<e-t: ;ct:-tic' 4
i s
7-cr' i :- ects' 4 nc: <-:- ur t c;er-t4c-er ot hu bi-k j
e t
pub'4: er p?ee+4 3 1 rA14c M ernt cr-er :-- c~'-creerta!
i
,x 4--,-.
er--
r-m.m.4n-
~
sc s
i n-
,rren-e a e,w,.
,,e
-,.or4,3
- -., 4 - e s 4,, 1 4,,,4 4 er 7
7.,,3
+c' dup ta w escu = 36. m + p p -itte by t,,:
tg gi i
14 4 s '
tic" #0" ep '"2 c" e st? bMshai-ir 'the _te-H i n! - eci <f c ti ~.:.
b, BWR-STS-I 6-20 a
3 4
I, y
L e
'd ADMINISTRATIVE CONTROLS 1
THIRTY DAY WRITTEN REPORTS 6.h.l.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Infonnation provided on the licensee event report form shall be'supplemerted, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
4 Reactor protection system or engineered safety feature instru-a.
ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of
.affected systems.
b.
Conditions leading to operation in a degraded mode permitted
~
by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.
Observed inadequacies in the implementation of administrative c.
or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
d.
Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.
penctf,,q Otssdived&chMf'7#9">
An unplanned offsite release of ( ) more than 1 curie of e.
radioactive material in liquid e-luents162) more than 150 curies of noble gas in gaseous
. uents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:
1.
A description of the event and equipment involved.
2.
Cause( ) for the unplanned release.
-3.
Actions taken to prevent recurrence.
4.
Consequences of the unplanned release.
t l
h s
BWR-STS-I 6-21
~
J ADMINISTRATIVE CONTROLS easured ' vels of ra activity in environmen 1 sampling ^
medium etennined t exceed the re rting level alues of Tabl
.9-2 when eraged over y calendar arter samplin pe od. When r re than one o the radionu ides in Table
.9-2 l
e detected n the sampli medium, thi report shall submitted 'f:
oncentration conc oration (2)
+
... 1 1.0 limit level
)
li 't level (2)
When radion ides other th those in Tab 6.9-2 are dete ed and are t. result of pla effluents, t s report shall submit +
if the poten 'al annual dos o an individua s
(
equa to or greater an the calend year limits of pecifica-
)
ti s 3.11.1.2, 3.
.2.2 and 3.11
.3.
This repor is not equired if the asured level radioactivity s not the result of plan effluents; ho ver, in such a event, the condition s i be reporte nd described i the Annual Radiologi Environment Operating Repo SPECIAL REPORTS Specia report may be r uired c ering insp.tions, te e and main-ten ce acti ties.
T se speci reports e determi d on an in v' ual bas' for eac unit and heir prep ation and ubmittal a esigna d in the 'echnical ecificatio s.
/
6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Of fice within the time period specified for each report.
{,
O chnrrcnce of %A M w u2) or svforr3*rt, sve,rr swlocf
-~
Sty wtEtcnnt <v wmmestt) suf ret. Exc.ludu{
t veses a.
k r4os spedicam t.s rc(x"ty o+ rhe dettettn of e vocleue c4 mclez r weefw dewnnw.
i l
~
i Ct:R-Cl s-[
6-22
a'
\\
TABLE 6.9-2 N
REPO illG LEVELS FOR RA010ACTrVJTY CONCENTRATIONS ENVIRONMENTAL SAMPLES Rep evels
)4}borneParticulate h(pCiQg, wet) fish 1k Vegetable Analysis Water or ses (pCi/m )
(pC 1)
(pCi/Kg, wet 3
\\
4 11 - 3 3
10 Mn-54 1 x 10 3 x 10 4
Fe-59 4 x 10 1 x 10 4
Co 58 1 x 10 x 10
?
Co-60 3 x 10 1x U
\\
\\
2 4
Zn-65 x 10 2 x 10 2
N Zr-Nb-95 4x 1-131 2
0.9 3
1 x 102 3
Cs-134 30 10 1 x 10 60 1 x 10 g
Cs-37 50 20 x 10 70 2 x 103 2
Ba-La-140 N 2 x 10 3 x 102 N
N y
i
Q i
J
~
t ADMINISTRATIVE CONTROLS I
l 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for t.t least five years:
Records and logs of unit operation covering time interval a.
at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipnent related to nuclear safety.
/
ALL REPORTABLE OCCURRENCES submitted to the Commission.
c.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by Specifica-e.
tion 6.8.1.
f.
Records of radioactive shipments.
Records of sealed source and fission detector leak tests and g.
- results, h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Unit Operating License:
Records and drawing changes reflecting unit design modifica-a.
tions made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
Records of radiation exposure for all individuals entering c.
radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
4 BWR-STS-I 6-24
'A-i
~
,2; L
I i
s
'i ADMINISTRATIVE CONTROLS e.
Records of transient of operational cycles for those unit cot-ponents identified in Table 5.7 1.
S,7,j-l.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the QA Manual.
(
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
PFhG SRB k.
Records of meetings of the feast and the (ONRAO'.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA (OTT'ONAL' 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
" Health Physics personnel or personnel escorted by Health Physics per-sonnel in accordance with approved emergency procedures shall be exempt from the RWP issuance requirement during the performance of their i
radiation protection duties, provided they comply with approved radia-tion protection procedures for entry into high radiation areas.
m BWR-STS-I S.25
\\
']bem.
\\
ADMINISTRATIVE CONTROLS A radiation monitoring device which continuously integrates the
~ b.
radiation dose rate in the area and alarms when a preset inte-grated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowl-edgeable of them.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
c.
This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified 4 6 9
the f::i'ity 90:lth ohysicist-in the Radiation Work Pennit.
The requirements of 6.12.1, above, shall also apply to each high 6.12.2 radiation area in which the intensity of radiation is greater than In addition, locked doors shall be provided to prevent 1000 mrem /hr.
unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Super"i:Or on duty and/or Fb erma*
the Plant Health Physicist.
/
J l
BWR-STS-I 6-26 t
l