Text

Forwards marked-up Revision to 820513 Radiological Effluent Tech Specs.Approval Requested by 830101 to Allow Effective Implementation of New Environ Protection Plan & Pending Tech Specs.Pages 1-5 & 1-6 to Be Forwarded Under Separate Cover
	ML17301A009
Person / Time
Site:	Saint Lucie
Issue date:	11/05/1982
From:	Robert E. Uhrig; FLORIDA POWER & LIGHT CO.
To:	Eisenhut D; Office of Nuclear Reactor Regulation
References
	L-82-490, NUDOCS 8211120440
	Download: ML17301A009 (127)
	v • d • e

DOCKET 05000335 NOTES:

REGULAT<

INFORNATION DISTRISUTIOA(STEM (RIDS)

! CE'SUION NBR:8211120400 DOCs DATE: 82/11/05 NOTARIZED:

YES FACIL:50 335 St, Lucie Plant~

Uni t 1~

F1 or'ida Power 8 Light Co ~

AUTH,NAME AUTHOR AFFILIATION UHRIGr R ~ Es Florida Power 8'ight Co, REC IP ~ NAME RECIPIENT AFFILIATION EISENHUT~D.G.

Division of Licensing

SUBJECT:

Forwards marked-up revision to 820513 radiological effluent Tech Specs'pproval requested by 830101 to allow effective implementation of new environ protection plan 3 pendinp Tech Specs. Pages 1

5 8

1-6 'to e forwarded nder separate cover

~

DISTRIBUTION CODE:

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SIZE R TITLE: Public Comment on Environmental Statement RECIPIENT ID CODE/NAME NRR ORB3 BC 06'ELSON'

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01 INTERNAL: ELD/HDS2 NRR/DE/AEAB

?0 NRR/DE/HGEB 21 NRR/DSI/AE8 19 NRR/DSI/RAB 17 RGN2 COPIES LTTR ENCL

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7 1

1 1

1 RECIPIENT ID CODE/NAME KREUTZERrPO NRR NORRISgJ NRR'/DE/EEB 16 NRR/DE/SAB 18 SB 15 REG FILE 04 COPIES LTTR ENCL 1

1 1

1 EXTERNAL:

ACRS NATL LAB 21 NSIC 05 6

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1 LPDR NRC PDR NTIS 03 02 1

1 1

1 TOTAL NUMBER OF COPIES REQUIRED:

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P. O. BOX 14000, JUNO BEACH, FL 33408 FLORIDAPOWER & LIGHTCOMPANY November 5, 1982 L-82-490 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Eisenhut:
Re:
St. Lucie Unit 1 Docket No. 50-335 Radiological Effluent Technical S ecifications Please find attached a revision of the Radiological Effluent Technical Specifications we submitted in L-82-201, dated May 13, 1982.
The Technical Specifications are in a marked up form as requested by your staff.
Pages 1-5 and 1-6 are not included with this revision because two definitions on these pages may change as a result of discussions con-cerning St. Lucie Unit 2.
These pages will be forwarded in a separate letter as soon as possible.
We request that these proposed amendments be approved effective January 1,
1983.
This will allow us to effectively coordinate the implementation of the new Environmental Protection Plan and the pending Technical Specifications for St. Lucie 2.
The additional time will also be necessary to allow for procedure writing and personnel training.
Very truly yours, Robert E. Uhrig Vice President Advanced System and Technology REU/JEM/cab Attachment cc:
Mr. James P. O'Rei lly, Region II Harold F. Reis, Esquire I'2lilromeo 82l<05 PDR ADOCK 05000335 P
PDR PEOPLE... SERVING PEOPLE
STATE OF FLORlDA
)
)
COUNTY OF DADE
)
ss Robert E. Uhri being first. duly sworn, deposes and s ays:
That, he is Vice President Light Company, the Licensee herein; of Florida Power That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Robert E. Uhrig Subscribed and sworn to before me 'this
<Hi OTARY ~UBLl in and for the County of Dade,
~Stat~ of,,Florida
"< f i
'i' a
Notary Public, State of Rortda at Large commission expires:
My commhsion Expires october 30 t983 on ru r aynar onding Agency
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DOSE EOUIVALEHT I-131 i
bd.".tflat concentra'on of I-131 t!".8~crocuries/
!se;sj!i'q thyroid dose as the qua <'l.'it~g and13"'."
I-134 and I-135 actual 1!j pr:~'~ent.
on s,
=-lii "I e< those Fac ons sos.
ower 1.10 tlsE EOUIYALEHT I-131 t al 1 gram)
. ".-.c" alone would produce t isota. '= ~ixture of I-131, I-132, C'he
>.'..cL nodose conversion iacto, ~ use liSt~;.,'in'L, kbie III Of TID-14844,1"..", Cal and "
0 ;or this calculati c.:~ation of Oi stance in p 'o'portion to the P
siE
-..'it r<s'-;:~,tor Sites."
u".RAG-1': 3 IHTEGRATIOH EltERGY:.'
co ncentratlon oi
."g) of tlje<sut s I.
f or'hall X.>=-'ythe average (we';:g lted each
'.adionucl ic!:.:"ein the reactor,. coolant at ", le tine of sampli il of t..".'..'t'verage b;-:..a and gamma ener.'gies per di, i'ntegration (in,i
)
iso>".,l3~es, other,'i:-;-'i iodines, wi;lf half lives>jireater than 15 rtltnutes,
.l'tking
- 'odine activi"" 'he coolan<<:
',)U I,'se up
<,. Sleast 9o~ oi,
.he <otal nor; i,
iI'r EHG: 'EEREO SAFFii'"..';TURE RESPO"":i
,,s ~iin
-'sL i
E The ENGIN ERED;";;";FETY FEA-,gE
RESPONSE
TIH"e.-tiall be triat tiriie intc.lval r:.. when the monito".a~ parameti;,;I exceeds its ESF'.:i"tuation.";otpoint at;.'.~e o
t chs's.-siel sensor unti'l ttie 'F eoL!'i'pment is capable,. I, per fort"si,ng its saic>ss!
ful-.;.[ion (i.e.,
the val~,"..ll trav"!,'o their require 'ositio':.-..',.pump discj1=Ige prt.':<,sures reach their revs!ired;".jlues, etc..).
Times '~halls spclude diesel"l-'q:",.-:.."ator s<<artisr g and see': nco.'oading delays wher= =.@ply'=<<ble.
- >I:!
F P-'FLUENCY'OTATIOt<
is!Ys'ti fil.-
t, ',
1,'.~
The FREQUENCY t<OTATIOH s~";":iiied for the. perfor;.;"n"6;.of Surveillance,'-'t F:g>irements shall correspond th~ ~<<he intervals defined',ad'Table 1.2.
J ane GASEOUS RADMASTE TREATl/ENT SYSTEH
1.14 A GASEOUS RAOMASTE TREATH NT SYSTEH is any system designed and installed to reduce radioactive gaseous effluents by collecting prirrary 'coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
IDENTIFI EO LEAKAGE 1.15 NTIFIEO:=..~EMGE shall be:
Leal:-ge (g; gept CONTROLL'f0 'L"'AKAGE) in%6;.cl o='d systens -'soch~'ay.
pump/seal'. or valve packing e
a sttmp or:
lclgec+ing; nicks Leakage irido the coni'ainment specifical!j locatedjand knc
'cr)!'eration,Iof',
1 cake'gp detects I
aks that aJe captured and conducted to i
r I. s" atmos pIie're from i
'~ 6 s'purces; ttlat are b'o-'.:h i terfe'r 'ith theI,":
either not to e s;~is' Or fl olj sg..
ns no Co be'iESSURE i
.","UHDARY LLAHAGE,'or i j st 4~2 g
v'.
Reactor cools;:st~'sys em leakagethrough a steam'generator to the"'econdary system.
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DEF IHITIOHS
1. 16 LOM TEMPERATURE RCS OVERPRESSVRE PROTECTIOH RANGE The L%1') I TFH~Zi~;"TURE RCS OYERPRESSURE PROTECTIVf;,'-,QHGE is: tha~'- o~~qrating condition IJJ~en'j{2) the col@ -"I'pgxtemperature.;f's
<<','280 F 'during c'ooldown~-'~.d' 320 ~F."IduJ" ng keatup and/<2) i8"~reactor c'volant;system h'as pr'js'sureD'ounda"j>>
i'-"cari~.v.
The! eactor, coolant
<ystem does,',not..b'ave prjksur':e boundar~v.'~";.egrii,'~hen J-.,he reacto."~cool~'nt system'x)'z;,~(en to coh..af=nent".',.and the minimum area o
';g="-reactor cooi>~~system opening is greater'~~hhn 3.60 square inches4---
J H"HB-R(SI OF H
PUBLIC 1.17 l'IEHBER(S)
OF THE PUBLIC shall include a'll persons who are not occupationally associated with the plant.
This category does not i,nclude employees of the utility; its contractors or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational or other purposes not.associated. with the pl ant.
OFFSITE DOSE CALCULATIOH NAHUAL (ODCH)
.1.18 The OFFSITE DOSE CALCVLATIOH h!AHUAL shall contain the current methodoloo+
and parameters used in the calcula.ion of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid ef liuent monitoring alarm/trip setpoints, and shalT include the Radiological Environmental'onitoring Sample point locations.
OPERABLE - OPERABILITY 1.19 A sy~-'=e:",<',".'subsysteri~mra'in, componen--;-~a~>>device shaj~-4e OPERABLE or have OPERPPILITt'"when i,-'.;-":is capable of,perfo'".r,'.hg its sp4cYii d'~functir f('s')
and v".En
'- ail necessar.'.,!
'attend@>",0. inst","dmentatl'0Tl con<rois, el e'ctrical'i,power,
i,.
cool i ria '-oi.='seal w<."e".,'~'.lubricate.oa~op~other auxi;) iary'.'equipment;, ibad>,;are,.:.
require<'~'or the s'ys 'emi, subsysi~<<,'..Hain, compon'ert:-'or device to"'phi~form its functio"i'(s) are also capable oi pe,~forming their related supports..u'fction(s).
O PERATIOHAL iJIODE HODF f.',
g.",.,
'e I'. <3k nn'iqpcRa O"AL kODQ(i. e.
NODE)Chal'\\cn respond to.:an>
olla~',inc 1 ukjve combina".-.'.-. of core reacts'vasty cordjtion, powe'r; level and'verage,'peac~top.:,
cons't te")sar.c!~ure speci f,~9d ip;T'able 1.1.
~ vi;+>>v evr PHYSICS TESTS 1<mk PHYSICS;.'iESTS;shall be thos>>'~i"s't's performed to~z7Ua>ure the fundamental u"" ar chare:cteristics;tof the reactor'iore and related
>nstqumenta~" ori.,and
1) o=scribt;t'."in Chapter '14.0,=. the FSAR:, '-2) autho'r ized und."qthe.jr'ovisions of 10 F,".~."~0.59, or 3).ot>: ~.use approved 'u'v'.'.~",,>~Commiss'on':.. ~~~-.,',
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PRO".F:.".,'O'.EKY COPY TABLE l. 2 FREOUEHCY HOTATIOH HGTATIOH FREOUEHCY S
At least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s.
At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 
}X a/Ni" At least once per 7 days.
At least 4 per month and a minimum of 48 per year.
SA S/U/
At least once per 31 days.
At least once per 92 days.
At least once per 184 days.
At least once per 18 months.
Prior to each reactor startup.
Completed prior to each release.
H. A.
Hot aoplicable.
X~or Radioactive affluent Sampling.
For Radioactive Batch Re'leases only.
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IHSTRUHEHTATIOH T R T
3/4. 3. 3 t.OHITORiHG IHSTRUt~EHTATION RAOIATIOH MOH.TORI t,'G IHSTRU!lhHTATIOH LINITIHG COHDITIOH FOR OPERATIOH
3. 3. 3. 1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.
APPLICABILITY:
As shown in Table 3.3-6.
ACTIOI<:
Mith a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the, setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.
b.
C.
Nth one or hiore radiation monitoring channels inoperable, take the ACTIOH shown in Table 3.3-6.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEI LLAHCE REOVIREYiEHTS 4.3.3.1 Each radiati'cn monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHAHHEL CHECK, CHAHHEL CALIBRATIOH and CllAHHEL,FUHCTIOHAL TEST operations for the NODES and a
the frequencies shown in Table 4.3-3.
TAttLE 3.3-6 RADIATIOH NOHITOltlNG IHSTRUt1EHTATION tlSTRUt 1EHT tllI<It!UH CI IAHHL1.S OPERAOLE APPLICABLE t 1001'.S ALARtl/TRIP S El'PO IHT t~iEASUREt1ENT RANGE ACTIOII
(()
~, rggyg L
r-
/s=~wglq a.
Poet'Storaqe Pool Area.,',
'~ '" i:~
r tt'l rI ~v/ >
~
~
p~avI(
r Y e
(
.)z Containment Isol ati on 3
6
< 90 mR/hr 1 -
10 mR/hr 25 I
4.isa'JG~
1 1 - 10 R/ter ontainment Area - lli Range 27
< 10 R/hr 1, 2, 3 L 4 PROCESS llOHITORS a.
Fuel St.orage Pool Area Ventilation System i.
Gaseous
.Activ i ty '1) ii.
ParLiculate Activity (1) b.
Containment Gaseous Activity RCS Leakage Oetection (1) i i.
Particulate Activity RCS Leakage OeLection (1) 7 Pg J~~
10
- PK', pCi/cc 24 z~ j- ~> <p.~)
Hot App'1 i cab 1 e Hot Applicable 1, 2, 38th I
1, 2,.38 10 10 tiCi/cc 23 1-10 cpm 6
23
~wl
( ')
1 )
-r(~ I s
s
~
I I l(I.'-. I -,'
I
~ i' Di
3. 3. 3.
>lith fuel in the storage pool or building
""<lith irradiated fuel in the storage pool or whenever there is fuel movement within the pool or crane operation with loads over the store<ye pool '
(
s a
s (
(
A
~
~
1.
'V
~~"The Alarm/Trip SeLpoints a.e determined and set inaccordance with the requiremei)Ls of Specification
TROLE 3.3-6 (Contin RADIATIOH MONI TOR I HG IHSTRUHEHTATIOH IHSTRUHENT PROCLSS HOHITORS (Continued)
HI HIi%UN CllRNHLLS OI)I'.RROLE APP LICROLE NODES
'LMH/TRIP S ETPO IHl'lEASUREIIEHT RANGE
/ICT10N c.
Hoble Gas Effluent Monitors Radwaste Oui lding Exhaust System (Plant Vent Exhaust I'loni tol )
Steam Generator Olowdown Treatment Facility Building Exhaust System Steam Safety Valve Discha1ge +~
1, 2, 3, A 4 1, 2, 3, 8
4
/ i) 10
. - +>;;,...".; pCi/cc 27 10 10 pCi/cc 27 10
- 10 pCi/cc 27
)v.
ECCS Exhaust 1, 2, 3, 8
4 I
-7 5
10
- 10 pCi/cc 27 The Alarm/Trip Setpoints are determined and set in accordance with the re<Iuiretncnts of Speci fi ca tion 3. 3. 3. 10.
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TABLE 3.3-6 (Cont>nued)
ACTION STATEMENTS ACTION 22 With the >number of channels OPERABLE less than required by the Minimum Channels OPEPABLE requirement, perform area surveys of the monitored area with portablie monitoring,instrumientation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 23 With the number of channels OPERABLE less'han required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4. 6.1.
ACTION 24 ACTION 25.
Wi'th the numioer oi channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requi rements of Speci ficati on C"-"~~~'= ~~~"~",i>'"".;~>>~~4-=-"~-'~c~r'>'-: ~~""-.~"-"~
~:i fi>>'cg With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9. 9.
ACTION 27
~
~
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With, the number of OPERABLE Channels less than required by'he Minimum Channels OPERABLE requ-iremeili elt
~
1 restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:,
1)
Initiate the preplanned alternate method of mohitoring the appropriate parameter(s),
and 2)
Prepare and submit a Special Report to the Commission pursuant to Specification
6. 9.2 within 14 days following the. event. outlinirrg the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
Z
'ABLE 4. 3-T N
I llll II Tll TLNTITI N I II TILL, I: EEIIlllilI INSTRUMENT 1.
AREA t<OHITORS CIIAHiIEL CIIECK CIIAHNEL CALI0 RATlON CI IAHiHEL
'FUNCTiOHAL TEST NODES FOR MIIICII SURVEILLANCE IS RE UIRED Fi(el Storage Pool Ai ea R
II
~....
~
~,
..E'"-:..:
" - '"*',"""".NU t'-'.
Containment - Isolation R
S 6
C:
gEE>>
'~T' l4~'~~ N'T~."' '~h'
"'L J~K Q.
Containment, Area - Nigh Range S
R H
1, 2, 3, 8
4 2.
PROCESS I10HITORS a.
Fuel Storage Pool Area - Ven-tilation System i.
Gaseous Activity ii.
Particulate Activity Containment i.
Gaseous Activity a)
RCS Leakage Detection ii.
Particulate Activity a)
RCS Leakage Detection S
S H
H 1,2,3,84 1,2,3,,54 lilith fuel in'lie storage pool or building
~" >lith irradiated fuel in the storage pool E:...~,,'E,,.;
e=
IHSTRUHEHT TABLE 4.3-3 (C
ued)
CtlAHHEL CtlECl(
RADIATION HOHITOP It'G -IttSTRUMLHTATION SUiRVEI LLAHCE RE Ul REMEt<TS I
MODES FOR MtlIClt SURVEILLAi'tCE IS RE UIRED PROCESS MOHITORS (Continued) c.
Hoble Gas-Effluent Monitors Radwaste Building Exhaust System Plant Vent Monitor
~il l 1 I.
< ifI.IVS 7 1, 2, 3 4 0
2 1
HSTRUhEHTATIOH METEOROLOGICAL
'. HSTRUHEHTATIOH LIl>iITIHG COHOITIOH FOR OPERATIOH 3.3.3.4 The meteorological monitoring instrumentation chanc,els" shown in Table 3.3-8 shall be OPERABLE.
APPLICABILITY: At all times.
ACTIOH:
a.
>lith the number of OPERABLE meteorological monitoring channels less than required by Table 3.3-8, the Licensee should suspend all release of gaseous radioactive material from the rad>>aste gas decay tanks until the inoperable channel(s) is restored to OPERABLE status.
C.
Mith one or more required meteorolcgical monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Spec-;fication 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.
The provisions of Specifications 3.0. 3 and
3. 0: -. are not applicable.
SURVEILLAHCE REQUIREl 1EHTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPEPABLE by the performance of the CHAHHEL CHECK and CHANHEL CALIBRATIOH operations at the frequencies shown in Table 4.3-5..
The Heteorological Instrumentation system is shared between St.
Lucie - Un>t I and St.
Lucie -'nit 2.
TABLE 3.3-8 HETEOPOLOGICAL YiOHITORIHG IttSTRUtlEHTAT'ON ItiSTRUMEt<T 8( ELEVATION INSTRUMENT hF tkIHUhi ACCURACY HIHIHUM CHANNELS OPERABLE 1.
MIt<DSPEED a)
Hominal El ev (10 meters) b)
Hominal Elev (57.9 meters) 2."
MIND DIRECTION a)
Homiral Elev (10 meters) b)
Homiinal Elev (57.9 meters}
0. 5 "mph
0. 5 "mph 50 50 1A H.A.'B H. A.
3.
AIR TEheERATURE (Del a T) a)
Hominal El ev (10 meters) b)
Hominal Elev ('7.9 me er )
c)
Hominal Elev (33.5 meters) 0 10Cj+
0 10> Rw 0 )oC~).
~C 1
"C H.A.
Startina speed o
anemometer shall be
< 1 mph:
LT measurement channels only.
The 57.9 meter Channel may be substitu ed for the 10 meter wind speed for up to 30 days in the event the 10 meter Channel is IHOPERA..LE.
Mind Speed Data from the 57.9 meter elevation should be adjusted using the wind speed power law:
S S
10 meters
=
57.9 meters where:
(0. 1727)
S =,wind speed in mph'
= 0.25 for Pasqui ll Vertical Stability Classes A,B,C,D.
n = 0.50 for Pasquill Vertical Stabili-y Classes E,F,G.
1.727 x 10-~ = constant,
= 10 meters/57.
9 meters The 57.9 meter Channel may be substituted for the 10 meter Mind Direction Channel for up to 30 days in the event the'0 meter Channel is INOPERABLE.
C
~
I
~
~
<ENTS CHANNEL CHECK CHANNEL CALI8 RATION 3.
MIND SPEED a)
Nominal Elev (10 meters) b)
Nominal El ev (57. 9 meters)
MIND DIRECTION a) 'ominal Elev (10 me ers) b)
'Hominal Elev (57.9 meters)
AIR TEMPERATURE (DELTA T) a)
Nominal El ev (10 meters) b)
Nominal Elev (57.9 meters) c),
Nominal El ev (33. 5 meters) 0 D*
D Dw D
D D'A SA SA" SA SA~
SA SA SA~
Required only if these Channels are be'ing substituted fm one of the. )minimum Channels Operable as per Table 3.3-8.
t<STRUi t~HTA~~O<<<
RADIOACTIVE LIQUID EFF LUEHT l'OHITORIHG IHSTRUHEt~TATIOH l
<<1<<~ ~<<
LItlITIt<G COHDITIOH FOR OPERATION 3.3.3.9 The radioac ive 1iquid effluent monitoring instrumentation channe>>
shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoinis set to ensure that the limits of Specification
3. 11'.). 1 are not exceeded.
The alarm/
trip setpoints of these channels shall be determined in accoroance with the methodoloog and parameters in the OFFSITE DOSE CALCULi(TIOt>> t!AHUAL (ODCN>.
APPLICABILITY:
At all times.
ACi<<ON:
a.
C.
Mith a radioactive liquid effluent monitoring instrumenta-:ion channel alarm/trip setpoint less con:ervative than required by the above specificat.ion, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
With less than the minimum nuimber ot r adioactive liquid ei fluent
-monitoring 'instrumeflta:ion channels OPERABLE, take the ACTION shown ln Table
3. 3-~2.
If the inoperable instruments are not returned to operable sta i s wi.hin 30 days, explain in the next Semiannual Radioactive Effluen'elease Report why tihe inoperability was not corrected in a timely manner.
The provisions of Specifications
3. 0, 3
3. O. 4 and y~ -re not appl.icable.
SURVEILLANCE REOUIREt!EHTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHAHHEL CHECK, SOURCE
CHECK, CHANNEL CALIBRATION and CHANHEL FUHCTIOiHAL TEST operations at. the frequencies sho~n in Table 4.3-8.
TRl3l.E 3. 3-l
~r! u c,.:.:r v ui rn,r
~
~
INSTRUHENT 1.
GROSS RAOIOACTIVITY HONITORS I'ROVIOING A'ARH AND AUTOHATIC TCRHINATION OF RELEASE a.
Liquid Radwaste Effluent Line b.
Steam Generator Blowdown Cffluent L'ine 2.
FLOM RATE HEASUREHENT DEVICCS a.
Liquid Radwaste Effluent Line b.
Discharge Canal I
c.
Steam Generator Blowdown Effluent Lines HINIHUH CNRNNELS OPERABLE ACl ION 30 30 30 rg
TABLE 3. 3-12 (Continued)
i. 2 '.-;I/'<<l rrlvv TABLE HOTATIOH ACTEOH 28-Mith the number of channels OPERABLE less:than required by the Minimum Channels OPERABLE requirement, efiluent releases may continue for up to 14 days provided that prior to initiating a release:
a.
At least two independent samples are ana',yzed in accordance with Specification ~~-.X-.3q and
<.<1. t, f. t At least two technically qualified members of the Facility Stai i independently ver ify, the release rate calculations and discharge line valving (one performis, one verifies);
Otherwise, suspend release of radioactive effluents via this pathway.
'ACTIOH 29 -
4'ith the number of channels OPERABLE less than ",equired by the Minimum Channels OPERABLE requirement, eifluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection oi at least 2 x 10-microcuries/gram:
b.
At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the speciiiic activity of
'he secondary coolant is greater than 0.01 microcuries/
gram DOSE EgUIYALEHT I-131.
Ai 1 east once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the speci fi c ac.i viity of the secondary coolant i's less than or equal to 0. 0" micro-
'uries/gram DOSE EJUIYALEHT I-131.
ACTION 30 "
Minimumi system design flow oi required running pumps shall be.utilized for MPC calcula ions for discharge canal flow
.and maximum system design f'low shall be utilized for MPC calculations for effluent line flow.
ST. 'C:E -
UHET 4 4 3/4 3-50
BADIOACTIVl'. l I UID EFI LUEHT l1OHITO'RIHG IHSTRUllEHTATIOH SUR'!EILLAHCE RE UIREHEHTS IHSTRUJ~EH T l.
GROSS BETA OR GAHt1A RADIOACTIVITYHOHITOBS PROVIOIHG ALM~3 AHD AUTO'r'ill'lC TERNIHATIGH OF RELEASF a.
Liquid Badwaste Effluent Line b.
Steam Generator Blowdown Effluent Line 2.
FLOH BATE l"lEASURE%HT DEVICES a.
Liquid Radwaste Effluent Line b.
Stea~ Generator Olowdown Effluent Line CI lAHHEL CI IECK SOURCE Cl IECK H.A.
H.A.
CllAHi'lEL CALIORA1'ION R(2)
R(23 CHAHlEL FUHC rIOHAL TEST Q(l)
Q(l)
Q m0 IIII I1I m
3) z m0 Im I0X 0
0 m
I G)x 0
~g 0X g'X O
O f~c Z0
~~~a
P. O. BOX 14000, JUNO BEACH, F L 33408 TABLE 4.3-8 (Continued)
TABLE NOTATION I
~
p
~
~
FLORIDAPOWER & LIGHTCOMPANY (1)
The CHAHHEL FUHCTIOHAL TEST shall also demonstrate that automatic
.,'solation of thi s path~ay and control room alarm annu.sociation'ccur if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm/trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.'
(2) 4.
Instrument controls not set in operate mode.
The initial CHAHHEL CAL:BRA IOH for rad',oactivity measurement instrumentation shall be performed using one or more of the reference standards traceable to the Rational Bureau of Standards or using standards that have been calibrat'ed against standards certified by the HBS.
These s anoal ds should permit calibrating the system over its intended range of energy a.d rate capabilities that are typical of normal plant operation.
For subsequent CHAHHEL CALIBRATIOH, button sources that have been related to the initial calibration may be used, at intervals of at least once per
~8 months.
This can normally be accomplished during refueling outaoes.
ST.
I UC!:- - U"': $ L 3/C 3-:-2 PEOPLE... SERVING PEOPLE
!tiSTRJt,itiTATIOH
)(OO~BQf 10$000IIQ IlljI F H)fjl,&PPB
<ilI/i.
RAD!OACT'VE GASEO":=.
EI'> LU HT t/Ot<ITORIHG IHSTRUHEHT"TiiO'<
NITItiG COt<DITIOH FOR OPERATIOH I
T F
FLORIOA POWER & LIGHTCOMPANY 3.3.3.10 The radioactive gaseous'ffluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the linits of Specification
3. 11.2.1 are not exceeded.
The alarm/irip setpoints of these channels shall be determined in accordance with the methodology and parameters'n the ODCN.
APPLICABILITY:. As shown in Table
3. 3-13 ACTION:
C.
Mith a 'radi oacti ve gaseous effluent moni toring instrumentati on channel alarm/trip setpoint, less conservative than reauired by the above Specifica-'ion, immediately suspend the release of radio-active gaseous effluents monitored by ihe affected channel or decla.
e the channel inoperable.
4'ith less than the minimum number of radioactive gaseous effluent monitoring instrumentaiion channels OPERABLE, take the ACTION shown in Table 3.3-13.
If the inoperable instruments are not returned to operable status within 30 days, explain in the next Sen>iannual Radioactive E>> luent Release Report why the inoperability was. not corrected in a timely manner.
The provisions of Specifications 3.0. 3,
3. G. 4, and
6. 9. i.~i are no appl'.cable.
SUR'liILLAtiCE REOUI>R~HEtiTS 4.3.3.11 Each radioactive gaseous e>fluent n>onitoring instrumentation channel shall be den>onstraied OPERABLE by performance of the CHAHHEL CHECK, SOURCE
CHECK, CHAHtiEL CAL BRATIOH and CHAHHEL FUHCTIOHAL TEST ooerations at the frequencies shown in Table 4.3-9.
ST.
LUCIE - UHIT g-$
3/4 3-53 PEOPLE... SERVING PEOPLE
'1'ABLE 3 RAOIOACTIVE GASEOUS EFFLUEH'I'OHITORIHG IHSTRU'1EHTATIOH r-C:
~ H I'Il IHSTRUHCHT l.
WASTE GAS llOLOUP SYSTEll HlNIllU'1 CIIAHHELS Ol'LRAOLF.
APi'l.lCARI LITY ACTIOII Ill0 Im Ch z0 m0 I.m b.
C.
e.
Iodine Sampler Particulate Sampler Flow )late Sampler Flow Rate Honitor
~,~u~r I p/<fg ]
OCCr //+ Pncili~<~ ~~
~r~~~R ~~M
~//z".
u'.
Noble Gas Activity monitor -'roviding Alarm and Automatic Termination of Release 2.
MASTE GAS llOLDUP SYSTU1 EXPLOSIVE GAS MONITOR IHG SYSTEl1 a.
Oxygen Honi tors (~'~~'~
3.
COHOENSER EVACUATION SYSTEM a.
Hoble Gas Activity l1onitor PLANT VFNT SYSTEH Noble Gas Activity l1onitor.(Low Range)
~>>
35 3?
37 40
$ 0 I0
.0 0
Ql I
8 y+ll
+/lr
~~
~1
I rI3 IHSTRUt 1EHT I
t'11HIt'1UH CIIAHHELS GPFRADLE APPLICABI LITY TMLE 3.3-13 tinued RADIOACTIVE GAS1 GUS EFFLUEHT. HOH ITORIHG IHSTRUHENTATION ACT I Oui Ce3 Cr3 I
Cn C31 a.
I Hoble Gas Activit Honitor Io 'ne Sam er c.
Part.ia 1
e Sampler d.
ow Rate FUEL SloRAGE AREA vEHTILATIOH SYSTEH a.
Noble Gas Activity Honitor (Low Range) b.
Iodine Sampler c..
Part.iculate Sampler d.
Flow Rate monitor e.
Sampler Flow Rate Honitor t1ACllIHE SHOP VEHTIlATIOH S STEt1 (1)
(1)
(1)
(1)/
1)
A 37 40 no
.37'll m0II Ifll CDfll Z
Cl Ill0 IIll Sampler Flow Rate t1odtor 7.
STEAN GENERATOR OLOMD01tt< OUILDItlG YEHT SYSTEH Q.~~ )
(
()
a.
Noble Gas Activil.y Honi tor (1) b.
Iodine Sampler (1) c.
Particulate Sampler d.
Flow Bate Honi tor e.
Sampler Flow Rate Honitor (1)'.H~
7g J~ ~,.
vfclccc ~non H~c.3 "I /v><>~~v dM ~q~
Y
/ac i r
I gg('~ cj /c.r./c.'wc t
/ SI Qc4lw /
c~ ~j /+5(.
~ c I I" 0
O 37 o
m no I
40 x 3O '.
36
~
+!It 0
0 X0 o
l Cz I//
~M(.
0 TABLE 3.3-13 (Continued)
!ABLE NOTATION At all times, FLORIDAPOWER & LIGHTCOMPANY ACTION 36 CTION 37 T
ACTION 39 waste gas holdup system operation (treatment for primary svstem times when air ejector exhaust is not directed to plant vent.
ACTION 3S -
Mith the number of channels OPERABLE less than required by the H!inimum Channels GP=RAB E requirement, the contents of the tank(s) may be.released to the environment for up to 14 days provided that prior.o initiating the release:
a.
At least two incependent samples of the'tank's contents are analyzed, and b.
At least two technically qualified members of the Facility Staff independen ly verify the release rate calculations and discharge valve lineup (one performs, one verifies).
Otherwise, suspend rel ase of radioactive effluents via this pathway.
Mith the number of c>>=nnels OPERABLE less than required by the Hiinimum Channels OPERABLE requirement,.effluent releases via this pathway may continue for to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
Mith the number of channels OPERABLE less than required by the Hinimum Channels OPERABLE requirement, effwent releases.
via this pa hway, may continue for up to 30 days provided grab p
'8' these samples are analyzed for Isotopic activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 38 -
Haximum system flo~s sha'll be uti.lized in the determination of the instantaneous release monitor alarm 'setpoinl.
Mith the number of channnels OPERABLE one less than r'equired by
- the Hinimum Channels OPERABLE requirement, operation of this system may continue for up to 30 days provided samples of 02 are analyzed by the lab gas partitioner at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , Mith two channels inoperable, operation of this system may continue fol up to 14 days provided samples of 02 are analyzed by the lab partitioner at least or,ce per 15 minutes.
ACTION 40 -
Mith the number of channels OPERABLE less han required by the Hinimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4. 11-2.
ST.
LUCIE -
uNJT 5f 3/4 3-56 PEOPLE.:. SERVING PEOPLE
.3-9 RADIOACTIVE GASEOUS EFFI.UEHT tlONITORIHG IHSTRUtlEHTATIOH SURVEILLANCE IIE UIREtlEHTS IHSTRUt1ENT l.
MASTE GAS IIOLDUP SYSTEM a.
Noble Gas Activity Monitor
-'roviding Alarm and Automatic.
Termination of Release Z.
HASTE GAS IIOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.
Oxygen tlonitor CIIAHHEL CIIECK SOUILCE CIIRHHCL CIIECK 'ALIBINT ION R(3)
Q(5)
CI IAHt<EL FUNCTIONAL TCST Q(l)
M t10DES IN MIIICII SURVEILLAHCE REQUIRED 3,
b.
Oxygen tlonitor (alternate)"""'
P CONDENSER EVACUATIOH SYSTEM a.
Noble Gas hctivity t1oni tor PLANT VENT SYSTEM D
H.A.
Q(5)
R(3)
Q(2) m0
'Im Chm Z
Cl m0r m
a.
Noble Gas Activity t1onitor D
b. Iodine Sampler
c. Particulate Sampler d.
Sampler Flow Rate Monitor M
K/
M I
I N.A.
H. A.
H.A.
R(3)
H.A.
N. h.
goI<<
M ~~M I~ c~<~:~~
Q.~ ~(~VGA)
~ Zcj Mr(.a~~4' c4" '/."< > ~~~~
4/i/1' tl. A.
H. h.
H.A.
0 A
'00 I
C)X O0 z
'C
~~lb 0
IO
TABLE h.3-9
(
nue(I)
RRDIOACTIVE GRSEOUS EFFLUENT HOHITORING INS'IRUHEHTATIOH SURVEILLANCE RE UIREHEHTS I
n IWfll IHSTRUHEHT 5.
FUEI STORAGE AREA VENTILATION SYSTEH a.
Hoble Gas Activity Honitor CIIAHNEL CIIECK SOURCE CIIRHNEL CIIECI<
CALI BRM ION R(3)
CIIRHHEL F UNCT IOHRL lEST HODES IH MIIICII SURVEILLANCE RE VIREO b.
Iodine Sampler
c. Parti cul a te Samp1 er d.= Sampler Flow Rate Honitor H. A.
H. A.
H ~ A.
N. A.
N. A.
~D 6.
HACIIIHE SIIOP VEHTLLATIONrSYSTEH Noble Gas tivi Honitor
b. Iodin Sampl c.
P ti culm'.e Sampl ei
~i Sample Flow Rate Honitor.
I<,.
Vl'.
R(3)/'~A.R.
w g n.
H. A.
iQ(2)
H. R.
m0 Im mX z
Cl m0 Im 7.
STEAM GENERATOR OLOLitDOW BUILDING VENT a.
Noble Gas Rctivity Honi tor b.
Iodine Sampler c.
Par ticul ate Samp 1 er d.
Sampler Flow Rate Honitor H. A.
I H.R.
R(3)
H.A.
H.A.
p/.g Z
g~~
~i"~
+;,, ~ 6P~M L~~ Ur~
Q(2)
H.R H.A; H. A.
I0 0
0 i0x 00 z
I
+t(n
";ABLE 4. 3-9 (Continued) 0 a
TABLE HOTATIOH FLORIDA POWER 8 LIGHT COMPANY At all times other than 'when the line is valved out and
'.Ocked.
(2)
(3)
(4)
During waste gas holdup system operation (treatment for primary system offgases).
At all times when air ejector exhaust is not directed to Dlant vent.
The CHAHHEL FUHCTIOHAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
l.
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.
The CHAHHEL FUHCTIOHAL TEST shall also demonstraLe that control room alarm annunciation occurs if any of the following conditions exis s.:
l.
InstrurIent indicates measured levels above the alarm s'endpoint.
2.
Circuit failure.
e 3.
Instrument indicates a downscale. failure.
. 4.
Instrument, controls not, set in operate mode.
The initial CHAHHEL CALIBRATIOH for radioactivity measurement instI'umentation shall be performed using on or more oi the reference standards traceable to the Hational Bureau o.
Standards or using standards that have been calibrated against standards'ertified by the HBS.
These standards should permit calibrating the system over its intended ranoe of energy and rate apabi li+ies that are typical of normal plan operation.
For subsequent CHAHHEL CALIBRATIOH, button sources that have been'elated to the initial calibration may be used, at. intervals of at least once per 18 months.
This can normally be accomplished during refueling outages.
The CHAHHEL CALIBRATIOH shall include the use of standard gas. samples containing a nominal:
l.
One volume percent
oxygen, balance nit'rogen, and 2.
Four volume percent
oxygen, balance nitrogen.
3 I
E'
~ p~~g dg~l
< LIOW~~~
8 ST.
LUCIE - UHIT > 4 3/4 3"59 PEOPLE... SERVING PEOPLE
P. O. BOX 14000, JUNO BEACH, F L 33408 PsL L ~op, App T 4o iocF~so
@tv Ci",a Qollowii~p "LORIO GGcklbvls Z-wc.Sic, s o/4 II
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I'i-l6 PEOPLE SERVING PEOPLE
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3/4.
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RADIOACTIVE ErFLUEHTS P. O. BOX 140(gl0, 4 PJ
'BBABJP, PL 33408 3/4. 11.
1 LIOUID EffLUENTS HC"HTRATION FLORIOA POWER & LIGHTCOMPANY LIHITTHG CONDITION fOR OPERATION 3.11.1.1 The concen ration of radioactive material released from the site (see fiGure 5.1-1) shall be 1 imited to the concentrations specified in 10 C. R Part 20, Appendix B, Table II, Column 2 for radionuclides other han dissolved or entrained noble gases.
For dissolved or entrained noble cases, the concentration shall be lir>>ited to 2 x 10-~ micI ocuries/ml total activity.
APPLI CABI LITY:
At a 1 1 times.
ACTION:
Pith the concentratio, of Iadioactive naterialI released from he site exceeding the above limii.s ll"i7iediately I'estoI e the concentration to within the above limits.
URVEILLAHCE R OUIRFH NTS 4.11.1.1.1 The radioactivity conten: of each batch of radioactive liouid waste shall be determined prior to release by samplin<
and analysis in accoroance wi h 'able 4.1i-l.
The results oi p e
I elease o-nalyses shall be usea with the calculational methods in the ODCh to assure thai the corIcentration at the point of release is mairtained within.he limits of 'Specification 3.11.i.l.
Also,
= results of the previous post-release analyses shall be used, with the calcu-lational mieti'Iods in ti'Ie.'0"."i to assure that the.concentrations at the point of release were maintaine" within the limits of Specification
3. 11. 1. 1.
4. 11. l. l. 2 Pos -release analyses of samples composited from batch releases
.shall be performed in ac ordance with T'able 4. 11-1.
4. 11. l. 1. 3 The radioacJtivity concentration of liquids discharged from
~ continuous release points shall be determined by collection and analysis of samples in accordance wiht Table 4. 11-1.
The results of the analyses shall be used with the calculational methods in the ODCH to assure that the concentrations at the point of release are maintained within the limits of i Specification 3.11.1.1.
ST.
LUCIE - UNIT $ ii 3/4 ll-l PEOPLE... SERVING PEOPLE
L
ID MASTE SAHPLIH~ AtiD ~hAL >l~
'A'" "'
PP<0".F '".Y'E"t "95II R.".D.OACTIVE LIQU Liquid Release Type Sampl ing Frequency FLORIDAPOWER & LIGHT COMPANY Lo~er, Limit Hinimum of Detection Analysis Type of Activity (LLD)
Frequency
'nalysis (pCi jml )
A. 'Batch Maste Release Tanks c p
p Each Batch Each Batch
-7 Principal Gamma 5xl0 Emitters e I-131 1 x10 p
One Batch/H H
Dissolved and Entrained Gases
~
(Gamma Emitters) 1 xl 0 p
H b
Each Batch Composite p
b Each Batch Composite H-3 Gross Alpha Sr-89, Sr" 90 Fe-55 1 xl0 lxlO 5xl 0 1xlO B. Contiruous Releases-QQ Dai ly 4/H Composite Prl nci pa 1 Gamma Emit ers 5x10 D
4/Hi Grab Sample Composite Dai ly I".1 31 Dissolved and Entrained Gases (Gamma Emitters) lxlO 1 x10 Dai ly H
Composite H-3 Gr oss Alpha lx10 1 x10 C. Settling Basin Daily M
Grab Sample Composite Sr-89, Sr" 90 F e-55 P ri nc ipa 1 Gamma Emitters I-131 5xlO 1xl0 Sx10 1x10 ST.
LUC.'E - UNIT P<
3/4 11-2 PEOPLE..'. SERVING PEOPLE
TABLE 4. 11-1 (Continued)
TABLE tiOTAT~OH a.
The LLD is the smallest concentration of radi"active material in a sample that will be detected with 95K probability w',th 5M probability of falsely concluding that a blank observation represents a ",real" signal.
For a particular measuremcnt
system, (which may inc'.ude radiochemical separation):
LLD =
4.66 sb E
V 2.22 x 10 Y
exp (-Mt)
Mher e:
LLO is the "a priori" lower limit of detection as defined above (as microcuri es per unit mass cr volume),
' is +he standard deviation of the backgro nd coun ing rate or. of I Ie counting rate of a blank sample as app opriate (as counts pel mj nut e),
E is the counting efficiency (as'ounts per transformation),
~ ~
Y is the sample size (in units of mass or volume),
2.22 x l0 is the number of transformations pel minute per flic ocurie,.
Y is the fractional radiochemical y'.eld (when applicable),
A is the radioactive decav constant fo" the particular r adi onuc l ide, and b,t is the elapsed time between midpoint of sample collection and time of counti ng (for plant effluents, not environmental samples).
The value of s used in the calculation of the LLO for a detection system shall b3 based on the actual observed variance of the background counting rate or of the counting rate o-he blank 'samples (as appropriate) rather'han on an unver',fied theolet cally predicted vari.nce.
Typical values of E
Y Y
and Di shall be used iz the calculation.
3/4 11-3
TABLE e, ll-1 (continued)
PplOOF iA'. REYIE>Y COPY TASLE NOTATION A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which i' representative of the liquids released.
A batch release is the discharge of liquid wastes of a discrete volume'.
Prio" to samplino for analyses, each batch shall be isolated, and then thoroughly mixed to assur representative sampling.
A continuous release is
.he discharge of liquid wastes of a nondiscrete volume, e.g.,
from a volume of a system that has an input flow during the continuous release.
The principal gamma emit ers for which the LLD specification applies exclusively are the following radionuclides:
Mn-54, Fe-5S, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these ruclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Grab samples to be taken when there is confirmed primary to secondary sys em leakage indicated by the air ejector monitor indicating
> 2x background.
I
. g.
If Compone J
I nt Coolino Mater activity is >1x10 pCi/ml, perform a weekly
- gross activity on the.intal e Cooling Mater System outlet to ensure the
-7
-7 activity level is a 2xl0 pCi/ml LLD limit." If ICM is >2xl0 pCi/61, perform analysis in ac"ordance ui h
a P',ant Continuous Release on this Table.
ST i UC I c UNiT h 3/4 11-4
0
RADIOACTIVE EFFLUEHTS PROOF.Fi P~EVlEY COPY
.-DOSE.
LZr<ITIHG COHDITIOH FOR OPERATIOH-3.11.1.2 The dose or dose commitment to a
HEHSER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UHRESTRICTED AREAS (see Figure 5.1-1) shall be limited:
a.
. During any calendar quarter to less than or eoual to l.'5 mrems to the total body and to less than or equal to 5 mrems to any organ, and b.
During any calendar'year to less than or equal t.o 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: 'At all times.
ACTIOH:
a
~
Vith the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report requi. ed by Specification
6. 9. 1, prepare and submit +
'to the Commission w'.thir. 30 days, pursuant to Sp cirication 6..9.2, a
Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective ac:ions to be aken to reduce the releases and radioactive materials in liquid effluen-s during the remainder of the cur rent calendar quarter and during the subsequent three calendar
quarters, so that the cur.ulative dose or dose commitment.
to an individual from these releases -is within 3 mrems to the tot.al body and 10 mrems to any organ.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are no applicable.
SURYEILLAHCE REOUIREPEHTS 4.11.1.2 Dose Calculations.
Cumulative dose contributions from lic id effluents shall be determined in accordance with the methodology and parameters in the ODCH at. least once per 31 days.
ST.
LUC'E - UHIT g' 3/4 11-5
II
RADIOACTI'<J'E EFFLUEHTS
~LI UID MAS'.E TREATHEHT
/
~
~
LIHITIHG COHDITIOH FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE.
The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liouid effluent from the site to UNRESTRiCTED AREAS (see Figure 5.1-1)
-when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
APPLICABILITY: At al 1 times.
ACT<0<<:
Mith the liquid radwas e treatment system ioperable for more than
'31 days or with radioactive liquid waste being discharced without treatr<ent and in excess of the above limi s, in lieu of any other report required by Specification 6.9. 1, prepare and submit to the Commission within 30 days pursuant to Specification
6. 9. 2 a Special i Repo: t which includes the following 'information:
l.
Identification of. the inoperable equipment or subsystems and the reason for inoperability, 2.
Action(s) taken to restore the inoperable equipment to OPEPABLE
~
status, and 3.
Summary oescription of action(s) waken to prevent a recurrence.
b.
The provisions of. Specifications
3. 0. 3 and 3. 0. 4 are not applicable.
SURYEILLANCE REQUIREH NTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31
days, in accordance with the ODCH unless the liquid radwaste treatment system is being used.
4. 11. 1. 3. 2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating th liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless he liquid radwaste system has been utilized.to process radioactive liquid effluents during the previous 92 days.
/
ST.
LUCIE - UNiT ~~ f 3/4 11-6
RA010ACTIVE
-."" "." LUEH.'S 3/4. 11.2 GASEOUS EFFLUEHTS OSE RATE "
ppg JF E REVIEY( COP'I LIViITIHG COHO ITIOH FOR OPERATION 3.11.2.1 The dose rate in UHRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site (see Ficure 5.1-1) shall be limited to the following:
a.
b.
For noble gases:
Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and For all radionuclides and for all radioac ive materials in particulate form and radionuclides (other than noble gases) with half lives gr eater than 8 days:
Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At al 1 times.
ACTIOH:
Mith the dose rate(s) exceeding the above limits, immediately decrease the t
t elease rate to within the above limit(s).
SURVEI LLAHCE. REOUIREt",EHTS 4.11.2.1.1 The dose rate due to noble gases
',n gaseous effluents shall be.
determined to be within the above limits in accordance with the methodology and parameters in the OOCH.
4. 11.2. 1.2 The dose rate due to radioactive materials, other than noble
gases, in gaseous effluents shall be de ermined to be within the above limits in accordance with the methodology and parameters in the OOCH by obtaining representa ive samples and performing analyses in accordance with the sampling and analysis program specified in Table
4. 11-2.
3/4 li-7
RADIOACTIVE CASE NSTE SAtlC LittG AND AttALYSIS PROGRAH C
~
~)
Sampling Gaseous Release T
)e Fre< uenc f)
Each.Tank Grab Sample A.
Maste Gas Storage Tank
P 9.
Containment Purge 'acl) Purge Grab Sam le Hinimum Analysis Fre( uellc 3
P.
Each Ca))k P
Each Pu).ge l)
, Type of Activi,t,~ Anal sis Principal Gamma Emi tters e Principal Gamma Emitter.
33-3 Lower Limit of.
Detection
{LLO)
( jCi/ml) lx10 lxl0 1x10 (1') Plant Vent (2) Fuel Building Vent
-(3+( 1actTfrie SHop
-Vc>>L
8) Steam Generator 331 owdown 13ui 1 din Ve>>t~ ~
D ~
All Release Types as listed in R, C3, C above.
0/H Grab Sample Continuo')s d 0/>>
Ct)<lrcoa 1 Sa~n) 1 e Conti))uous d c
c/>>
Particulat.e Sam le Pri)>c';pal Gamma Emitters 33-3 I-131 Principal Gannna Emitter (I-131, Others) 1 xl0 1 xl0 1 x10 xl0-11 Continuous
. d Continuous d H
Compos i te Par Liculate Sami) 3 ee Composite Pa)'t i cul a te Sample Gross Alpha Sr-09, Sr-90 1 vlO x10-11 Continuous Noble Gas d
Ho>>i tor Hob]e Gases Gross Oetd or Gamma lxl0
TABLE 4.
1 1-2 (Continued)
PROOF 5 REYlPi'OPY, TABLE NOTATION a.
The LLD is the smallest concentration of radioactive. >material in a sample that will be detected with SSX probability with only Sr. probability of falsely concluding that a blank observation represents a "real" signal.
Fol a particular measurement system (which may include radiochemical separation):
LLO =
=4. 66 sb E
~
V 2.22 x 10' Y
exp (-Mt)
Mhere:
LLD is the "a priori" lower limit of detection as defined above (as microcuri es per uni t mass or volume),
s. 'is the standard deviation of the background counting rate -or of tk'e. counting rate o>
a blank sample as appropriate (as counts per minute),
-". is the counting e>ficiency (as counts per trans>ormation),
V is
+he sample size (in units of mass or volume),
2. 22 x 10 is the number of transformations per minute per l>licrocu'ie, Y is the
>raci1onal radiochemical yield (when applicable),
). is t'e radioactive decay constant for the particular radionuclide, and Dt is the elapsed time between midpoint of sa:,pie collection and time of counting (for plant effluents, not'nvironmental sam>ples).
The value of s
used in the calculation of the LLD for a detection system shall b3 based on the actual'bserved variance of the back-cround counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretiically predicted variance.
Typical values of E, V, Y, and at shall be used in the calculat1on.
T/'"-LE 4.11-2 (Continued) i/BL HOTAi iOl(
Sampling and analysis shall also be performed following shutdown, star'up, or a
THERMAL POWER change exceeding 1SX of RATED THERMAL POMEP, vr:."==-"~in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis sho~s that the DOSE EgUiVALEHT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity moni:or shows tlat effluent activity has not increased by more than a factor or 3.
Samples shall be changed.at least 4 times a month and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).
Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 davs following each
shutdown, startup or THERMAL POMER change exceeding 15M of RATED THERMAL POMEP, in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing if (1) analysis shows that 'the DOSE EOUIVALEHT I-131 concentration in the primary coolant has increased more than a factor of 3; and (2) the noble gas activity moritor shows that effluent activity has increased by more than a factor or 3.
Mhen samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , are analy=ed, the orre'sponding LLDs may be increased by a factor of 10.
d.
The ratio of the sample flo~ ra e to the sampled stream flow rate shall be known icr
~he time period covered by each dose or dose rate calculation made in accordance with Specifications
3. i1. 2. 1,
3. 11. 2. 2 and
3. 11. 2. 3.
The principal gamma emitters for which the LLD specification applies exclusivelv are 'he following radionuclides:
Kr-87, Kr-88, Xe-133,.
Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59,
- Cc-58, Co-60,'n-65, tio-99, Cs-34, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks 'which are measureable ard identiiiable, tooether with the above nuciides, shall also be '.den.ified and reported.
3/4 ll-'0
RADIDACTIVE'F F LUEHTS
~npnr j (pt)p.v [tjj})1 DOSE "
HOBLE GASES A
LINITIHG COHDITIGH FOR OPERATION
+o oP t=tl<B P cg T~~ KOLlC 3.11.2.2 The air doseAdue to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure
5. 1-~) shall be lim ted to the following:
a.
During any calendar quarter:
Less than or equal to
"" mrads for gamma radiation and less than or equal to 10 mrads for beta
".adiation and, b.
During any calendar year:
Less than or eoual to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta rad',ation.
APPLICABILITY: At all times.
.ACi}Ol<
a.
'~(ith the calculated air dose from radioac-ive noble gases in Gaseous effluents exceeding any of ihe above limits, in.lieu of any other report required bv Specif ication 6.9.:, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Reoort which ioentifies the causa(s) for exceeding the limit(s) and defines the corrective actions to'e tal;en to reduce the releases oi radioactive noble gases in gaseous eifl ~ents during the remainder of the current calendar quarter and during the subsequent three calendar
quarters, so that 'he cumulative dose is within ~0 mrads for amma radiation and 20 mrads for beta radiat ion.
b.
The provisions of Specifications
3. 0. 3 and
3. 0. 4 are not appl;cable.
SUR('E I LLAHCE REOUI REI(EHTS
4. 11. 2. 2 Dose Calculations.
Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the methodolgy and parameters in the ODCi~i't least once pe.
31 days.
/
ST UCIE - UH!t 3/~~
11-11
PAD IGACT'"
"Fc I UEtiT5 PEG".F t,'ND't M"i'OSE
" RADIOIODIHES, RADiOACTIVE tiATERIALS IH PARTICULA'.: FGRl'i, At"" RADIOHUCLIDES
" ER THAts ttOBLE GASFS TING COttDITIOH FOR OPERATIOH Hct<oEP
~4 -%E PuBLi~
3.
1 l. 2. 3 The dose to a@individual rron radi oiodi nes and r
d ioaccilte ssaterials in particulate form, and radionuclides (other than noble gases) with half-lives greater ihan 8 days ln gaseous eifluents released, from a=eh reactor unit, from the site (see Figure 5. 1-1) shall be limited to the following:
a.
During ariy calendar quarter:
Less ihan or equal to 7.5 mrems to any organ and, b.
During any calendar year:
Less ihan or equal to 15 mrems to any organ.
APPLICABILITY: At all iimes.
ACTIOt<:
Mith the ca'tculated dose from the release of racioiodines, radioaciive materials in particulate folm ol radionuclides (other than noble oases) with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu oi a:".y other.
report required by Speciiication
o. 9. 1, prepare and submit to the Commiission within 30 days, pursuant io Specif'.cation
6. 9.2, a Special Peport which identifies the cause(s) for exceeding the li-..i-: and defines the corrective aciions o be taken
.o re ce tre -=leases of radioiodines and radioactive materials ip particulate for."., and radionuclides (other than noble cases) w',th s":alf-;ives gr=a.er than 8 days in gaseous effluents durirsg the remainder of the cs'-rent calendar quarter and during the subsequent thre calendar =uarters, so tha't the cumiul ative dose or dose,commi tment to an indi vii dual fromi these releases is within 15 nrems to any organ.
b.
The provisions of Specifications 3.0.3 and 3.0.~ are not a=plicable.
SURYEILLA"CE REQUI REHEHTS
~.11.2. 3 Dose Calculations.
Cumulative dose contribu-.ions for the.-urrent calendar quarter and current calendar year shall be determined in ac=ordance with the methodology and parameters in the ODCH at leasi once per 31 days.'T.
LUCiE - UNIT 4 2 3/4 11-12
RADIOr'IIVE Et F UEHTS G'.SEOUS RADWASTE TRE/1MLHT LIMITIHG COHDITIOH FOR OPERATIOH 3.11.2.4 The GASEOUS 'RADWASTE TREATMEHT SYSTEH and the VEHTILATIOt< EXHAUST
~ TREATMEHT SYSTEM shall be OPERABLE.
The appropriate portio'ns of the GASEOUS g< JAB~ TREATHEHT SYSTEM shall be used to reduce radioactive materials in gaseous waste prio~ to their discharge when the projected gaseous effluent air
'oses due to gaseous effluent releases from the site to UHRESTRICTED AREAS (see Figure 5. 1-1),
when averaged over 3i days,'ould exce d 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The approp. iate portions of the VEHTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharoe when the projected doses due to gaseous e.fluent releases from the site (see Figure S. 1-1) when averaged over 31 days would exceed
0. 3 mrem o any organ.
/iPPLIChBILITY:
At, all times.
ACTIOI<:
With the GASEOUS RADWASTE TPEATMEHT SYSTEM and/or the VENT>LATIOH EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or wi ih gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9. 1, prepare and submit to the Commission within '30 days, pursuant to Specification 6.9.2, a
Sp cial Report which includes the following information:
1.
Identification of the inoperable eouipment or subsystems 2nd the reason for the inoperability, 2.
Action(s) taken to restore the inoperable equ',pment to OPERABLE
status, and 3.
Summary description of action(s) taken to prevent a recurrence.
b..
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVFILLAHCE REQUIREMEHTS
4. 11. 2. 4.
1 Doses due to gaseous releases fr.om the site to UNRESTRICTED AREAS shall be projected at least once pe.
31 days, in accordanc~
with the ODCM unless the GASEOUS RADWASTE-TREATMENT SYSTEM is being used.
4. 11. 2. 4. 2 The GASEOUS RADWASTE TREATMEHT SYSTEM and VEHTELATIOH EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMEHT SYSTEM equipment and VEHTILATIOH EXHAUST TREATMEHT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appro-riate system has been utilized to process radioactive gaseous effl'uents during he previous 92 days.
ST.
LUCIE - UNIT fr+
3/4 11-13
RADIOACTIVE EFFLUEHTS EXPLOSIVE CAS Vi.'XTURC Ph03i 5 (FYiÃ f.'[)P'(
HITitiG CGt<OITIOH iOR OPERA ION 3.11.2.5 The concentration of oxygen in the on service waste gas decay tank shall be limited to 'less than or equal to 2
by volume whenever the hydrogen concentration exceeds 4~ by voll;me.
APPLICABILITY: At all t mes.
AC7IOH:
b.
h With the concentration of oxyoen in the on service ~aste gas decay tank greater than 2 'y volume but less than or equal 4X by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .
- With the concentration of oxygen in the on service waste gas decay tank greater and 4~ by volume and the hydrogen concentration greater than 2
by volume, immediately suspend all additions of waste gases
'o the system and immediately commence reduction of the concentration of oxygen to less than or equal to 2 by volume.
C.
The provi si ons of Specifications
3. 0. 3 and 3. 0. 4 are no+ appl i cabl e.
RVEILLAHCE REOU:R:FEl<TS
4. 11.2.5 The concentrations of hydrogen and oxyge'n in the on service ~aste gas decay tank shall be determined to be within the above limits by contin-uously monitoring the waste gases in the on service waste gas decay tank with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Speci fication 3. 3. 3. 10.
I 3/4 11-14
RADIOACTIVE Er r LUEHTS GAS STORAGE TAHVS LINITIHG CONDITIOH FOR OPERATIOH 3,11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 285,000 cur ies noble gases (considered as Xe-133).
APPLICABIiITv.
At all times ACTXGN:
a ~
b.
Mith the 'quantity of radioact,ve material in any gas storage tank exceeding the above limit, immediately suspend all additions of radi oacti ve materi al to the tank, and provide prompt noti fication to the Commission.
~ ~
The provisions of Specifications
3. 0. 3 and 3. 0.4 are not applicable.
SURVEILLAHC= REQUIRE!':EHTS
4. 11. 2. 6 The quantity cf radioactive material contained in each gas storage
'tank shall be determined to be within the above limit ai least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive.,materials are being added to the tank when reactor
'IOO coolant system activity exce ds =
E
/
I ST.
LUCIE - UNIT
~p K 3/4 11-15
RADIOACTIVE -".,FF'EHTS 3/4. 11. 3 TOTAL DOSF PRO:."F
.".: REPin)'OPY T
LIt~iITIHG COHO ITION FOR OP ERATION 3.11.3 The annual (calendar year ) dose or dose commitment to any ttEI'ABER OF THE PUBLIC due to releases of radioactivity and to radiation from.uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
Mith the calculated doses from the release of radioactive materials in liquid or gaseous erfluents exceeding twice the limits of Specifica-tion 3. 11.1.2a,
3. 11.1.2b, 3.11.2.2a, 3.11.2.2b,
3. 11.2.3a, or
3. 11.2.3b, calculations should be made including direct radiation contributions from the reactor units and from. outside storage tanks to determine whether the above li'mits of Specification
3. 11. 3 have been exceeded.
If such is the case in lieu of a Licensee Event
Report, prenare and submit to the Commission within 30 days, pursuant to Specification
6. 9. 2, a Special Report that defines the corrective action z.o be taken to reduce subsequent releases to prevent recur-rence o-exceeding the above limits and includes the schedule for achiev'.ng conformance with the above limits.
This Special
Report, as defined in $0 CFR Part 20.405c, shall include an analysis that estimates the radiation expos'ure (dose) to a
t!Et~iBER OF THE PUBLIC from uranium fuel'ycle sources, including ail effluent pathways. and direct radiation, for the calendar year that includes the release(s) covered by this report.
Ii shall also describe levels of radiation and concen.rations of radioactive material
involved, and the cause of the exposure levels or concentrations.
If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violatioh of 40 CFR Part 190 has not already been corrected, the Special Re'port shall include a request for a variance in accordance with the provisions oi 40 CFR Part 190.
Submittal of the report is consiaered a timely request, and a variance is granted until staff action on -he request.
is complete..
b.
The provisions of Specirications 3.0.3 and 3.0.4 are not applicable.
t SURVEILLANCE REQUI REt iENTS 4.11.3.1 Cumulative dose contributions from 'iiquid and gaseous effiuen s shall be determined in accordance with Surveillanc(>>i",.equirements 4.11.1.2, 4.11.2.2, and 4.'ll:2.3, and in accordance with the metho'dology and parameters in the ODCH.
4. 11.3.2 Cumulative dose contributions from direct radiation from the reactor units and from. radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCH.
This Surveillance Requirement e
e shall be reouired only in the event the above Action a.
reouires the applicable ai cul ati ons.
ST.
LUCIE - UtiIT 5 2, 3/4 11-16
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3/4. 12 PADIOLOGICAL EHVIROt<tlEhTAL HOh'TORIHG 3/4. 12.
1 tiOHITORIt(G PROGRAH t'iITil<G COHDITIOH FOR OPERATION PR00t: 5 IIERB'l 60P7
. 12.
1 The radiological environmental monitoring program. shall be conducted as specified in Table 3. 12-1.
APPLICABiLITY: At all times.
ACT!ON:
a.
b.
Mith the cerr-.~.:~~e~ radiological environmental monitoring program not being conducted as specified in Table 3.12-1, in lieu of'a Licensee Event Report, prepare and submit to the Com!mi ss ior,, in the Annual Radiological Environmental Operating Report required by Specifica-tioh 6.9.1.11, a description of the reasons for not conducting the program as r quired and the plans for preventing a recurrence.
Mith the leiel of radioactivity as the result of plant. effluents. in an environmental sampling, medium at a specified
'location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar
quarter, in lieu of a l.icensee Event Report, prepare and submit tc the Commission 'within 30 days, pursuant to Specification 6.9.2, a
Special Report that ideni.ifies the cause(s')
for exceeding the limit(s) and def ines the corr ecti ve acti ons to be taken to reduce radi'oacti ve effluents so that the potential annual dose to A HEHBER OF THE PUBLIC is less than the calendar year limits of Specifications
3. 11. 1.2,
3. 11. 2. 2, and 3. 11. 2. 3.
Khen more than one of the rad',onuclides in Table
3. 12-2 are detected in the sampling medium, this report shall be submitted if:
C.
concentration (1) concentration (2) repor ing level
( 1) reporting. level (2) alien radionuclides other than those in Table
3. 12-2're de ected and are the result of. plant effiuents, this report shall be submitted if the potential annual dose to A HEHBER OF THE-PUBLiC is equal to or greater than the calendar year limits of Specifications
3. 11. 1.2,
3. 11. 2. 2 ard 3. 11. 2. 3.
This report shall include the methodo'logy for calculating the cumulative potential dose contrioutions for the calendar year from radionuclides detected in environmental samples and can be determined in accordance with the methodology and parameters in the ODCH.
This report is not required if the measured level of radio-activity was not the result of plant effluents;
however, in such an
event, the condition shall be reported and described in the Annual Radiological Environmental Operatirig Report.
Mith milk or broadleaf vegetaion samples unavailable from one or more of the sample locations reouired by Table
3. 12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The specific A confirmatory reanalysis desirable, as appropriate ompieted at the earliest within 30 days.
of the or',ginal, a duplicate, or a
new sample may be The resul ts of the conf i rmatory anal ys i s shall be time consistent with the analysis but in any case ST.
LUCIE -
UNIT qcf 3/4 12-1
0
RADIOLOGICAL EHVIROHl"EHTAL NOHITORJHG gc)
I (Q pgq mr n g~1 p~~J pa <'~g li(
locations from which samples were unavailable may then be deleted from the monitoring program>. ~ In lieu of a Licensee Event Report and pursuant to Specification 6
."~>, identify the ca se of the unavail-abilityy of sar>'ples and identi<y the new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCY< reflecting the new location(s).
The provisions of Specifica ions 3.0.3 and 3.0.4 are not applicable.
SURVE:LLAHCE REOUIPEHEHTS
4. 12.
1 The radiological enviironmental monitoring sam<ples shall be collected pursuant to Table
3. 12-1 from the specifi c locations given in the table and figure(s) in the OGCH," ard shall be analyzed pursuant to he requirements of Table 3. 12-l and the detection capabilities required by Table 4. 12-1.
ST.
LUC:E " UHIT g J.
3/-. >2-2
l n
l&
foal TABLE 3. 12-1 RADIOLOGICAL ENYIftONf1EHTAL HONITORING PROGRAHa
<3 Exposure Pathway and/or Sam ) 1 c l.
OI RL'CT RADIATION Number of Representative Samples and b) c) 27 Honitoring Locations Sampling and d)
Continuous moni toring wi th santpI.~ collection quarterly Type and Frequency d) of Analvsis Gannna exposure rate-qua rte rly.
2.
AIRBORNE Radioiodine and Par ticulates 5 Locations Continuous sampler operation with sample collccl.ion w~eckl
, or morc frequently if required by dust loading Radioiodine Filter:'-131 analysis weekly Partlculatc Filter:
Gros s be ta radi oac tivi ty analysis 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months following a filter chang
~
Gannna' so t,opj~
ana 1ys i s h) ol'omposit.e (by locat.ion) quarterly WATERBORNE a.
Sur face h) 1 Location s) l Location Weekly Honthly Gamma isotopic 8 tritium
. h) analyses weekly Gamma isotopic 8 Lritiun~
h) analyses monthly b.
Sediment from 2 Locations shoreline Semiannually Gamma isotopic ahalysis
. h) semiannually
" ':"'"'"""'ll HROIOLOG ICAL E "IVIltOHilLHTRL liOHITOIlll'lG PAOGIIRH Expos()re Pathway
<<n(l/o). Saml)'I c
'1.
I HGEST IOH H(m)ber oI llcpresc>>Lative Samples a>>(l b
~S~)n)
I e Locat) ons b) c)
Sa.npl ing an(l Col lection I:rcquency d) d)
Type an(I Frequency a.
Fisl) and Invert.eb) ates 1.
Crustacea 2 Locations.
Semi a)u)ua 1 ly Gamma isotopic analyses h) sc)ni annually 2.
Fi sh 2 Locat1ons Semiannually Gan))n<< isotopic analyses h) sclni an))(i<<1 ly b.. Food Products 1.
Droad 1 ea f 3 Locat i ons=1) vegetation
/
llonthly when available Gamma isotopic and h) 1-131 a>>a lyses n)onthly
TABLE 3. 12-1 (continued)
TABLE NOTATION PROOF E REVIEW'Opy Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, 1
ticn oi automatic sampling equipmen. or other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunc y
t hall be made to complete corrective action prior to +he end of the nex'amplino period.
All deviations from the sampling schedule documiented in the Annu 1 Radiological Environmental Operating Report pursuant to Specification
6. 9. 11. 1.
Specific parameters of distance and direction sector from the centerisne o
one reac.or, and additional descrip ion wnere pertinent, shall be provided for each sample location in Table
3. 12-1 in a Table and figure(s) in"the ODCN.
A" '
mav not, be possible or practicable to continue
.o obtain t.1mes s
t.
m In 1
the media of choice at the most desired lo ation or time.
n sampesof iem hosen for these instances suitable alternative media and locations may be c the particuliar pathway in ques ion and appropriate substitutions made w1<<hin 30 days in the radiological environmental monitoring program.
The following deiinition of frequencies shall apply to Table 3.12-1 only:
Meekl
- Hot less than once per calendar week.
A nsaximum interval of
'll days is allowed between the col'lection o i any two consecutive samples.
Semi-t~ioni v -
o es hl H t 1
s than 2 times per calendar month wi h an interval val of of not less than 7 days between samlple collections.
A maximum inierva o
24 days is allowed between collection oi any two consecutive samp es.
Honthl
" Not less than once per calendar month with an interval of not less than 10 days between sample collections.
uarterlv - Hot (ess than once per calendai Quarter.
Semsannua iy -
ne S'l - One sample each between calendar dates (January 1 - June 30) and (July 1 - December 31).
An interval oi not less than
~0 days wi be provided between sample collections.
1 11 The frequency of analyses is to be consistent with the sample collection frequency One or more ins rumen s, s
t t
such as a pressurized ion chamber s for measuring and recording dose rate continuously may be used in place of, or
>n t 'e rating dosimeters.
For purposes of this table, a
thermoluminescent dosimeter (TLD) is corsidered to be one phosphor; or.
two or more phosphors in a pac ei packe" are considered as two or more dosimeters.
TABLE 3.12-l (continued)
TABLE t<OTATiOH Refers o normal collection frequency.
Hore frequent sample.collection is permitted when conditions warrant.
Airborne particulate sample filters are analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow'or radon and thoron daughter decay.
in. addition to the reouirement for a qamma isotopic on a composite sample a
oamma isotonic is. also reouired
>or each sample havinc a oross be'a radioactivitv wh;ch is (.O oCi/m" and which is also (0 times that of the most recent con-rol sample.
h.
(>
(
~ >a.~'g~
(X. "
Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the
>aci lity.
gJ~M/
'.h St.
Lucie Plant (grab sample).
Atlantic Ocean, a.
a location beyond influence from plant effluents (grab sample)(
Discharges from the St.
Lucie Plant do not influence drinking water or or ound water pathways."
Sam>ples of broad leaf.vegetation grown rearest each.of two different of>site locations of highest predicted annual average ground level D/g, and one sam le of similar broad leaf veget tion at'n available location.
15-30 km distant in the least preval'ent wind direction H M>~~->.~~J~
~@i(,~ 0'> ~<<>
TAB
. 12-2 REPORTIHG LEVELS FOR RADIOACTIVITYCOHCEHTRATIOHS IH EHVIROHHEHTAL Sht'iPLES Repo> ting Levels Mater hna 1 ys i s (pCi/2)
Airborne Particulate or Gases (pCi/ma)
Fish (pCi/kg, wet)
Milk (pCi/R)
Food ProUuct.s (pCi/kg, wet) hn-5l Co-50 Co-60 2n-65 1-131 Cs-130 Cs-137 30,000
1,000 400 1,000 300 300 400
%I 30 50 0.9 10 20 30,000 10,000 30,000 10,000 20,000
.1, 000 2,000 60 70 100 1,000
'2, 000 0'".8 Ua-La-140 200 300 Since no drinking water pathway exists, a value of 30,000 pCi/2, is used.
For drinking water samples, a
value of 20,000 pCi/2 is used.
Tl>is is 40'FR Part ill value.
I s.I I' I TROLE 0v 12-1 OETECTION CRtRDILITIES Fon ENVInONHENTRL SRtlr LC RNRLVSIS' LOWLY LIthIT OF l)CTLCTIOtf (LLO)
~w Rntllys 1 s IJros s III'Lsl ll-3 tin-5'It Fe-59 Water (pCi/2) n geol MOP'.
15 30 Rirborne Particulate ol. Gas (pCi/lll )
D. Dj Fl S ll (pCi/kg,wet) 130 260 t'ai I k (pCi/E)
Food Products-(pCi/kg,wet)
Se<l i i~en t (pCi/kg,dry c
Co-50,60 Zn-65 I
Zr-Nb-95 l-l31 Cs-13Il Cs-j3/
Oa-La-140 15 30 15 jd 15 15 0 07
0. 05 0.06 130 260 130 150 15 60 60 00 150 1
180 Cf, no drinkin0 water pathway exists, a value of 3000 pCi/2 'sesy be used. 4~
, I G'
TABLE 4.12-1 (Continued)
P')fj
~
g D Ip// [f)(fl/
TABLE tiOTATIOH a This list does not mean that only these nuclides are t'o be considered.
Other peaks that.are identifiable, together with those of the above
nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9. 1. 11.
Required detection capabilities for thermoluminescent dosimeters used for environmen al measurements are given in Regulatory Guide 4.13.
cThe LLD is defined, for purposes of these specifications, as the smalles concentration of radioactive material in a sample that will yield a net
count, above system background, that will be detected with 95Yo probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement
system, which may include radiochemical separation:
LLD
4. 65 sb E
~
Y
2. 22 Y
exp(-Ut)
Mher e:
LLD is the "a priori" lower limit o detection as defined above, as picocuries per unit mass or volume, s
is the standard devia.ion of the background counting rate or of tIie counting rate of a blank sample as appropriate, as coun s per
minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume,
2. 22 is the number of disir>tegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A, is the radioactive decay. constant for the particular radionuclide, and 5t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of -E, V, "., and Dt should be used in the calculation.
ST.
LL'C.'E - UNIT g A 3/4 12-9
I TABLE 4. 12-1 (Con..inued)
TABLE llOTATJOH It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated. LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances miay render these LLDs unachievable.
In such cases, the contributing fac'ors shall be identified and described in the Annual Radiolooical Environmental Operating Report oursuant to Specification G. 9.1.1l.
LLD for drinking water samples.
if no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
3/4 12-10
RAD'.OLOGI CAL ""HVII":Oct!!EHTALt~IOH!TORIHG PI'<OOF 5 REMDY COPY 3/4. 12. 2 LAND USE CEHSUS t1ITIhG COiHDITIOH FOR OPERATIOH
3. 12. 2 A land use census shall be conducted and sl all identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sec-ors of the nearest milk animal, ihe nearest residence and the nearest'arden*
of greater than SO m'- (500 ft ) producing broad leaf vegetation.
APPLICABILITY: At all times.
J ACi Ohr:
a.
Mith a land use census identifying a location(s) that yields a
calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event
Report, id ntify the new location(s) in the next Semiannual Radioactive Effluent Release
Report,
'pursuant to Specification ~~H-.
6.9, i,to.
b.
>lith a land use census identifying a loca ion(s) that y>elds a
calculated dose or dose commitment (via the same exposure pathway)
'0M greater than at a location from which samples are currently being obtained in accordance with Specification
3. 12. 1, add the new location(s) to the radiological environmental monitoring program wi:hin 30 days.
The sampling location(s),
excluding the control station location, 'having the lowest calculated dose or dose t
commitmi,ent(s), via the same exposure
pathway, may be deleted fr omi this monitoring program alter October 31 of the year in which this land usa census was conducted.
In 'lieu o-a License Event. Report and pursuant to Specirrcation s~,.it, identify the new location(s) in the next Semiannual Radioactive Effluent. Release Reoor+
and also include in the report a revised figure(s) and table for the ODCH reflecting the n
w location(s).
c.
The provisions'f Specifications 3.0.3 and 3.0.4 are rot applicable.
SURVE I LLANCE REQUI RELlENTS
4. 12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best
results, such as by a door-to-door survey, aerial
survey, or by consulting local agriculture authorities.
The results of the land use census shall.be included in the Annual Radiological Environmental Operating Report pursuant to Speci ficati on 6. 9. 1. 11.
Broad 1 ea f vegetati on samp1 ing of-at~zrl~irsre~-di ff'<rent"kids-wf-va~~Mea may be performed at the site boundary in each of two different direction sectors with the highest predicted D/gs in lieu of the garden census.
Specifications for broad leaf vegetation sampling in Table
3. 12-1.4b shall be followed, including analysis of control samples.
ST.
LUCIE - UNIT
~+ a 3/4 12-11
PROOF-h PP,'IEN COPY R.'D'OLOG'CAL 'EHVIROHHEHTAL MONITORING 3/4. 12. 3 INTERi&BORATORY COMPARISON PROGRAM jt!IsTING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materiajs supplied as part of an Interl aboratory Comparison Program tilai has been approved by the
~
I Commission.
e APPL:CABILITY:
At ell times. ",,....it
..P i'ii; ~ ~>.,~. (~pSl) 6 ACTION:
a.
Mith analyses not being per formed as require'd
above, report the corr ect i ve acti ons to the Commi ssi on i n 'e Annual Radi ol ogi cal Environmental Operating Repor-pursuant to Specification 6.S. l. 11.
b.
The provisions of Specifications
3. 0. 3 and
3. 0. 4 are not applicable.
SURYEILLAHCE REOIJIRE!!EHTS
.12.3 A summarv of ihe results ob.ained as part of the above reouired terlabora.ory Comparison Program shall be included in the Annual Radiological nvironmental Operating Report pursuant o Specification 6.9.i. 11.
3/4 '2-12
(') ~ g pg~
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avc4 eh~ a5-~
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3/Q. tl.Z..S Cy;g'OWLVe. gpss gp~.p~
3)+.tl.2--
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>/4 l2.+ LAt"5 ASK CENSgg 3A,'l2.5 x,ATE.@LAB, compbg~yso9 P f'OGM~
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~ 3 IHSTRU(~)EHTAfIOt(
ASES
/)),~
3/4. 3.1.2r.d.-~'ir'-.-."3":2'EA6'l:GPaPROTECT,.-'!E AHD EHGIHEEREO SAFETY FEATURES Actuat> on'. oystees
) ns:) u)sentat)on and bypasses)!ensure tl'at 1)
". e'sso
" res Actuate'hn ac io".,'no.,or r tri"j wiIsl b lated
initiated Engineer ~r. I Sare~y Fe~,
u
~ !
I'hen ther<',~rameter mop its setp~)~i,
2) the:
reac o
bl A2tl Itored by e/;or.
deci fi ed co'. '.- =
E;re ches c
1 or'-c 1 ogi:-
1 to)b cnann
-icer ce om oA 'lereo 1 5 Mi2iAtai"."d, 3) e out of de".vice O'I.lclQAt festing r edundanay.I i 5 mai nia ~ qed to perm nce
<" ';.'suf i icien cnannz l
Or.ma i n ~~TAIs from div:hr'~"'I-.
.NK reliabif', it:
for the'r:
.i ntegr~:<ed used 1 rl til j ).
~ s T.,lie SI.
overal.
s
~
ab1 e al c2pab 1 1
~nd ~),
5 i.en) r inci'yis a Sv
'al e parame:,e
's.
RABILIT~ of these I
255
)")I
. to provi a
1 e the ove SA)f.st QI rit design nsj'he aksumpti ons oui I Qc redunAn"",j and di)ve'rsi y
-;ection 2ndmitigatiq~'n o
the faci~
,'condlil) with the ilable in transien consisten ed av
accident an I
e syst ns 15
'opera+ion o'ach of the lyses.
J quiremet,'its s
'. accide",t ala f.
I irvei 1 la I'ce
",e I:
5-:em funr.tiO:a l:
hese sys~ems
'ens J".e eciii d for hat the iginal 1 ca aoilitv is ma'Atainec comparaI)le
+o t)e o, ed at th mi p
er iodio;,'surv,i lian~a iy-est] pe-forsi nt t.o ons ra-'
I desi grf; star dards...'The
'p requ~nci es are sdr ficir
. j)
'",lie m
At of
,1 filum ab 1 1 1 iy.
ied fr t.e
)ll 5 C2~,
)
em ides
re'spon e.time; ctive "nd ESFIY
.hin thy tim at the spec
.=
quencies"provI eesureme tIiatth'Ctl3
imit, r t)'I n
fulnC<<
assurance I
>.'r ot chanr~i is c'omple,*"ed wit Ho cr,'audit wa~
takI~.A in I.
ciated arith e
acci der!t~: anal 1OA 2559 in the els wH ach
)ses.
ti:es assume) se charIA I
h respo se ti he anaiyses f bl e.
e d'emonstrate ffi 44surerp'Qnts pro.
",e ak'~ fi ned indijjted ad',not appl)c) l'.,'~!Responsi, ti)-='ay b or t~ftal cha,t'nel;;iest met f.'by any seri "v'.ide8 th2t 5
q!.entl,,
ove a
a a
t lapping
)the "s of spp ch ies..s demon'sirate
'ponse,'-.time verIi;ficat L.o c (
C'12ilne..
e. POnSe be 44monstra Id gy Qitherj 1) pn place, J
Sensor re hon may
. site."test mea 'ureme.ts or
onsl te or o
T
'ert;iied re oonse;times..(
4!
lng
.< p,!acement yen~,brs wlih a
s
(/
2) z Lg.l 1 1 I:
The Safe y in)ect>on Actua )on S)g-j, (SIAS) p toy))las d)rect aot)Iet) of:~he Containment Isolation Signal (CIS)'-"to ensure jb"...)'ainment isolation in he event of a sniall break LOCA.
. A.
(,')'s OA ACT.:AT-iOH Sl'STEH IHSl:..'HTAT~ON
'he f))ERASILITYIlf the
) sector protect>va'.and Engineered Safety Ei 'stores 3/4. 3. 3 MONITORING IHSTRUNEHTATIOH 3/4. 3. 3. 1 RAOIATION h)OHITORIHG IHSTRUHEHTATIOH The OPERABILITY of the'radiat'.on monitoring channels ensures that:
1) the ra'diation levels are continually measured in the areas served by the ST.
LUCIE - UNIT g t B 3/4 3-1
S
> HSTRU!'EHTATIOll BASES e
ndividua'I channels; and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and 3) suificient infor'mation is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consisten't with the recommendations of Pegulatory Guide 1.97, "Instrumentation for Light-Mater-Cooled Huclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," December 1980 and HUREG-0737, "Clarification of 7<HI< Action Plan Requirements,"
lac ve<zbe r 1980.'/4.3.
3.2 IHCORE DETECTOPS m,~p 'ra vvs 5
~
~ ith phe".$ oeci i i ed m-j.nj,mum sureme~'nts,obtained
.fio'".4.se of ne "on flux di '~ "
o
.-'p!The OPERABILITY of the incore dete'~ ors cor.",.';.':!e.f.~i of equipment~~~sures that
.~ Ie,-;mea th),s '5'"
-.m accurately:t'=-":resent the(".sp<
s.'i al
~ rea='j>> c';,re.
'J'(
"7 j
.3/.:: 'i'3. ". "i SFISHIC
<i NSTRU.':~HTATION':
ut, al the )~,.)
i
<;1 on is7',;
!!,.),
~ 7<
':i
<%re.r<
"'6e fac'il! -'Tt to!g determinL
'. i:- plan ursuant t'g<,~ppc~~dix "A" of.'0 0" R Part 1('<O."'<The with the reci'r<<",endations of';;-;.'.gjj'atory Gu>'~-'l. 12, Ear.hquakes," April 1974.~~
~~n t shutcsown is required,'nstrum~~
~~~ttation is cen'sist,"!lt 2~~
~~! he 0!..EQnBILI',I!I of tl.e! selsmlc lfisc.rumentatson ensures that. su<<. accent s~~
~~capabilitv'lis avai'i<Role to. promptly'ete".ine '.the magni~~
~~. de of.a seismic.everit I<~~
~~~ r~~
~
~~2nd evaiuc -e the t'.epponse~~
~~'~of those.j features irIportant tp.. safety.~~
~~Th i.s capabi 1 i ty's onse'~~
~~'.that used< i 'he'-!.~~
~~3/4. 3. 3. 4.~~
~~HETFORO LOGICAL IHSTRUHEHTATIOH a'nr~~
~
\\
~
~~s erg<~~
~~Wi"~~
~
~~amas1 The. OPEPP3~i.LITY. of'thi i~e.~eorol g<.=al instru!:.-<"tation ensL<,es.the~",~~
~~ufficie'nt mei'ecor)ling<car.',:data, is avails'ale'or es <mating!po-ahtial rad:a jon dp',e:~~
~~o the pub! ic a~:a resi>t off'aroutit!e or.:a'ci-.identai':i.elease of r='i<oactiv'e'jmater ials,--~~
~~to.the atmos'phere..:This~~
'c'apabilityi.,j;s riquir n;to ev'~i;uate p'ije !Ieedl'got i ni 4atii'g pj'OteCtiliC'~me>>aS'ureS KChgorjteCt. the,:;health arjd., Sar'<>'ty Of pl'ie'ubl iC and is cch~mtent wi'i l)>."<je recorlfil(ig~fation'sero(~ Regulatorjf>MYde =1.75$'<Onsite Heteorological Pr ograrns~'ebruary 1972.
~~~ rr,'i) 3/4. 3. 3. 8 ~'K="MO> ~-,SHUTDOMH INSTRUMENTATION Tj'PE<(AliiL'ITY og".zi e"; remote' l)dtdown;ins r 'ir!entat ion'r su".'sp'$hjbg~~
~~, suffic;. ent 'c.->abi l i ~y,.'-is available'o'a'.prermit-"shutdc!,;nv apd; maintensance o'i',;HOT STAND."'Y of ttle,'fac(iHtg frohm locations'u~spde of ~h>'ontrol r'ncr',-~~
~~This'j, capabv'lity is'equii'~c.. in tiie ev"nt confro/i room hab,.stability ij-<."ovst ajd'his consistent with Gen4:ev'1 Desig'n.,criterion"1'9 of 10 CFR 50.~~
~~ST.~~
~~LUC! = -~~
~~U<<<T d!, I B 3/4 3-2~~
~~Pi'0".F 'EYlBY COPY 1HSTRU:"iEHTATIOH BASES 3~~
~~/4. 3. 3. 6~~
'ACCIDEH I YiOHITORIHG IHSTRUYLHTATIOH "The 0."LRABI!:.'!Y oi 'le acc.:.-i="'nt mo:,to! in~ instr.:.!..:Tliaticn'ensures'hat sufficient info!':iiciion is,availa'..I e on s'lec-,.-"d plant'j~arameters to mc.'ol
/
~~an~.'ssess tf'iese variables.followi'pg an acciident.~~
~~This capability is'on~~~
~~i 5 i'.nt with ihe,. ecoiM; endati Gris of Rf gul a%01 y Gul oe 1. 97,~~
~~'!InstrIimentati on for Lio>:.-Ma i;.", "Cool ed Huc! ear Pl aihts to.i'.5ses.":, Pl ant C nditions Dur ing and Fo) iowi'r~g'n j<ctcider!'-;" Deca-:.ber 1975 ani.". gUR '! 0"78~~
~~"'Yi' Lessons.~~
~~Learned Tq,~~
~~~> Force 5"at s Repor ar ';hort';7erm Recom.-;,!."l.oations".'=i"-~~
~~ly',~~
~
~~3/4. 3. 3. 7 F,':::!";: DETECTIOH IHSTRUt~EHTATIOH Xr~~
~~.,i,'GPERABIL"'T~'.of tihe~ i,:re detec" 'T'on ins'",'.I:menta,ion ensur es that adequate~~
~~'arning capability is available for., the promot detCion cf fi".=-"s.~~
~~Th)',",'apabi!~~
~~ity is required ih order to ¹tect aid loc-'~~
~~fires in'h'eir cari'y stage-.:;~~
~~Pro.pt d",.tec;:ion of fires iv'i]l l'educe the po.entiaT for:.damage Ito safety 'related equip!:.-"nt 'and is 'an i.ntegral pleme!;t i.l the 'overa!1 facil'.ity fire i otec ion p;oar-:m.~~
~~g I~~
~
~
~~".ne event ';"at a por~~
!on of ti!p fire oetectjon. ins" Tumen tion ino><<,"'a" te, the es.;,::aliis.'!me:-.;.:OT frequ-;.""'irie,".atrols:in.tl!e affecte~d arieas is T;-auired to provide ceteciion capabi-sty until the inc>~rable i'nsirumei:!.,ation is;;-s ored to OPERABILI~.
~~/4. 3. 3. 8 LOOSE" P."';".7'. DETECT: l.r z IHSTRUt<":t'TATIOH~~
~~. Thy'OPERABILITY',of the,'!Ocky-par~~~
~~deiectionj,",;-:.,rumeri~""i Jn ens...~es that Suf iC i.nt',Co-paLility';is vgii1tb'le ta tietai loo."=,'r,::t=a11i jevtsj.;.,'he primary sys"',em aild av01d,'oP fillt1'te camiage'o '"~~
~~~ "\\"! v sys72m -zcfii...'~jents.~~
~~The al low~bi e oui:-o.f-servi.c.-'. 'ames ance,"<Urveil I ~pc=- r'equ',er.i~!>.s ~.re/'.insistent with:-..he rec'oniendatio is':of Regula>Cry Guide.,'"<33,~~
~~".'..'oo'e-Pai'" ':;etection Prog!',Im for the Primary System ot Light-Mater-Cooled R'~actors,"..",':;~1ay 1981.~~
3/4.3.3.9 RADIOACTIVE Li UID EFFLUEHT IHSTRUHEHTATiOH The radioactive liquid effluent ins rumentation is prov',ded to monitor and control, as app! icable; the releases of radioactive materials in liquid efiluents during actual or poten-ial. releases of liquiid effluents.
~~The alarm/~~
~~trip setpoints for these instruments shal'1 be calculated in accordance with the methodology in the ODCYi to ensure that he alarm/trip wil 1 occur prior to exceedino the lim~itsgr 10 CFR Part 20.~~
~~The OPERABILITY and use of this instrumentation inconsistent with the reouirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.~~
~~gyp~~~
~g
~~' no" ST.~~
~~LUCIE - UNIT ': L.~~
~~B 3/4 3-3~~
~~I!'ST P Ut"E ts TATI 0t<~~
~~BASES.~~
3/4.3.3.10 RADIOACTIVE GASESOUS EFF1.UEtiT IhSTRUtiEHTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the re1eases of radioactive materials in gaseous efflu n s dur',ng actual or potential releases of gaseous ef luents.
The alarm/trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCH to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.
~~This instrumen'tation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the was.e gas holdup system.~~
~~The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part SO.~~
"I'.3.4 Oo.B',TH 0" Rsp.cE i'ROTECT!Oh v
~~."; Thi= rneciric~~
~~>o-n'.i: prov.ided to en.:.::-',a that.>e tgu'.'i:"eoversza'.3r'.~~
~~',pr'o ect~~
~~('n 1nstrumentat s Gn <<nd 't he tur bi re sspeed conti 0) "4al pcs a c OP"..'~~
E
~~. and '-.:-'1-prO;eCts th turbine frOm.eXCec=-iVes OVerSpeed.~~
~~~ PrG~sectiC i O~~
~~"."lb1ne~~
~~'. exce>> s~~
~~. Ve G"airspeed i s.reoui; ed s i llcerccxce-sive. ov.=srs".~eed o>~~
~~h-,, +ur.-:~'ould a~~
~~gen r,:.:.e pots n'ail'aeaai;-,:j mis slee'l irh,could i;,r.-ct:.=.nd'sar',.)a-e-'y v~~
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'related compo;:ents,
',.quipmers~ or- <t>ucturc"-.-'.'.'ssg ST.
LUCIE - UNIT $ i.
8 3/4 3-4
DIOACTZVE EFF( UEHTS PROOF K REYIP; COPY ASES 3/6. 11. 1:1 COHCEHTRATIOH This specification is provide to ensure that the concentration of radioactive materials released in
-quid waste effluents from the site to UHRESTRICTED AREAS will be less t.".=". the concentration levels specified in 10 CFR Part 20, Appendix 8, Table Column 2.
This limityticn provides addi-tional assurance that the levels o= radioactive
..aterials in bodies of water outside the site will result in ex=osures within (1) the Section II;A design objectives of Appendix I, 10 CFR P=rt 50, to a individual, and (2) the limits of 10 CFR 20.106(e) to the popvla-'on.
The concentration limi. for dissolved or entrained noble gases is based 'n the assumption that Xe-135 is the control ling rad;oisotope and its MPC in a-.r (submersion) was converted to an equivalent concentration in water using the m='.hods described in International Commission on Radiological Pro ection (ICRP) =.ublication 2.
3/4. 11. 1. 2 DOSE This speci ication is provide to implement the reoui rements of Sections II.A, III.A and IV.A of A==endix I, 10 CFR Part 50.
The Limiting Condition fo. Operation 'implements
=he guides set forth in Section II.A of Apper di x I.
The ACTION statemen+ s "rovide the r equi red oper ating f1 exibi 1 ity ard at the same. time implem nt the "uides set forth in Section V.A of Appen-dix I to assure that the releases cf radioactive mater ial in liqu'.d efflvents will be kept "as low as is reasona'iy achievable."
The dose calculation
~
methodology and parameters in the C3CM implement the reauirements in Sec-tion III.A of Appendix I that confcrmance with the gvides of Appendix I be'hown by calculational procedures "ased on models and data, such. that the'ctual exposure of a
MEMBER OF THE PU8LIC through appropria e pathways is unlikely to be substantially underestimated.
The equations specified in the ODCM fol calculating the doses due
=o the actual release rates of radioactive materials in liquid effluents are
" nsistent with the methodology.provided in Regulatory G ide
~~1. 109, "Calculaticn of Annval Doses to Man from Routine Releases of Reactor Efflvents for....e Purpose o~~
~~Evaluating Corpliance with 10 CFR Part 50, Aopendix I," March, l976 and Regulatory Guide~~
~~1. 113, "Estimating Aquatic Dispersion of Effluents free Accidental and Routine Reactor Releases for the Purpose of Implementing Ap" ndix I," April 1977.~~
This specification applies to -he release of liquid effluents from eacn reactor at the si e.
For units wi:n shaped radwaste treatment
~~systems, the liquid efflvents from the shared system are proportioned among the units sharing that system.~~
ST.
LUCIE - UHI!
P 3/4 ll-l
RADIOACTIVE EFFLUEHTS
<ASES
/4. 11. 1. 3 LIQUID'lASTE TREATMENT The OPERABILITY of the. liquid radwaste treatment system ensures that his sys en will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of this sys iem be used when specified provides assurance that the releases c
radioactive materials in licuid ef<luents will be kept "as low as is reasonably achievable".
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the des I Qn cbjecti ve given in Sec iion II. D of Appendix I to 10 CFR Part 50.
The speci <ied limits governing the use of appropriate portions of the liquid, radwaste ireatment sysiem were specified as a suitable
<raciion of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
3/4. 11.2 GASEOUS EFFLUEHTS 3/4.11.2.1 DOSE RATE This spec fication is provided to ensure that the. dose at any time at and bevond the S
TE BOUNDARY from gaseous e<fluents from all units on the site will be within the annual dose limits of 10 CFR Part 20.
The annual dose limits '
a e
t t
e re. ihe doses assocIated with the concentrations of 10 CFR Part 20, Appenoix B,
abl<e II, Column i.
These limits provide reasonable assurance that radioactive material discharged in gaseous ef< luents. will not result in the exposure of a V<EMBER Or" THE PUBLIC, either within or outside the SITE BOUHDARY, io annual average concentraiions exceeding the limits specified in Appendix 8, Table II of'0 CFR Part 20 (10 CFR Part 20. 106(b)).
For N:"."<BERS OF THE PUBl IC who nay at imes be wiihin ihe SITE BOUNDARY, the occupancy of'ha" l'<=t<BER OF THE PUBLIC will usually be su<ficiently low to compensate
<or any increase in the atmospheric difrusion factor above that for the SITE BOUHDARY.
The specitied release rate limits ".estrict, at all times, the. corresponding gamma and beta dose rates above background io a HB<BER OF THE PUBLIC at or beycnd the SITE BOUHDARY tc less than or equal to 500 mrems/year to the total body or to les..
than or equal to 3000 mrems/year to the skin.
These release rate limits alsc r'es i ict, at al 1 times, the correspondi ng thyr oi d dose rate "bove background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.
~ ~
~
~ ~
~
~~~
I Tjhs s'spat.'.fioation applies~to~he reYease~=gaseous ef~en~frofa el 1 reactors at~the site.
The required detection capabilities
<or radioactive materials in gaseous i waste samples ar e tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detec ion limits can be found in HASL Procedures
~~Hanual, HASL-300 (revised annually), Currie, L. A., "Limits for qualitative Detec-ion and quantitative Determination - Application to Radio-t i~~
A chemistry," Anal.
Chem.
"0, 586-93 (1968),
and Hartwell, J. K., "Detection imits for Radioanalytical Counting Techniques," Atlantic Richfield Hanfcrd ompany Report ARH-SA-215 (June 1975).
ST.
LVCIE - UHIT P i, B 3/4 11-2
RADIOACTIVE EFFLUEHTS BASES This specification applies to the release of gaseous e fluents from all reactors at the site.
For units with shared radwaste tree:.-,ent
~~systems, the gaseous effluents irom the shared system are pi oportioned among the 'units sharing that system.~~
3/4.11.2.2 DOSE -
HOBLE GASFS-This specification is provided to implement the reouirements of Sections II.B, III.A and IY.A of Appendix I, 10 CFR Part 50.
The Limiiting Condition for Operation implements the guides set forth in Section II.B.of Appendix I.
The ACTIQH statements provide the required operating flexibility and at the same time impl ement the cuides set forth 'in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous ef> luents will be kept, "as low as is reasonably achievable."
The Surveillance
Requiremen's implement the ".e~uirements in Section III.A of Appendix I that con ormance with the guides of Appendix I be shown by calculational procedures based on ",,odels and data such that the actual exposure oi a
HEHBER OF THE PUBLIC through 2pplopriate.pathways is unlikely to be substantially under-estimated.
The dose calculation methodology and parameters established in the ODCH for calcul ing the doses due to the actual release rates of radioactive noble gases in gaseous efiluen:s are consistent with the methodology provided f
rr t
t e
in Regulatory Gdide 1.109, "Calculation of Annual Doses to Han from Routine Releases of Reac or Effluents for the Purpose of Evaluating Compliance with
~ 10 CFR Part 50, Appendix I;" Hiarcihi 1976 and Regulatory.
Guiae 1.111, "Hethods for Es ima ing Atmospheric 'Transport and'ispersion of Gaseous Efiluents in Routine Rel eases from L ght"Matel Cool ed Reactors,"
Revi s i on 1, July 1977.
The ODCH equations provided Tol de'ermining the air doses at and beyond the SITE BOUHDARY are based upon he historical average atmospheric conditions or real atmiospheric conditions.
Thl 5 speci ficati on. appl i es to the rel ease of gaseous eff1 vents fromi each reactor-at th site..
For uni s wi=n shared radwaste treatment
~~systems, the gaseous efiluents from, the shared system are proportioned among the units~~
'haring that system.
3/4-1 1
~ 2
~ 3 DOS RAD 'IODIH S
RAD 'ACTIVE HATERIALS IH PARTI CULATE FORM AHD RADIOHUCLIDES OTHER THAN HOBL-GASES This spec'.fication is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condi-tions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTIOH sta ements provide the required operating flexibility and at the semi,e timie implement the guides set forth in Section IY.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably ac ievcble."
The ODCH calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Apoendix I that conformance with he guides of Append x i be shown by calculational procedures based on models and data, such that the actual expo-sure'of a
HENBER OF THE PUBLIC hrough appropriate pathways is unlikely to be substantially unde",estimated.
Tiie ODCH calculational methodology and parameters B 3/4 11-3
RAOIOACT'VE EFFLUFNTS Ffi00!'.REVIEW CDPY SES for calculating the doses due to the actual release rates of the subject
!<ateri al s are cons i stent with the methodol ogy provided in Regul atory Guide 1. 109, "Calculation of Annual Doses to Hah from Routine Releases of Reactor Effluents for. the Purpose of Fvaluating Compliance ~ith 10 CFR Part 50, Appendix I," Harch, 1976 2nd Regulatory Guide 1.111, "Hethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Rou iin<e Releases from Light-Mater-Cooled Reactors,"
Revision 1, 'uly 1977.
These equa ions also provide for determining the ac. al doses based upon the historical averaae aimcspheric or real meteor-ological conditions.
The release rate speci ications for iodine-131, tritium<,
and radi"nuclides in particulate form with <"al< lives greater than 8 days ar e dependert upon the exisiing radionuclide pai< ways to man, in the areas at and beyond t.".e SITE BGUNDAPY.
The pathways iha. were examined in the develooment of these calculations were:
~~1) individual inhalation of airborne radionuclides,~~
~~2) depcsition o< radionuclides onto g'"een lea<y vegetation wi ih subsequent~~
~~'consumpt-.on by man,~~
~~3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of he milk and meat by man, and~~
~~4) depos'ion on the ground with subsequent~~
.exposure of man.
This specification applies to the release of gas'eous e;flue'nts from each reac.or at the site.
For units with hared radwaste treaimeni
~~systems, tre a~~
a n
r r
aseous
=ffluents from the shared system are proportioned am<ong the units hal i,,g hat system<.
3/4. 11.2.4 GASEOUS RADMASTF TREATMENT The OPERABILITY of the GASEOUS RADMASTE T?EATHENT SYST.H and the V NTILA!.ON EXHAUST TREATH<ENT SYSTEH ensures hat the sysiems wi 11 be available for use '-henever gaseous ef<luenis reauire ireatment prior to release to the environm=-nt.
The requirement that the apprcpriate portions of these systems be used,
~hen specified, provides reasonable assurance that the releases of radicac-'ve mate".ials in gaseous effluents wi!1 be kep+ "as low as is reason-ably ach'evable".
This specification impleme<its the requirements of 10 CFR Pari 50.:.5a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the des';:z objectives given in Section IT..D of Appendix I to 10 CFR Par't 50.
The spec'<ied limits governing the use of appropriate portions of the systems werc speciried as a suitable fraction of the dose design objectives set forth in Secti:ns IT.. B and II. C of Appendix I, 10 CFR Part 50, fcr gaseous effluents.
3/4. 11. 2. 5 EXPLOSIVE 'GAS MIXTURE This specification is provided to ensure that the concentration of
. potentia ly explosive gas mixtures contained in t<ie waste gas holdup system is maintain:" below the flammability limits of hydrogen and oxyaen.
Maintaining ihe conc:-atration of hydroaen and oxygen belo~ their flammability limits provides assurance that the releases of radioaciive materials will be controlled in confc"vance with the requirem<ents of General Design Criierion 60 of Appendix A
o 10 CF
. Part, 50.
ST.
LUCI: - UNIT g 5 8 3/41-4
RADIIOACTI VE F FLUEHTS PROOF u RPIEYl COPY BASES 3/4i ll. 2. 6 GAS STORAGE TAt<KS Restricting the quantity of radioactivity contained in> each gas storage tank provides assurance that in the event of an uncontrolled release of the ta'nk's con ents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.
This is consistent with Standard Review Plan 15.7. 1, "Maste Gas System F ailure."
3/4. 11. 3 TOTAL DOSE This soecification is proyided to meet the dose limitations of 40 CFR Part.
190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.
The
. specification requires the preparation and subnittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to t,he total body or any organ, except the thyroid, which s>"ail be linited to less than or equal to 75 mrems.
For sites containing up to four reactors, it is highly unii kely that :he resultant dose to a
YEHBER OF THE PUBLIC will exceed the dose limits ef 40 CFR Part 190 i> the individual reac+ors remain within twice the dose design objectives of Appendix I, t
r t
r e
and if direct radiat,ion doses from the reactor units and outside storag tanks are kept snail.
The Special Report will descr ibe a course of action that should result in the limitation of the annual dose to a
H=.ABER OF THE PUBLIC to within the 40 CFR Part 190 limits.'or the purposes of the Special Report, it may be assuned that the dose conmitment to the tlEHBiR OF THE PUBLIC from other uranium fuel cycle so'urces is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at, the sa.>e site or with n a radius of 8 km rus be considered.
If the dose to any llEHBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a req est for a variance (provided the release conditions resu'lting in violation of 40 CFR Part 190 have not, already beon corrected),
in accordance with the provisions of 40 CFR Part 190. 11 and 10 CFR Part 20.405c, is considered to be a tin>ely request and ful>ills the r quirements of 40 CFR Part 190 until 1<RC staf> action is completed.
The variance only relates to the lini s of 40 CFR Part
~~190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Soecifica-tions 3.11. 1. 1 and~~
~~3. 11.2. 1.~~
An individual is not corsidered a HEHSER OF THE PUB! IC during any period in which he/she is engaged in carrying out any operation that is part. of the nuclear fuel cycle.
B 3/4 11"5
3/4. 12 RAD 'OLOGI CAL "HVIROHl~iEHTAL t'iOHITOR'G BASES 3/4. 12. 1 llOHITORIViG PROGRAH The radiological envhonmental nionitoring program required by his specification provides represerstative measurements of radiation and of radio-active materials in hose exposure pathays and for those radionucl ides that lead to the highes" potential radiation exposures of YiEHBERS OF THE PUBLIC resulting from the sta'ion operation.
This monitoring program implementsSection IV.8.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiologic 1
es iluerst monitor ing program by veri iying that the measurable concentrations of radioactive materials and levels of 'radiation are not higher than expected on the basis of'he effluent nseasurements and the modeling of the environmental exposure pathways...'The initially speci iied rionitoring program will 'be effec.ive for at least the first 3 years of commercial operation.
Following this period, progran changes may be initiaied based on operational experience.
The required detection capabilities for environmen al sanple analyses are tabulated in terns of the lowe> limits of detec ion (LLDs).
The LLDs required by Table'4. 12-1 are considered optimum for routine environnen al neasurements in industrial laboratories.
It should be recognized that the LLD is defined as an a oriori (before the rect) limit represen ing the capabiiity o
a m:
i (
parti cul a; measurer>>ent.
Detailed discussiion of the LLD, and other detection limits, can be found in HASL Procedures t,anual, HASL-300 {revised annually),'urrie, L. A., "Limits for qualitative Detection and guantitative Determination - Aopliication to Radiochemiistry," Anal.
Chem.
40, S86-93 (1968),. and Hartwell, J. Y., "Detection Limits for Radioanaly ical Counting Techniques," Atlantic Richfield Hanford Company
~~Report, ARH-SA-215 (June 1975).~~
8 3/4 12"1
3/4. 12 RAD IOLOG ICAL'>NVIROti>~>EttTAL ! lOt<ITOR "tG BASES pp00!: g pg)E't>
C0 3/4.12. 2 LAND USE CEHSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUttOARY are identi
>ied and that M>odifications to the radiological environmental monitoring program are made if required by the results of this census.
The best informa-'ion from the door-to-door survey, from aerial survey or from consulting with local agricul'ural authorities shal>
be u ed.
This census satisfies tho requirem>ents of Section IV.B.3 of Appendix I to 10 C;"R Part 50.
Restricting the census to aa dens o>
gr e=ter than 50 m
provides assurance tl.at significant exposure pathways vip leafy vegetables will be identified and monitored since a garden of this size is the minimum required to pioduce the quantity 26 kg/year of leafy vegetables assumed in Regulatory Guide 1. 109 for consu>>ption by a child.
To determine this minimum garden size, the following assu>"lptions were made:
1) 20K of the garden was used for growing broad leaf veaet=--'ion (i. e., similar to lettuce and cabbage),
and 2) a vegetation yield of 2 kg/m2.
3/4. 12/3 I>iTERLABORATORY COHPARISO!i PRGGRA>"l
~
~
~
~
The requi rement for participation in an approved Interlaboratory Comparison Program is provided to censure that independent checks on the precision and
. accuracy of the measurem>ents of radioactive material in environmental sample matrices are performed as part of i>he qu'ali'.y ass >rance program for environ-mental monitoring in order to demonstrate that the results are reasonably
'alid for the purposes of Section IV. 8. 2 of Appendix I to 10 CFR Part 50.
ST.
LUCIE - UNIT 55.
8 3/4 12-2
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6. 0 AOHIHISTRATIVE CO}iMOLS 6.1 RESPOHSI BILITY 6.1.1 The"PTaan Manager shall be responsible for overall facility'peration and shall delegate. in writing the succession to this respon-sibility during his absence.
~~6. 2 ORGAHIZATIOH I~~
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\\ 1 OFFSITE:
6.2.1 The.'offsite 'organization for facility manageme'nt an'd, technical:
."'uppoi.t shall.=be-as. shown on Figure 6;2-1;.'
~
r a
'I FACILITY:STAFF:
, r 6.2:2.',
. The 'Faci 1 lty, orga>>ization shall be" as. shown} or..'Figure'.;.6.'2-.2 and:
'.:",!., '::.".i","'.'.:EaCh iOn::du y: Se'nil";t; S hall';. be'Or
}jO'Seed:.O
}'at'>1'eaS i 'the'rainimimt (-..*"
"."":shift crew composition shown in'Table'}6.Z-'1'..';."-"",.';."'
a O'..; 't. 1eas t=ane;:~l ".(.ased-'3pera tor;-.shal.l:'be
'i'ff-4I >>"-:corn c>ply-.n'om~
~ When~i}etfkl<i~-""i~'"h~-~aotO~".=f ~ -': ':~." rc'.t.::"":,":At';.'.1east ~~~;-";.~"*='er:se'FJ'~a<=~vo."~s, shal'1'-. b'o. p'r'esenK',in.'the'.'-
~~-.';-,'};".'}.".." '.":;;control rooim: during: >>;."..~:,0",;".Yt~i ~-~ p;;;scheduled~~
".reactor'a-.';=';"-.,'..','.; .':.; "::; -,"..,'-'%PI'.egin and-'du" ing.'. c'yj>'rom reacto'r.:.-..tri ps..'.::,'""'-.'.,:,'.-;..,':.-;."= -.:.,';"."...An';.indiYidual'. qual ified:, iIl'.radiati on prote'cti on."procedures'-- shall . be.'on'-si te when.-fuel;:-:is..in the reac'tor*:..."';".'-..".;:;;.-.'::.::., -.,',;-"'e,"-'Al
~~l. U:"X"Vi;MPYM'tS:;after:.: the.,-sl nitl c",1~~
~~. fiy1'":1oadi'n'g ',sha 1 1 'be...':. '.- '":-;-...."",~l.'@~3"., <'"'== }pe,">"5e<<;, by 'e'i ther.. a. c'lceiis ed-Se'nior-'"Remen'8'.~~
~~..';.:::.~~~
. 'perator-oi'.=,S~'ci'.--"~~eYi t '"<<0p=ato~45NltUUy to. Fuel Handl'ing"., '..." ': ".',who; has'.no: other 'concurrent'responsibilities" during';.tIj's "r . '.."f,:..':. A:"~~~r~~-.og';at 1 east."-8"ji i@~rw>ha11.." be'ma Tntaine}d aonsi te .. -';-. '.,".'.".-.'0,'al 1'.:.times.:, The'ire Br'igade.:shall,:not include'-3':m mbers::..:.
~~-'--'., -"::-,:,-':of, the minimum'shi'ft. crew nece's'sary.-.for;".safe:-sIlutdtown'"of.'he:..<,~~
';:..'~:-."",.":.:.'unit',or -'any personnel: required fo'r.other=.'essenti al: funrctions'". '.:. during a fire=.ei}<rqency. ~, ~ a ~ ~ '1 ST.;.'.LUCIE -, UHIT:.1' '-: 'ftmendmerit",No.. >
~ LfT 'I ~ ~ I A. ~ ~ ),.)r, ~ ~ ~ ~ >>,r r '>> ~ i ~, ',Vfttthtsfo\\kf }, << H>>JCtthhhko Otktkht tfr Istlhl'fo 1 1 -.' ",r Ofinvr VICE rntslotkf i,g>>>> r1I >>H = VICE fntSIOtnf fowtn ntsnvn:ts (Oihrhflt RUC'lth AEYICW TOARO 1 >>f,t, ~ i + ~ frhkhCCA Litthtfk0 AHO HVIHOH)ftkfht fthhf>>IHC 4 ltAHACEfl0'f VALITY AS!VAANCE slhfIAOEACf H OCCAM AA ANALYSIS SIAMACEAOf I'owtn Afsovncts IIUClthil ' r.i ~ i'A@AnthOF rnwir>> Atsovncts SffiVI(ts ~ I)>> '.. ~Ik(LOOTS HEALTHTNYSI(S,TUEL, ~. "'AIIACCIICHT.OftnhffnifsCOLLO:T, ~ ~ OCSICk RCYIttf,nth(IO>>l tfiCUI~ " i'*"i ~ EC:llffC.RAOIOCHtftfstRY,flnE TIIOTCCTIOIIAO)IUIISTAATOA,ET4.:."* '>>~>>)l '.'. ~ ". fU i~ ~i" ~8 ~ ~ ~ POWER AESOUACls ..:- Stt flcohl @st )>>. TOWER ACSOVACts st~ff Au(tfhn ~ 1 .-":,. COXnCOIOOH titvhttll ~'r',. r ~ r>>1 ...Flgufct 0.2-1;.Offsito Organ1:ation.for Facility Managarnant and ':-'.,:-:,'.:.-'~Tachnicai Stfjport -.: .r, ) '>>j
i I Ai I ~ ~ ~ ~' ethht sthnhctn L ~>>I>> >>W I tohtn h($00n.ts sfhrr lt(ALIHrHYSICS $1ICIALIST rotvtn hl $vvltcl5 5 Ihrr Itihl 1r 6 Il CI I6N AOMINI$'tnhlolt IYT I l' ECHNICAL "S TAIS >>i >>H ~,I ~ 'l '+ ~ l ~- 'AIOMINIST1ATIYE ',v"ASSISTAllf ' .I rp. i~ I "r"I" ~ A ~;* 'VA(tfTCOXTho ~ f $1hle ': l or(1th'flolls SUr>>ittnl(NO(AT ~Nttguilfnt ANO ~. ' CONIAOL', Svl(AYISVA ':.AISISTANI:I Sur frINTINO(Prf (LECiintCA'L L'thlhffnhhcf ASSISTAIIT Surththlft<otnf M'(CHNICAL": Mhlh1fNANCI SICultllY>> svrthvtson ~ V>>. >>W ~VV Cr(LIISrhf cUr'ilvlson HEALTH rHTSICA SVrtnY150h Sho Cr flthTIONS 5vrlhYIsott fitAININO svLfnvtsch lttACf0lt Svrtrvp/ch 'I ~- H (NCINfflt5 f(CIIKICIANS '(NCIKTtns tICHrllCION5 EKOIK(tns Tt CHNICIANS .OuhhOS." ~ l CLCnhs I V 'NCIN((tts AII0 1IC.'tnt CANS ENOIN(fhs Alto 1ICtt'llC1ht: 5 )00 r LANI surtnvtson ll1 5 Ir CINEtrts ArtO 'IICHLIICtih5 INSTAU'I IN 1 ANO 'ONIAOL $1(CIAI1$ 1 5 Alrh(ltllC($ CHI(t (LECTOICIAN tttCTIIICIAIIS her ht NIIC($ .. Ht(1(hs ~ Mltloitflthhct f0lt(LIAN~ MkC LtINI5 1 MtCHhlttCS Arrh(NIICES ~ 'ktLr(A ~ I i, , ~ .l 'I I II A'" A.IVV~ r'% rfg depth ~..'i ITAICN f KCIKI(n 115 5 contno( cthttn onnhloh 111 =fcsll(ON Tlf((,Y VV
~~Ills AICIINISAOrtfhlo Lttttlf,;...~~
~~~', t .,'t,,~ 'v,." v .LL, ~ ' ~ [g','~,1 ~ ht AtthIACI0$0rthrLTV'LIIIIN!:;=,:; 10.:'i 'LL I L ~ l SIOILLLNPVIlh10(lhlllllthlt4N.I'.,"', i ' . ~.. ~,A. - ',,t.; I...,,~~
~~~-..".-Ffgufts 0,2.2'; FCCfffly Ofg=ftfZrtfOITSt, LLICfO Pfcnt, Unft 3.~~
ONLICENS(0 or(nhtohs t/5 IS
Table 6.2-1 i<ruli~y-: SHIFT CRE;! Coi~POSITIO~P ~ ~ HITH THE OTHER UNIT IH l'iOOES 5 OR 6 GR DE-FUELED POSITION HUH8ER OF IHOIYIDUALS RE(VIREO TO FILL POSITION SS (SRO) SRO RO AO STA %DES 1, 2, 3, 5 4 1 2 ViODES 5 b 6 1 2b Hone POSITION WITH THE OTHER UtilT:Ih HODES 1, 2, 3, GR 4 hU"BER OF INDIYIDUALSRE/VIREO TO FILL:POSITION 0 ~ r h.":.') -. 'i
~~-:c~~
~ ?, f Qi*gr VQOES 5 c': 6 i ~ tBDES 1,'? 3, 6 4 " la 2 1a ~ Hon .1'one 'S {SRO) SRO'O ~ STA" 6-4 ~ 0 1 SS. -.Shift: Supervisor PO - Licensed i?eactc. Operator 'SRO'-. Lfcen'scd Senior Reactor'0'p'erator -" Auxf!iary':Operator ';,'-?STA,-..-Shift"..lechnfcal,Advisor': ~,.-','i -'".'-. Does'ot include the licensed'enior 'Reactor Operator 'r Senior.-Pei ctbr,- ,: Operator'Limited to Fuel;1landlfng,,supervising CORE ALTEPATIOHS-after the .fnitfal fuel loading. -"'. ":. Shf ft cr~i cenposftfon'ay be less than the mfnfmum-requirements for-a period of time not to.exceed'2 hours in ordec..toacco7raodate unexpected;,. ,absence of. on'duty'shfft,crm members provided,fmmedfate action fs taken,';, ='o.'r estoce,the, shf ft cern composition to i;fthin.the minim."n.r equirements", of Table..6;2-'1".;" \\ gg 'his bloc'lone. applies.fn.'t'.OAES '. through 6 prior to Unit.2:operant".ng'.-',"'. license fssuance'and ccmencement of initial.fuel loading'. p t a/ .-.Individual.ray.:fill the same'position on tne other unit. Qb -..One':.of the.t~o required.individuals may fill the same position on;the" other. unf t.'.' 1 ~, ~ . ~,-,~ . i ~ .ST.;,LUCIE -'. UHIT'1 . ="',:=,',, Amendment tlo';.'g7, 51 ~ C ~ ~
( ADHIt< ISTRATI'~'E CO!<T,":O'
~~6. 3 FACILITY STAFF UALIFICATIOHS 6.3.1 rEdcl}'.membe'r of the facilitymtaff-shall meet or exceed the minimum qualifica'tions of:gHSI"'t!18'.*1.-.'.1)71 'for co iparable positions, hi'ceti~~~~
~~~ for (1) theCR<dia'i-,io'n'rotection'.=Jtarvgi.".'.~~ho'-";.sriall'- mieet or exceed the jualifications of (Regulator>,".~ii!j'de.,l;.'8',~~ September~~
~~1975, and (2) thegSpi.fj:.;Techi:ical:-~~
'hdvjsor Who shall have a Sa'chelor,.s'=-dejLe'r=:o".-"-ejTit~jal ega.'in a scientific or etigineering discipline arith specific training in plar.t design and in the response and analvsis of the plant for transients and accidents.
6. 4 TRAIiiIHG 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of AflSI t/18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A.raining program for the Fire Brigade shall be maintained under the direction of the Fire Protection Administrator and shall meet or exceed the requirements of Section 27 of. the HFPA Code-1975, except, for Fire Brigade training sessions which sha'11 be held ac, least. quarterly; 6.5 "REYIEll kNO NlOIT. 6.5.1 FACILITY REYIEll GROUP FRG FU CT Oll ~ ~ ~ ~ '; ~'i~~< s ~'r v,
~~...'e~~
...~ s" -,, q s> a ~'>"," g 'i ~ t ~. 6.5.1.1 1'he Facility Review'Group shall function.to advise tfle Plant Hanager on all -matters related to nuclear safety.'OHPOSITIOH:,... 6;5 1.2 'he Facility; Reviei. 'Group. shall 'be'composed of the: I~ieger: .;- 'lant Hanager Hmher: Operations Super intendent f'hfii)er,'*;<<>>:~~~p~ .rc. g.Opel atlons Supervisor Herder: Haintenance Superintendent Hetther ~ ':Instrut."ant E Control Supervisor Hember: Reactor Supervisor Hember:. Health Physics Supervisor--. Hember. " '- Technical Supervisor, Hember:. Chemistry Supervisor-Nember: equality Control Supervisor Hember:. = . Assistant Plant Supt. Hechanical Nether: 'ssistant'lant Supt. Electrical The FRG Chairmn shall be 'designated in writing. -rg S) .. ST. LU IE'-'. UilIT.1..'"",'=,'-5'mndm 'nt ho', 29t37
AOHIHISTRATIVE COHTPOLS ALTFRHATES 6.5.1.3 All alternate members shall be appointed in writing by the FRG Chairman to serve on a temporary basis;
~~however, no more than two alternates shall participate ats voting members in FRG activities at.any one time.~~
~~tlEETIHG FRE UEHCY th t t i'h ~ <<h I. th I hlh 'I ~ ~ I t ~ " c' ~~~
~~', ~~~
h ..'r ~ I h. '\\ t ~ t,t t ~ J ~ t ~, ~I" t<<hIIWI ~ ,, Jr ~ ~ J <<J 6.5.1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman. I \\ ~ 'I .QUORUh t 6.5.1.5 A quorum of,the FRG shall.consist oi the'Chairman and four,'embers including,alterhates. .R SPQhSIBILITIES:.:;;.-,.'-:,,'.;;.: .6.5.1.6 The =~~~.'gj"~".v~3'i'ms,'GiX(7j!'hal 1 be responsible for:: . a. 'Revie!! of 1)'ll ',I".:icdguj~s:re'quired by,Specif ication 6.8"<='V,':."viaggthereto,',l2)any 'other'proposed 'procedu". es:6r. chances.: '.:,ther'~e'to as:;.determined.,b)'he, Pla'nt Manage",'. to a fect.,:.-.;,.'.:;'-;'.'-".;.
~~-'~t =--':b..~~
Revic!!~of'all;proposed,.~g'Ql and ~pi>t;:i~tdq<s7that':affect':-"-.: nucl eatr: safety ""'.".::;:,'. ". '=-c"."'" Retie! "at11"'p'r'6pos'ed changes to Appendix',A":.T~xca7P'- --""'='" '";:-; ci.'.'evie'>,.oi-'all:.prt'oposed,'changes or gad~$ c~tj~z>~" to: plant. '- =-.:,.-' '." '".:.:.'ystems 'or".equipment',-that:.'affect nuclear.'.;safety: ~ ", I ~, I ~ h ~ ~ I ~ . ~ - 'I t ~ ~, ST. LUCIE "'HIT:1 .'6-6 t I
ADi'1IHISTRATIVE CONTROLS ":nVCR"-'rgag] o'i> of al 1 r(iioIKtÃnsr"of the:.~ ech'nial";,'-5 f)"<fficYtQan> including the preparation and forwarding of'eports covering evaluation and recommendations to prevent recurrence to the hanager of Power Resources
~~Nuclear, the Vice President of Power Resources and to th Chairiman of the Company Nuclear Review Board.~~
~~'evie~of those PRPORTASL'E=OtiCUKREf/CKS'equires 24 hour notifica-tion to the.Comnission. ~" as"af facility o'pgragjcns'i to detect potential safety hazards.~~
~~h. ',Performance of FPec~,=~(:--..@Pie""4 and'nvestigations and reports th reon as requested by the Chairman of the. Company Nuclear ':~~
Review Board.. Revi ew of the i~.a>~"=-accUY~Zy""-~~1~r~nd implimenting 'rocedures'; and.shallt submit recommiended changes to the Chairman of the Com'pany,",Nuclear.Review Board. h ~r ., r~~ j. Review of.the Frri~gj eriij'-'-Ran ~~~Qmpl em nting"eve;<oS.eh 'and , -..-. shall..:,submit reccot".". nded. changes to the Cnairt-an o'r 'th' ":.':--'-'=':.'" "'Co':-pa nj:.thcl ear'='Revi ew:.. Board" " ': "-':.'.: ""-""""~""""'"='-"-" ='. Review o, every unplanned onsite release of radioactive material tc the environs including the prepara iicn of reports coverinG evaluation recommendations and disposition of the corrective action o prevent, recurrence and the forwarding oi these reports'to the Vice President. Nuclear Energy and to the Company Nuclear Review Board. Review Oi changes to the PROCESS CONTROL PROGRAM and the GFFSITE DOSE CALCULATIGH V~NUAL and RAD'n'nS i E 7.".EAT'H"HT SYSTEM,'iS. ( qgr r tYpg4 \\pl 'fta re r 4 pf 'L rrr riel rl tf z a ~, ~ r 'AUTHORIT",.'i';.!c': ~, r 6 5 1, 7.T.h't,F.aci'liey::Reerview,'Group.sha11:, '.::.;"-,'"a. 'ecohiniend-.':to::-.the.'Plant Manage>..written approv'al oi.-disapproval.--".-"." of jteos'considered under.'6:5;1.6(a) through:(d) -'above,,
~~- ~~~
~ t ~ ~ a t b. Pender determinations in wri ing with regard to whether.qr not each item considered under 6.5.1.6'(a) throifgh;(e),;above".-~- ":'onstitutes an.unrevie~~'ed.safety question.: '.. ...;i: r c.'rovide in.itten notification ~iithin 24.hours .to -'the Vice,'... ,President.of;Power'esources. and-the Company Hucteav:..Review. Board.' .:,of disagreement, betpIeen the FRG and the Plant Hanager; . however'," the Plant Manager shall'aveiresponsibility for resolution of,': such disagreements pursuant to 6.l.l above. t
~ ~ fcDI1IHISTBATIVE COfs TROLS ~ RECORDS 6.5.1.8 The Facility Review Group shall. maintain written minutes of each meeting and copies shall be provided to the Vice President of Power Resources and Chairman of the Company Nuclear Review Board.' ~ h h ~ I r I ~ t'hh ~ .tth', ~ ~ ~ h E 'I h ~ 1 1 ~ '1 Ih E t h h A .h ~ ~ 'I* ST. LUCIE ': UflIT.1. h j ~ ~, 'h h '1 ~ ' ~ ~ ~ 1 r 6 8 1 ~ ~ h 6.,tJ.E COI<PANY IRICLEAR REYIEM BOARD LCCMRB FUHCTTON h 6.5.2.1 The; Company Nuclear Review Board-shall function'o provide independent"rev.iew and audit of designated activities"in.the,'areas. of:, h 'a.', 'uclear power plant. operations h t* I'.'ucl eahr, engineering ~t c.'.;chemistry and'adiochemistry t h I d; '. met~ll~Jrgy e.'.-instrumentation and'control'" '"""." ":"-'""'. '-;-':
~~f..~~
~~"t radio'fogical safety~~
~~r ~.::.~~
~ g =Necllanicdl and electi ical 'engineering,,".".";.',",..",.:.,'-;.;, '.'" '-h'.. ': q'vali'ty assurance practices -."'..."';"',"."."".~;:":':;>'.",l -,i-",::':!!'.."."';.',"-', 'h ~ t% ~ ~ t ~ ~, ~
ir Cr (r (,r-AOHIHISTRATI VE COHTROLS COt (POS IT10H ~ ~ 6.5.2.2 The CHRB shall be composed of the: Member: tlember: member: Viember: li(ember: Hember: Member: Vice President Huclear and General Engineerin Chief Engineer Power Plants Vice President of Power Resources Power Plant Engineering Supervisor lhanager of Power Resou,ces - Huclear Manager of gA Power Plant Engineering Supervisor P~. f .i l The CHPB Chairman shall be designated in writing. ALTEPHATES 6.5.2.3 All alternate me(,bers shall be appointed in writing by the Ctf -Chah~oan to serve on a temporary basis;
~~however, no more than tvro alte nates-shall participate as voting m mbers in CftRB activities at any on~~
. COHSULTAHTS., -" 6.5.2.4 Consul.tants shall be utilized as determined by the CHRB Chairman to provide expert advico to the CHRB. r/ V. NEET IHG FREguEt~(c i'-'.5.2.5 - The CHRB 'shall raeet: at least once per calendar quarter'- 'uring the initial year of facility operation following'uel loading at least. once per six months thereafter. r'-~lf)>>P rr. Qv v,") QUORUM 7 6.5.?.6 A quorum of CHRB sha',l consist of the Chairman or his design alternate and four members including alternates Ho more than a mino of the. quorum shall have line responsibility for, operation of the fac )) ~r U ~ ST. LuC1E - uHrT l 6-9 Amendment Ho.
AOi / INISTRATIVE CONTROLS RETIE'I'l JJ 5 ~,'5' ~ J 6.5.2. 7 The CNR8 shall review: a. The,'QYotg".evalYi~~icgp 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.'roposed l.'!)angeS; to procedures, equi.pment or systems whgc7i~ ~ ~ ~ 'tfi."63K'iY"~n~un ej,ieVew~iHSy.'.que~tigg':,as defined in Section 0.59, 10 CFR. . c.J,:Proposed ".i.";":."L":Sp"c'5'.s. aPicin~s:.ar.l"~',"P~. e.. @jOJ~.,';FE5of applicabTe'.statutes,.'codes ",egulations,.'rders,. = ,Technical Specifications, -license requirements, 'or of.interiial., '-:.= procedures or instructions'.!;-.z'nj-Qgc.";@<~.'MCFcg;-,.sjgn&3'c=rjceq';='"'.:Si gni ficJant c;n~fgg3~9'g3oY>ii~Y6'.~~gQor 'dey> ations froi 'r.oima1: ~ and expected performance, cf, plant: equipment..~~~-..Q'~'nuclear,. w ~+ Aa~r r J Joey,'q, 44.l Q.,l. '( 0 i J g. 'Zf.'G.",~<:N F3)KUPB".lKKMwoh~ng~Ãi'4>os'n'ossification to.'the " *:.Jh;:, -;. Any indicati on'- Gf aii ='up~.<gjVf~YCeo '8~;Kiency~ in some .aspect.'*.of design or operation. of safety 'related.structures, .systems, .:or components. ~': '.-'.'::"-~ 1 ~ '.:;i .. 'eports 'and meetings~F~@sYRf the ~or.",iiXy;JR'!s~'-gitonp; y II 'I ~ ' ~ ,J I J '..i ~ ~,, 1 J ~ V ',J, ~ 1 'J C J ~ - \\ ~ ~ I p 1 ~ I ~ ~ ~ J 0 ~ ST. LUCIE'-'NIl"1.. .. C-10 ~ ~
AUDITS 6.5.2.8 Audits of facility activities st> ll be performed under the cognizance oi the CURB. These audits shall encompass: a. The conformance of facility operation to all provisions contained 'within the Technical Specifications and applicabl license conditions at least once per 12 months. b. The performance, training and qualifications of the entire facility staff at least once per '.12 months. c. The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method'f op ration that affect. nuclear safety at least once per.6. months. d. The per.ormance of all activiti'es. required by the quality Assurance Program to.meet'the criteria of Appendix "B", 10 CFR 50, at least once per 24 months. e The Facility Emergency Plan and implementing. procedures at ':<:..:least once per..:24 months;;::,,":-;..-,:.,: f; The Facility Security Plan and implenenting procedures at'e~st once per 24 months. g.'. ,Any other area. of facility operation e~ e:by'...'-..: the CHRB or;<the;Ex'ecuti ~.:~M.esident. h;. The Facility Fire Pr'otection,'Program'nd imp)'emeniing pro'cedures" at least once.per
~~24. months.~~
An. independent. fire protection an< loss prevention program inspection ~nd'".'au'dH sha Tl"'be"per formed at least" once-per:12 " months utilizing either. qualified offsite,licensee<personnel or an outside fire protection firm..
~~i. 'An ir;spection and..audit-of. the fire protection and loss prevention'rogran shall be".performed by. a qualified outside fire consultant a,t least once per..',.36 months.~~
1, The radiological environmental monitoring program and the results therecf a. least once per 12 months. ~. The 0;"FS:TE DOSE CALCULATIOh HAt<UAL and im<plementing procedures at lees-once per 24 months: ~ The PROCESS CONTROL PROGRAM and implementing procedures for solidi i<c=tion of radioactive wastes at least, once per 24 months. The performance of activities required by the equality Control Prograr: 'o meet the criteria of Regulatory Guide 1.21, Revision 1 June 1974 ard Rec latory Guide 4. 1, Revision 1, April 1975, at least once per '2 months. /< AUTHORITY 6.5.2.9 The ChRB shall report to.and*'advise 'the Executive Vice President on those areas of. responsibility specified in Sections 6.5.2.7'nd 6.5.2.8.
I' elj. ~ << 'I' ~ a I, 'I S a, ~ ~ l ADtlIHISTRATIVE CONTROLS. RECORDS 6.5.2.10 Records of CHRS activities shall be prepared; approved and 'istributed as indicated below: Sa << -a l'I I 'I l
~
.J' ~ l a. Hinutes of each CNRB meeting shall. be prepared, approved and 'orwarded to the Executive Vice President within 14 days following each meeting. b. Reports of reviewers encompassed by Section 6.5.2.7.above, shall be prepared, approved and forwarded 'to the Executive Vice President.<rithin,14 days following completion 'of"the"review. ... I ~ ~ a c. Audit reports encompassed by. Section 6.5.2.8'above,'shall 'be forwarded.to"the'xecutive Vice President and. to.the 'manage-:," ment, positions'e'sponsible for:.the'areas 'audited vrithin;30;"":: ; 'ays after completion.,of 'the. audit., I . 6.6: eEPORTASL.","OcruPREl'C~', i;CTiO1>.';,r '.-' " e ~ ',,C ~
~6

-6;<1 <" I ne';.fol 1 oirinq
<'ctions.'saba 1 1;".,be'."tat;er,' o~'-:RF<'E~r~i>Qr'Kj3"CYi~R"-':C<~.c,:::,',:,'.,": ..; ~:'. ~ '.The Costi..'ssionps'ha'<'l:. be".-'no"'ffi'cd~and/or:a report submi tted ".;: puzsuarit.to,the requirement:s oi Specification. 6;9:: ', -::I
~~'.'b. s, E~cii~Ãr5PABt~TQCCURREi<CE =-requiring='i4..rio~7V&otiA'c~t i:on::,=to...',. ',:.:..~~
~~~;-",.:;-;:.,'.;.=:";.::.'he,Corri ss~ on qV:"=l.'f,=. bZ.,> O'Qiv!<( 't."~"the 'F!,'e. and~~
."-.~To:.,'.. Ljr~=to,-.'::,':.'.:;,, '.:;.-'-':; =" the'""'.f/Pp'. ab J~i:he'-'.3~- e i~;-gi".es5dei~"-,." ';Po.;~r, Ps soiir2i ~-l ~ a ~ a ~ a a ~ C,' ~ l: I S \\ I ~ ~Spr<<S'r~'<< r a I ~ -; ~ ~ 'a' ~ ~ , '+aCft~4 ~+-r's'rC>> A'~)~gl~r~'""'Cr<<C<<>la '<< ~ t'YS(SCI<<SC C ~ ~ a I r I K~~g'aa caj'- p~w~<<'s< ~Sr. rsclf&IAs. s+., <<a I I ~ ~ l' ~ f I a I ~, .'.\\ I I ~ ~ ~ I ', I ~ ~ ~ aj 'j "~ S Ia sT 'Lucre:- uHIT;.i":.;. "..., '6-12 'I. ~
AAYltlISTRATIVE COliTROLS i 6.7 .SAFE-;V;L.rVrT.-.vrOLeATroH~~ 6.7.1 The following actions shall be taken in the event a ~<if'cd,",L'<erat:.p~ is. KU.93sated-"6 a. ~ The facility shall be placed in at least KDT-".<TAHDB'Pwithin:'oJi'eL~ Qy.q b. The Safety L'imit violation shall be(-,,'jpo'i'0'e4 to the g6jiriij'SSLoii'he Pic'e";iPgesQgQ os~,.o>;or.."Perforce~ and.to the g>RQ within M4,"-:floU +55.. c.. A Safety-Limit Violation P,:go,'i shall bey".,'paj";~, The report 'hall be +i~.'."e~:,",t.'~Up.tht-ERG:,This repo)'t shall describe (1) '. /<pj's";i'C>'M'e'.-",.ci< ciw~t:=nces-preceding the.. violation, {2)g~'4j'e 4R, of" t lite viola':i'oan "up'on- 'i a'ci1 ity components, systems or strucYi!res". . and (3)",,"i".'i',get".y~~c&og taken to prevent, recurrence. The. Sa fety:Limit Violation.".cpu;&shall be ~j~;;~~=c."..:to..the: Cornission,: the CURB and the. Director of. Power Resources '." ";.'i: -';.'-withir;10,days',of.'the;..violation;.~-;..',',.>:.;.-".;".".",,-;;:,:,.:t'.e. =."..'I'-.':;,".-i."',".:i:.~;::.~' v
~~r a~~
6.8 PROCEDURES . 6.8:1'. k'rtitten.procedur es shall, be established;= imjlemen"ed-and main-.': ':tai,",ed,'covering",the. act$ ~tities.';refe",enced bel ow:;:.".,';:;:,:-.;...':"-:"."".'-'-.::;. t".:.'.;"," .. "",a "...'-The appl icabl e"procedures'r ea'commended'-:in'ppendix'A" oi . -~", '.; ,:.'...'.:. " Regulatory'uide 1.33",; Hovyepber; 1972'. r ....,b'-., Pe fuel ing. operati ons. . '.-.,'.'"c.'," Su: veilla'nce'arnd testyactivities..of safety",relat
~~d. equiP~ent..:.~~
v .'d.; Security; Plan.'impl ementation.- v '::=e.'-'.Emergency Plan, implementation.' Fire Protection Program impl ementation...".",'..:.- g. PROCESS COHTROL PROGRAM implementation j h. OFFSITE DOSE CALCULATIOH HAl<UAL implementation. i. equality Control Program. for effluent and
~~-~-...i~~
~. monitoring, using 'he gui dance in Regulatory Gui de l. 21, Re. isi on ~ June 1974. 1 Gi~~Gtbd GoW+ Piycyo ~ o vrouw ~,~Q~~~~ ~~j ~ 6.8.2 Each procedure o 6.8.i~above, and changes tnere-o, s;iat I Pe reviewed by the iRG and.pproved by the pi'anne lanager prior to in pie. en-at>on ano reviewed periodically as set forth in administrative procedures.
ADY!INISTRATIYE CONTROLS 6.8.3 fempoYKi'p'-"8jprlges) to procedures of 6.8.1 above may be made provided: a ~ The u7UefR of the originai procedure is not altered. The change is app7oved'by Po",.".lnembers of the plant management staff, at least one of whom ho'jds a Senior Reactor Operator's License on the unit affected. c.. The change is do7gÃi>ited, reviewed by the ~."J.',6 and approve4 by .the Plant tlanager within 1'4-":o~!3+ of implementation. 6.9 REPORTING RE UIR"=ViENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 'I 6.9.1 In, addition to the applic~tion reporting i equirements of'itle 10, ,Code of Federal Regulattons, the, folloiiing reports shall be submitted to the Director of the'egional Office of Inspection an'd Enforcement unless othe njise,,noted ;,...i,,,:.;:; ...i.'..,:.:... ~ ~ ~ STARTUP REPORT rr ~r !1 C ~ \\ \\>>fr' I ~ ~ '23 6.9,1.1 h'ugary report of plant startup and power escalation testing shall be subm>tted.following (1} receipt of'n operating license, {2) amendment,'to-the license.:involying: a platined increase.:,in po~:er'.-..1eyel,
~~(3) 'installation 'of'fuel that has a diffhrent.desijcn or has been manu.-,'actured:by.a.differerit fuel supplier, 'and (4) modifications that 'may~~
'ave sigr~ific~nt1y altered the nuclea>," thental, or hydraulic perfor-,; mance of 'the:plant. ~4 . 6.9,1.2 The.startup report shall address each of the tests identified in.the FSAR'.and:shall::;include a description of'he measured values'of'he operating conditions'or charactertstics obtained-'during the.::test prog. am and a comparison':of these values.with..d sign'redictions and specifications.:."Any corrective actions that.i<ere required to obtain sati factory operation. shall also be described. Any additional-specific details-reouired.;in license conditions based on other com>>mjtments shall be included in this.report. I '6.9..1.3 Startup" reports:,shall be.submitted within. {1).BO daIs following completion of, the startrup.test program,';(2)'0 days following 'resumption or corrniencement of commercial poi,er operation, or (3) 9 months following initial criticality, whichever is earliest. If the Stariup.Report does not.cover:all'three events (ie., initial criticality, completion of startup test program,'nd resumption or commencement of'corn rcial' \\ ~ I ST. LUCIE -. UNIT 1 6-14 Ato n(bryant No, f7,
~ I ~ .9!)IHISTRATI YE COi)TROLS power operation), supplementary reports shall be submitted at least every three months unti I all three events have been ccmpleted. ANNUAL REPORT~ 6.9.1.4 Annual reports covertng the activities of the unit as described below for the previous calendar polar squall be submitted prior to Harch 1 of each year. The initial report shall Be submitted prio" to March 1 of the year following initial criticality. 6.9.1.5 Reports required on an annual basN shall include: s'. A tabul "tion on an annual Basis of the number of.station, utility and other personnel (includ'ing contractors) receiving , expose'res greeter then I00 mrem/yr end their es"ogl~ et&I.mee re@i exposure according to worP. and joB functions, e.g., reacto~ operattons and su,veillance, $ nservice inspection, routine maintenance, special maintenance (descriBe maintenance), ctaste processtag, and refuelin'g. The dose, assignment to Yal ious duty functions may B'e estimates Based on pocket
~~...,.,:.,,",.j,;-dosimeter, 1 LD,.or film Badge require,"ents.,~~
Sma11 expo.",upes.. totalling less titian 20/'f:.the" individual total dose"need ilot.----'=-'e accointed for. In the aggregate, at least 80~ of the total >,hole bodv dose received free extern"1 sources sFiall b assigited to specific major Mort functions. "":i b.'.."The cm>piete results-of-.stem'generator.tube.-.inser~rice inspec-.. 'ions performed duri'ng.tBe report'eriod (reference Spectfica- =
~~-. t(on 4.4.5;G.B).~~
t v4 e 'l s:; A single submittal may Ge made foi 'a m'ultiple unit "'tation.':.-Th~ subiriittal should cmbine those sections that are creation ',to all'nits"at the station. I <<1 m g2 -This tabulatiori supplements the .:;;'.rem nts of 520.407 of '10 CFR '. 'Part 20;.
~~. $c ii.~~
~ 'e ~, ,s ST. LUCIE"- UHET l 6-1 5 s Amendm nt t'lo. 23
ADHIHISTPATIVE COHTROLS t<OHTHLY OPERATIHG REPORT 6.9.1.6 Routine reports of operating statistics and shutdo>vn epelience shall be submitted on a monthly basis to the Director, Office of lznage-ment and Program Analysis, U.S. Nucleal'egulatory Corrnission, Washington, D.C. 20555, with a copy to the Regional Office, no later than the 15th of each month folios(ing the calendar month covered by the report. PEPOPTMLE OCCURREHCES J = ~ p c, '<, ~ ~ ~ 6.9.1.7 The REPORTABLE OCCURREHCE of Specifications 6.9.1.8 and 6.9.1.9 belo;l, including corrective actions and measures to prevent recu! rence, shall be'.reported'o the HPC.": Supplemental reports. may be required to fully describe final resolution."of occurrence. IA case of corrected o-supplemental repo", ts, a licen'see event report:shall be completed
~~and, reference shall be made to tI!'e original report date.~~
PROI'iPT HOTIFICATIOH WITH WRITTEH:FOLI OHUP';9:1;8":I'tie "tp~jes.'of>:-;-.Jei>~.,s:!;; c Fec'.,b~l'o~, shall "b 'rcportedQ-'"i,"c'h'~".i.-,i~<'!', '"'"" "'ours by, telePhonec"'nd:congjif~!cd;.'by~,'iece."'1"!PlT -;";.>Jilgr<<rr, or facsimile tiansmission to th 'Oiiecior of i."he lleciionai",Ci'fic~",, oi:.h!s desig<!ate AO 1 ater . thaA tl!"'"'...AC'!!<rt'1nj+';.C!cQ~ '!'Oj!<J>'."i1tg.':!'~Gven<t% With <c< 'le": < ten-'< -'<<oi.,"!'qgup -$",ej5Fi="!".'!..lio.."3><'deja. The !vritten fo'Ilo!;up report sna tl="=.". include, as.a mirim~rl!,",a ccmple.ed copy;of:a-;.!licensee-event report.:for~<'.. Information.provided,on-the-1'ccensee'.-event <report fom.'shal 1 be'uppl e-;- mented,.as"needed; .by 'additio";ial narrative material to provide'comple';e'= explanation of ~he'ircumstances"su'rroundQ!g the event. <<~<<auo~p m ~es~Cn 4' M<<, a. QY'~4'...'Yl<~~Y:Of:"the,:'.~$hCVOr',.-".pr' c'.er,;,...O(! =. ip'S!,>i!";Oi'.;.','.Other"iVSfemS:-i."- Q'~st,'b c'>" .."j;0:.3 'lli1't G lng.,sc Tetg sc',.i<'~iP, se"t'! llgs:iv -llilc: Ic!(e-'c he .:.= c~;".'rQ()4<"VC pi:0'eCth>Q',fU!)~$ "j.01')'~ HC t i&i.-'",. 7l!OAl'tQrPQ 'pa!ct.'~ '= '.:,'-" "- c'.:..:t"='-" ~"=ct.".',";Ii. '~e 1'r~>"c".".,p<l;".':.:!ed:a:. th ',':smiting.,sa.!=@~i.-'. t. <'<c sQtt ij(> ! i'"ihe i".. c!'<;'..!c~c!. 'p=< g.ic atiors or.c Qilui&'-.-"'-.
=,

V4,." r 0m~ii f'j;".0>"',.<-.'~ouija.'1;

.o.'c:"i Alc;,'iVlnct.os;.~A b.
/Oping p"'"gq,,0 f:"inc~"':K!IA'w".or."a c:"-c-:ate J"-e~< "::rr's'";>",hen'",inX:pc.l'a!;~/pe>~ t'0J'"'<<pP)*w'CBon sub5ect" Yo a '"< '<m'!t'.Ag<'condition'or,'operatfor<'." .'i<"";".s" con'e"'amative than th=" 'iea'si,"'c'o:iserjab'B>e'as'p=cc.."'os .'%I!g"":",~:,'ting OI>di )OS "iO1" opere"tih)'".1;.=biihied..=i& 'e ~ ' 'e+II)'! )<<"" ".sggC"<."jga~3QJ)~c~'. %@no".:."ii-deg"",.(d<ht'ib>i y'Roc. or d.'in"fuel. cl(dding','VhFc40j. U~cl01 an <.-Qgg(SUQQg.4QQQda! y~ "t""p!'iL<-I'g-cofltcYAm~nt') ST. LUCIE - UHIT 1 '-16 lnendment"Ho. 23
AL)f)IHlST1?ATlVE COiA'ROLS
~~d. ~ii,.ac/'jj'i'tj.'.anginal',es. <nvolving d)sagree.-.."nt! 1th the predicted value oY reactivity balance under steady state conditions during po. er operati'on gn.ater than or equal to l~ bk/k; a~~
calculated reactivity balance indicating a SHUTDOHH.lNRGIH less conservative than specified in the technical specifica-. tions; short-'term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned react'ivity insertion of n!ore than 0.5X r k/k; or occurrence of any unplanned criticality. e....-~ - Fv.'(,Ilare""0'">>Vl771iu'net> on;,of.":one"'.Or-more =crine'o(!ents'Qf c~reVents, '"-'(o! 'could prevent, by ttsel,, the~vjg;~3,lieIit of the functional rr('qQiren!!ts of,=.,s<mt~(s) used to cope with accidents analyzed s n ~1fe=SAR'. r f. p,~-".."( ~dan"'1":.'i'"i'pr~";.Oi -,jfrpcedural'-,inhde-uac '1.;which prevents or 'coula p-event, bytisel'f, the;,',"ul;=,.iUirenY<of the functional <,,.'.&c'aqj~arKA'i~~: f system requiVed'"Ra'""'cope"i'8 th acci dents analyzed.': ">r( tl!e SAfC.' ~ ~ g.'~t O'A(ff-gg(is",Rr~siYng;:!,(;cjii':(!atUrcil.'+'~i!3f'<-a"iQe(',~((+AM",((1!IA(,>."'((9?p~(". . ("'GR)1.(',.'9f ii!',(:. Qve'lj7'e'5'! }"" "P."."t (:.~(6'VIo('",,'!,.00e( c. i.:~Op.';.','.; 4 i~..sh".i:;.'.,sZ~ te (,s,.".o! other ipI o'.-"~:i;4~e v;;=i",sg~(.rs"'".foui'red".b~i,'< ~t~chnica Y--.speci fic$t)ons=," ~)'J>>" ': aA yi' g~ 'dN > I' h..'- (,"('.~i".'~'(.'lbQQ:~Q>.Gc'-'".',l'jrc: i~Pc" As!en 0's '.,Pcc:(c! .'-(~a.::"(rI"Q'~Qp;:,Or.. 1ll ,,the.,>f~Vt:o7i'sed for sucfi'nalyses, as d..sciYbea in.i:Iie sai'ety," ':=.-'-:-":.':.;,ana'hays (s..",re(d'or t or:,N the', Bases-for (he teci(ni ca 1: spec< f(ca'-'.:;:.', 'tions",i 1ia'(.'have or 'coul d nave permitted' eactorI operation',",iI>',":".-'-.", a manner,';less conservattve th=. n assu',":ed in the analyses.".;.':;="" I 1 <. ~..PeVR'.".$ (.'"*."Y(i""ft!'"uc"urea-.;-ss s>F<".;. or;r;o,i: FriFnt"~'~ho~-.r.'huh'.es:-.',-', <~ r(.;>..r'ipi,"';; > ess.:cense vati,e.. <i!an ass(.':. d 't.'!: tfiY-(((.c1('I."..'TC- ~GAQ.",'!~9~;-'Jg;.~'b" (..a<('ty-"'"(1 IY,'(~'p,;-'.Qv", (~i ".'Rch"'tc( J;."p~c~ffci-Vi'iiigl,-~ babes:..,.Or;-discovery du!'! ra !.r(it li(.ie 'of cond>Uons'not sp cl ('fc'al'fy conswered tn tBe'sa.('ety analysts redo!;t'or ~ tech(ntc(al spec>i'tcations that <'eou$ re.ra-;edidl action 0! col. recttve (measures to prevent the mtstence or development of 'an unsafe condit.ion. j. Offsite releases of I adioac(ive na erials in liquid ana gaseous effluents that exceed the li.(its of Specification
3. 11. 1. 1 or

3. 11.2. l.
7 k. Exceeding the 1 iniits in Specification 3.11.2.o for the storage of radioactive materials in the listed tanks. The written follow-up report shell include a schedule and a description o( activities planned and/cr -'aken to reduce the contents to wi bin the spec',fied limits. !TH.!RT~'":OA~ I? l7TF.N. REPORYS;-,-. 6.9.1.9" lhe.typ s of events listed below shall be the sub)ect of >vritten reports to the Director of the Regional Office'nithin thirty days of
occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the <icensee event report form shall be s!<pjlcz<eni.ed, as needed, by additional na! ) ative material to provide complete exp1anation of tl!e circumstances surr ounding the event. a.
~~.pReactor;",protection.rsystcm-o."eo'oineered's~i:et<'.feat-'re"-'.-instru-~~
"'meiiY's'ett'ig's" i<h'i'chr~"foi!nd,to'be':"1 es's".'con'servatiI<e.:than::. "tho's'e 'est~-bl;is)>ed bj. the..techi! ical:.'.spec <f ications:.b"t:.!!i.iich:."-'d6:.riot'"pr p'e'n .'...tlfe "fulx.Q!i<.ij}t'of';theZu'r!c't':ional,'3"e71!Ljpem nts":- (gf.-: if<fected-'systems. 4~ I ( t<<9 (p J ~ d ~ tl"t>>9>p + i~<<<<<<<<< $ l~g Pt<<W<+...V, <,r W I,<<<~ <<W b. 4":C03(H C.'!Ons"-,,!eGclng'to 01 er3i.'r 0'!. 'Jn'-. a; 88graQQct=R0Q-:;p< rr"<lT< GQ. <bj<"a:.'L~niiiinq",cond iiicn'foi'=;ipei a'0'ion 0, p < 8'nf".sf)Mtdo'AFl-fQ-qadi i;e,.":bj'."lcm <.zing.'-~oridi..'..ion';for.'ia p rai;ioo,'. r'Ob""e'ed iriadequaCFFs~n.'th "..:.iri"pTemc~g7oY;;0<; aViP>ji".,sgr<ag'Iv'e', '}:".p<.or',"<."I!i'rM"coni;rols-;<which threaten "to'cause",!.ed!let ion'.,0".'-@ degree';of.'.redundancv. prov'.c!e('.:1!}'.,reactor..:p).otectzon:isystems-""<>','".of',<engrneared:s'ifety'gaea't'!I<.'c':."'j'st'eris.";" d ~ ~;,Ab}<Q)".<Tzi1'-0 egra<d<4 ci Qf>~s~j'.~'~r.':.;s,oihei, ~'I}an:,"i%osc 's$ be i <;< ed'<< -,in'6 g",'1;8;c;above-d signed-lo<<conta'1:.)7oioacaie,"L'="tej".i'al . i'Gsu '.: i!)r},~<re' l'i='-.'3 "Mo"i.,o'aces's'~ e. An unplanned o<fsite release of'1) more than 1 curie of radioa"tive material in liquid effluents,
~~2) more than l50 curies of noble gas in gaseous effluen s, or 3) more than 0.05 curie 0- radioiodine in gaseous effluents.~~
The report of an unplanned ofisite release of radioactive material shall include the following information: 2. A description o< the event and equipment involved. Cause(s) for t<<e unplanned release. Actions taken to prevent recurrence. Consequences of the unplanned,elease. ~ I'
h k k
ADY.;.'(:STRA.IVE CONTROLS PP,flflF 8 RD'10~> CBPY SEMIA!'t'UAL RADIOACTIVE EFFLUENT(T R:-'ASE REPO"T>> 6.9. i.iO Routine Radioactive Eff'.ueni-Release Reports covering the operation of'he unit during the previous 6 months of operation shall be submitted wi hin 60 days after January i ard July l of each year. 'The period of the first report shall begin with the date of initial criticality. The Radioactive Effluent Release Reports shall'nclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Recu)atory Gu'.de 3..21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Rastes and Releases of Radioactive Materials in Liquid and Gaseous E >> luents form Light-4'a.er-Cooled Nuclear Power Plants," Revis'.on i, June 19/4, with data su."..marized on a quarterly basis following the format o Appendix B therec,. The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour list.nc on magne'tic tape of wind speed, wind direction, atmospheric stabili y, and precipitation (if measured), or in the >orm o> joint fr quency distributions of wind speed, wind direction, and atmos-phari c stabi 1 iiy."~ in i s same re"or i silal 1 include an assessment of the radia ion doses d'e to he radioac=ive liquid and gaseous effluents released frcm th'e unit or station capri ng the previous calendar year. This same r'eport shall also include ar. assessment c> the radiation doses from radioactive 1:quid ard gaseous effl ents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BGUt>DARY (Figure
~~5. -i) during the report period.~~
All assump-tions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological condi-tions.concurrent with the t'me o> release of rad'.oactive materials in gaseous ef 1 cents, ps determined by sampl ir<g frecuency and measurement, shall be used >or cetermining the gaseous pathway Cases. The assessment of radia ion doses si>21 t performed in accordance wi=h the methodol ogy and para>ieters iil t lc OFFS T: DOSE CALCULATIO>h MAHJAL (ODCM). -"very 2 years using the previous 6 meet>is release history for isotopes and ili5 ori ca 1 meteor ol ci ca 1 data dete rmi r e the control 1 ing age group for bot h liquid and Gaseous pathways. If chancec fl OQ cu lent submit change to ODCM to refl>ec new tables for these groups and use the new groups in subsequent dose ca: cul> aii ons. The Radioac ive Fffluent Release Re. orL to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THF PUBLIC > rcm reactor rel eases > cr the previous A sincle subr>.ittal may be made >cr a multiple unit station. The submittal should combine those sectiions that are common 'o all units a the station; however, for units wi h separate radwaste
~~systems, the submittal shall sp cify the releases of radioactive material from>~~
~~each unit. X >>C In lieu of submission with the =i~~
~~Repcrt, the licensee has he opti meteorological data on site in a~~
request. rs. half year Radioactive Effluent Release cn of retaining this summary of required file that shall be provided to the NRC upon S'. LUC -" - UNIT ~ L
AOHIH1 'TRATIVE CONTROLS .calendar year. Acceptable methods for calculating the dose con ribution from uid and gaseous effluents are given in Regulatory Guide
~~1. 109, Harch 1976.~~
i.he Rad:oactive Effluent'elease Reports shall include the following information for each class of solid waste (~~~~~~~~~~r~1-) shipped offsite during the report period: a. Vol ume, b. Total curie quantity (specify whether determined by measurement o" estimate), c. Principal radionuclides (specify wheth r determined by measurement or estimate), d. Type of waste (e. g., dewatered spent resin, compacted dry waste evaporator bottoms) e. Type of container (e.g., > SA, Type A, Type 9, Large Quantity), and f. Solidification agent or absorbent (e. g.,
~~cement, urea formaldehyde),~~
The Radioactive Effluen+ Release Reports shall include a list and descr ption of unplanned releases from the site to UHRESTRICTE9 AREAS of radioactive materials in gaseo s and liquid effluents made during the reporting period. The Radioac ive Efficient Release Reports shall include any changes made during e reporting period to the PROCESS CONTROL PROGRAH (PCP) and to the OF.=SITE SE CALCULATION HAHAUL (ODCH), as well as a listing of new loca ions fcr dose alculations and/or environmental monitoring identified by the land use census pursuant to Specification
~~3. 12.2.~~
ANNUAL RAOIOLOGICAL EHVIROHHEHTAL OPERATING REPORT~ 5.9.1.11 Routine Radiological Environmental Operating Reports covering -.he operation of the uni during he previous calendar year shall be submit:ed prior to. Hay 1 of each year. The initial report shall be submitted pri:- to Hay 1 of the year following initial criticality. The Annual Radiological Environmental Operating Reports shall include s~~maries', interpretations, and information based on trend analysis of the results of the radiological environmental surveillance activities for the report perioc, including a comparison, as appropriate, with preoperational
~~studies, wi:-n operational controls and with previous environmental surveillance repor:s, and an assessment of the observed impacts of the plant operation on the env'.ronment.~~
~~The reports shall also include the results of land use censuses requirec by Specification~~
~~3. 12. 2.~~
The Annual Radiological Envir onmental Ope ating Reports shall include t,".e results of analysis of all radiological environmental samples and of al: environmental radiation measurements taken during the period pursuant tt.. the single submittal may be made for a multiple unit station. ST. LUC'" - UN>T 4 k
ADt.!It(ISTRATIVE COliTRGLS g locations specified in the Table and Figures in the ODCi!, as we'.1 as su;..mari-ed and tabulated results of.these analyses and measurements in.he format o, the table in the Radiological Assessment Branch Technical Pos'.tion, Revision 1, Hovember 1979. In the event that some individual results are ~ot availab(e for inclusion with the report, the report shall be submitted no-ing and eyplaini'ng the reasons Tol the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: radiological environmental monit'oring program; covering all sampling locations keyed to a tab tions from the cente: line of one "ea tor. he Compalison
~~Program, required by Speci fica-.ion deviations from the sampling schedule of Table analyses in which.he LLD required by Table 4.~~
~~a surmary descr'ation of the 'at least two le ble maps" le giving d-;s an-=.s and dir ec" resul:s the Inta;'aoor ator'i 3 ~ 12.: di scus s.'- of al 1~~
~~3. 12" (;~~
and disc ssi on of a 1 1 12-1 was not achievable. ('!-PO!iTF" 6.9.2 Special repo) ts shall be;subii!itted to'the Director of the Office of Inspection and Enforcer<<ent Peqional Office < ithin the tine. period'pecified for each report, These(reports sha'Il be sub:>>itted covering the activities identified below pursuant to the reouirements of the'. .applicable. reference specification; a. Q. !i4)e!'c o,c'..>c,l51jl~:.".l!4."';('.~<fl"."n'i:r~~li.cc(,'(oj'>..Specii ication 3 ~ 3 ~ 3@3 ~ ~ b. ~7,(aper~bi e.'.,4e@:(gk'(og,<(:.v"4-:.:",c~~i:oc.1ng. in~:ix~ag~~t.'gn;- ~ Specii'ication 3,3,3,<<., ~ c '~ p'o'ci f ! 'lj Q:gns I g~~f ( Q'>..Qgg~@'.~jp g Q!' ':$p ' r'c'l0ns 4 y 4 ~ 1 0 e 1 a7(a 4,.4..10.2.. d.. FECES, <',"'i:UB'cior;"-'Specifica~ions 3,5.2 and 3;5,3, e... ie'alp~ '~u,lac~'leaLc",g~-Q~j=-,<~'"i>"--.".q( =.)!p,j'(,", Spoc"< ("jcatjon '4 7 o '( f.::...~;(;r<<i".-;(<:e,"...'ana'(y=;-s, Specification 4;3.3,3,2. g. i=8"-c'.c( '-sL'('..:i6g"-l'cs!'j ~5+Spec>fice tion 4.7.6 1 ~ l
AQUI JJ ISTfNTIVE CONTROLS h. ~;;:iwi..~~".'Barre1;,Hovem n~', Specifications 3.4..11 and 4.4.11. i. .,irv-:Oetectioa'isKru'riro"niatfon, Specification 3.3.3.7. j.;Fi';e:-Suppres'sYon'Syste'ri-s, Speci ficati on 3.7.11.1. 'ZqclioJ"gicvi Fi4l~epq'peciKc~i'i~~ E,r).l.~ ~ 3,J J,ls3g 3r J Je2e2 > >rl J<2g~p 3>ll 6.10 RECORD RETEHTIOH 6.10.1 The following. records shall be retained for at least five years: a. Recoids and logs of facility operation covering time interval at ach power level. b. Records and logs of principal maintenance activities, insp ctions, repair and replacement of principal items of equipment related to nuclear safety. c. All REPORTABLE OCCURREHCES-submitted to the. Corn~ission. .,d.. Records of surveillance activities, inspections and calibrations, requ-ired.'by these Technical Specifications.'.. e. Records of reactor tests and experim nts. Records of changes made to Operating Procedures.. ~i .'.",g. Records,of-radioactive': hipments.'.- '.h; Records of sealed source leak tests arid results b. Records of new and irradiated fuel inventory,'- fuel transfers - and assembly burnup histories. .'c. Records of facility radiation and contamination surveys. d. ~ Records of radiation exposure for all individuals entering .radiation control areas. ST. LUCIE - VHIT 1 6-$9 2 f Amendment ho. .i'. Records of annual physical inventory of all sealed'source material .Of l;ecord. 6.10'.2"',The. following records shall be retained for the duration of the' Facil ity'perating License: a. " "Records".arid drawing change's reflecting.facility design inodifi- cations made to systems and equipment described'in the Final Safety'. Analysis Report.'
o Ml<IHISTRftTIYE CONTROLS. e.. m. Records of gaseous and liguid radioactive material released Co the environs. 1 Records of Cr'ansient or operational cycles for Chose facility components identified in Table 5.9-1. Records of training and qualification for current members of 'the lan", staff. Records of. in-sot vice inspections performed Pursuant to t<lese Teel)nical Specifications. Records of equality Assurance activities required by the gA Hanual. Records of reviews perrormed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. Records of. meetings o - the FRG and the CNR8. Records of Envirorh.ental gualification ))hich are covered under the 'rovisions of paragraph 6.13., Records of the service 'Iives of all hydraulic and mechanical snubbers listed on Tables 3.7-2a and 3.7-2b includirrg the date at which the service life co<fences and associated installation and maintenar<ce records. I n Ot.. Annual Radiological nvironmer)tal t~~<=:,.g Repor-s; af<t)0/5'c5 ~~')sm'1"t 'd w -t.l~iceclsop~ wlU.CsgggQ Use~,.ao ~ pI <spar.~ .KL)e Anrua'- Radio i ogica l ~nv) ronr))en".a-l-~4or) i Caz~.,",g..a por -. - o. Meteorolog'.cal dates summarized and reported in a:ormat consistent ~ ~ 'with 'the reccmmendations of Regulatory Guides 1.2l ar)d 1.23. 6.11 PSDIA7IO)~PROTECT" O)rq i-'ROGRrtr'...:...-.os.,:.:.,'..s-...,,;.s Procedrrr.es for personnel radiation protection shall be prepared consistent );ith the )acquire~)ents of 10 CFP. 20 and shall be approved, maintained and adhered to f'r all operations involving personnel radiation exposure. t ~ j s p C $ ~. y~ .. ~ z<~'.-.HIGi8'R'ADIQ <Y!r'..':iREAF;-;.:, 6.12. t" <".-.q. lieu o) '.Chc "control device" 0", "alarm signal" rer,";~qual'by pa) agrap)) '.a.+<A.-,.-high".:R~<!~ti4P4).ea', in which the int=h-.Py of.radiatior js('9), ~te).. '>q~;i)"ri':tt.:P,c "..c;:..~l)r: 6ut )Yes ~ thar 10'.)".y=:.".,i';- <$ii)"5))'ag bg."r~Z rz',<c-"."ded and )" '..>'<"Djqi~)m': ",j) 't.-r'. ", '"-'5':" "<<;"H. ':.". t)='Oi'='0'i'" '; ea'.,arid enCrance Q)ereto ))='h.=1-1 be'c;z)";w33e. ~.. 'uvnca."~'.g.-Pad<:;.tioiP'3'~+'Fcmipha).d any ':-'-'ir')divi'du~1 or'grorrr." ~-..."nclividua1s ocr )".i.:.9, to enter -sue}) areas P,"";-.~-<"b$';-".ji o:;~~ r,~:.')!" ~g) ~'..;.',e."..'i'o:l 'Y1iihÃv:i.;e'eiiJ7)'which coi)tin-, ooosly indi<,~tea the radiation.~os@ rate in le area. b. A i)i~,-"i'.ad)ation A ea in i<,'hich =))e Int~~=-.-i.ty of )'adiation H<g>'""'-.i'~~ ~~<;. s '~i0-)67ZiPIhr.-'sh'<cl =:ha-suib'':.w t)e'r,'."'i'i<::tr))sof 6.12.1.a )) ~,;,<above,;:; in additio,"T~c):~.!'~;;:: "-'~,:"; I.:; p;;;... 6 to prevent 3 ur))srthorized e'ntry ir)to such areas .".n>>"".-. <'.ey" -,<<:. ".."..<~":neii78 e VQO)C'l -; "'. ~ r <'-GTS< ).~<-g,hsCOJilirQ'. (ir.'sr<:~i).i'USDp:;.) S<) .,QA~d)$43' ~'i>
PP0 "i. 5 PRiPY 50PY AOt~iINI5(RATIVE CONTROLS 12 HIGH RADIATION AREA
6. 12. 1 In lieu of the "cont'i ol device" or "alarm s'ignal"'equired 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 conirolled by requiring issuance of a Raciation Mork Permit (RMP)".
Any individual or group of individuals permitied to ente" such areas shall be provided wiih or accompanied by one or more of ihe fol'.owing: a. A radiaiion moni i ring device which continuously indicates the radiation dose ra'e in the area. b. A radiation monitoring device which continuously integrates the. radiation dose rate in the area and alar...s when a preset integra'ted dose is received. "-n ry into such areas with this moni ioring device may be made after the dose rate level in tho area has been established and personnel have been:-,=- e knowledgeable oi ihem. A health physics oualified individual (i.e., qualified in radiation protec'iion procedures) with a rad-iat-ion dose rate monitoring device who is responsible for providing posi i',ve control over the activities within the area and shall performi periodic radiation survei llanc at 'he frequency specified by the faci1i.y Health Physicis i i>n the RMP. . 12.2 In addition to ihe.requirements c)f 6."'2. 1, areas accessIblie -o personnel with radiation levels such that a major po" -on of -'he body cou:"'e"eive.in one hour a dose greater ihan ~000 mrem shall be provided with locked Coo s io prevent unau horized en-:ry, and the keys shall be mainta-oned un"er -;,e adminis-t: a ive control of the Shiit Foreman on duiy an /o health phys'.cs s pervision, Doors shall remain locked except during periods of access by personnel under an approved RYP which snail specify the dose raie levels in the imme iate work area and the maximum allowable stay time for individuals in tt a-ar=a. For individual areas accessI'e to personnel wi ih radiaiion levels such -.hat a major poriion of the body could receive in one hour a dose in excess oi 1000 mrem~" that are locaied within large areas, such as PMR coniairmeni, where no enclosure exists for purposes of locking, and no enclosure cail be reason-ably constructed around ihe individual areas, hen thai area shall be roped off, conspicuously po ted and a flashing light shall be activated 25 a warning device. In lieu of the s ay time specification cf the RMP, dii ec. or ".emote (such as use of closed circuit TV cameras) continuous surveillance may be maCe by,personnel qualified in radiation protec ion procedures to provide positive exposure control. over the activities within the area. "Heal ih Physics personnel or personnel escorted by. Health Physics "ersonnel shall be exempt from the RMP issuance requirement during the pericr;,ance of their assigned radiation protection duiies, provided they are o herwise following plant radiation protection procedures fo~ entry into high adiation areas. "-t~ieasurement made at 18" rom source. of radioactivity. ST. LLiC;E UNIT 5 g
n$ ~ ADHIHISTfNTIVE COf/TROLS
~~6. 1 3 EHVIROtiNEHTAL UALI FI CATI OH~~
~ ~ 6.13.1 By no late: than 3une 30, 1982 all safety-related'lectrical equip-ment in the facility shall be'.qualified in accordance with the provisions of: Division of Operating Reactors "Guidelines for Evaluating Environmental gualification of Class IE Electrical Equipment in Operating Reactors" (DOR ~ Guidelines); or, HUREG-0588 "Interim Staff Position on Environmental gualification of Safety-Related Electrical Equipm nt", December 1979. Copies of these documents are attached to O.rder for,"iod'i.fication of License OPR-67 dated October 24, 1980. 6.13.2 By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the " environmental qualification method used for all safety-related electrical equipment in sufficient detail to docuriient the degree of compliance with the DOR Guidelines or f(UREG-0588. 'hereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further. qualii fied. e
6

14" SYSTEf fS'.".'.IH) EGRI7Y 2.
Integrated leak test requirements for each not to e-ceed refueling cycle intervals. r e IODIHE Vs0f". ITORIHG system at a frequency. s I 6 6.15 6.15.1 The licensee shall implement a program which will ensure the cap.bility to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following l. Training of personnel, 2. Procedures for renitoring, and e ~ 3. Provisions for maintenance of sampling and analysis equipment. 6.ldll.l The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids ~ ~ 4 e f e 4 during a serious transient or accident to as low. as practical levels. This p~ ogram shall include the following: Provisions establishing preventive maintenance and periodic visual inspection requiremen s, and is g ~ ~ V 'ST LUCIE - UHIT 1 6 Pd,~+ Order dated October2~ , 1980 Amendment Ho. 37
AOl4IHISTRATIVE COHTROLS 6.16 BACKUP llETHOD FOR DETERHIHIHG SUDCOOLIHG t%RGIt< 6,16.1 The licensee shall implement a program nhich v(ill ensure the capability to accurately mo'nitor the Reactor Coolant, System subcooling margin. This program shall include the folloning: 1. Training. of personnel, and 2. Procedures for monitoring. ~ ~ e ~ ~ l ~ !! ~ x ( ~ \\ IP lCi gl, ~ C ~ w!C )!, ~ ~ 4 ~ ) / A ~ C ~ a.' j C! yP.) C N g) ~ ~
~~. ~V. ';f "o)~ i':"~5 I.'I'I~~
~~~ ~ "C ST. LUCIE - UNIT 1 Amendment Ho. ('1 t 'C l a'l'I ~ ~ ~~~
";,'>. >>1STRAT

V= COtlTROLS i 94 1
~~5 'lf, '7~~
~~6. 1$.~~
PROC"-SS CGhTROL PROGRAH (PCP) FF.'C The PCP shall be approved by the ~>~~ prior'o implementation. 2 Licensee initiated changes to the PCP: Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report >or the period in which the change(s) was ma'de. This submittal shall contain: Suffic>en lv de'ailed informat::on to 'otally supor. the rationale for the
~~.-'-ange without benefit of addi ional or supplemental information; C.~~
A determination that the change did not reduce the overall conformance of the solidi>ied waste p-. oduct to existing criteria for solid was es; and f Documentation of the fact that the change has been reviewed and found acceptable by the FRG. 2'. Shall become e> fective upon review and accep ance by the FRG. g/ 1 $>
~~6. 1(..~~
GFFS > T"" DOSe, CALCULATiC'h ViAHUAL (GOCH') The ODCH shall be >p'proved by the Commission prior to imp>ementation. 2 Licen'se initiated changes to the ODCH: l. Shal 1 be s ubmi tted to the Commi ssi on i n the Semi annua'. Radi oact i ve ii>i>ent Release Report for the period in which the change(s) was lade ef > ecti ve. Thi s submi t"al sha1 1 conta i n: Sufficiently detailed information .o totally support the ~ ati onai e =or the change withou> bene f > t of additional or supp i e-men-.al in>ormation. Information submiL.ed should consist of a package of those pages of the ODCH to be. changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s); b. A determination that the change will not "educe the accuracy or reliability of dose calculations or setpoint determinations; and c. Documenta.ion of he fact that the change has been reviewed anc'. found acceptable by th FRG. 2. Shall become effective upon review and acceptance by th FRG.
/}}

L-82-490, Forwards marked-up Revision to 820513 Radiological Effluent Tech Specs.Approval Requested by 830101 to Allow Effective Implementation of New Environ Protection Plan & Pending Tech Specs.Pages 1-5 & 1-6 to Be Forwarded Under Separate Cover

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L-82-490, Forwards marked-up Revision to 820513 Radiological Effluent Tech Specs.Approval Requested by 830101 to Allow Effective Implementation of New Environ Protection Plan & Pending Tech Specs.Pages 1-5 & 1-6 to Be Forwarded Under Separate Cover

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