ML20206G211
| ML20206G211 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/30/1999 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20206G068 | List: |
| References | |
| NUDOCS 9905070128 | |
| Download: ML20206G211 (81) | |
Text
I 1
i Document Centrol De:k LR-N99096 LCR H99-02
.-v HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50 354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)
ENVIRONMENTAL IMPACT ASSESSMENT PSE&G has reviewed the proposed License Amendment Request (LCR) against the criteria of 10 CFR 51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, PSE&G concludes that the proposed change meets the criteria delineateo in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10) for a categorical exclusion from the requirements for an Environmental impact Statement.
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l 9905070128 990430 PDR ADOCK 0500o3 4
HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)
TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this change request:
Technical Specification Paae INDEX ii, ix, xv, xvi, xviii, xxi, and xxii DEFINITIONS 1-4,1-6 and 1-8 3/4 3.7.10 3 / 4 3-91 thru 3-95 3 /4 3.7.11 3 / 4 3-96 thru 3-102 3/4 11.1.1 3 / 4 11-1 thru 11-4 3/4 11.1.2 3/4 11-5 3/4 11.1.3 3 / 4 11-6 3/4 11.21 3 / 4 11-8 thru 11-11 3/4 11.2.2 3/4 11-12 3/4 1123 3/4 11-13 3/4 1124 3/4 11-14 3/4 112.5 3/4 11-15 3/4 1128 3/4 11-18 3/4 113 3/4 11-19 3/4 114 3/4 11-20 3/4 121 3 / 4 12-1 thru 12-12 3/4 122 3/4 1213 3/4 123 3/4 12-14 684 6-16b
6.9.1.6 6-18 6.9.1.7 6-19 and 6-20 6.10.3
(>-22 6.13 6-24 6.14 6-24 6.15 6-24 and 6-25 B 3 / 4 3. 7.10 B 3 / 4 3-6 83/4 3.7.11 B 3 / 4 3-6 B 3 / 4 11.1.1 B 3 / 4 11-1 B 3 / 4 11.1.2 ~
B 3 / 4 11-1 B 3 / 4 11.1.3 83/411-2 B 3 / 4 11.2.1 B 3 / 4 11-2 B 3 / 4 11.2.2 B 3 / 4 11-3 83/4 11.2.3 B 3 / 4 11-3 B 3 / 4 11.2.4 B 3 / 4 11-4 B 3 / 4 11.2.5 B 3 / 4 11-4 83/4 11.3 B 3 / 4 11-5 B 3 / 4 11,4 8 3 / 4 11-5 and 11-6 B 3 / 4 12.1 83/4 12-1 B 3 / 4 12 2 83/412-1 B 3 / 4 12.3 03/412-2 l
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INDEX OEFINITIONS
_SECTION DEFINITIONS (Continued) 3 D4GE
'\\
- 1. 26 0FF-GAS RA0 WASTE TREATMENT SY5 TEM...
14 1.27 0FFSITE DOSE CALCULATION MANUAL..............................
1-4 1.28 OPERA 8LE - OPERA 8ILITY.....................................
i 1-5 1.29 OPERATIONAL CONDITION -CONDITION..............................
15 1.30 PHYSICS TEST5....................................................
1-5 1.31 PRESSURE BOUNDARY LEAKAGE......
...................a 1-5 1.32 PRIMARY CONTAINMENTINTEGRITY.....................................
1-5 1.33 PROCESS CONTROL PROGRAM............................
1-6 1.34 PURGE-PURGING...............
1-6 1.35 RATED THERMAL POWER................................................
i 1-6 O
1.36 REACTOR PROTECTION SYSTEM RESPONSE TIME..............................
J',
1-6 1.37 REPORTABLE EVENT......
l 1-6 1,38 R00 DENSITY...............
1-6 l
1.39 SECONDARY CONTAINMENT INTEGRITV.
1-7 1.40 SHUTOOWN MARGIN.......
1-7 1.41 SITE BOUNDARY............
1-7
- 1. 42 @0yICyr190. u.e 7..v. 5 cp 1-s 1.43 SOURCE CHECK.............
1-8 1.4.A SPIRAL RELOAD.........
1-B 1.45 SPIRAL UNLOAD..........
1-B 1.46 STAGGERED TEST BASIS.
l'8 1.47 THERMAL P0WER..............
1-8 1.48 TURBINE BYPASS SYSTEM RESPONSE TIME..................................
1-9 )
.. s f
HOPE CREEK
.i i AmendmentNo./ v
- NDEX
- .:Mt?Iw, coserttons Pon oPERATII:N AND StlRVEII.I ANCE REQUIREMENTS ste ren Table 3. 3. 7. 4-1. Remota $hutdown Monitoring M
Instrpnentation 3/4 3 75 Table 3.3.1.4 2 Remote Shutdown Systems controls 3/4 3 33 Table 4.3.7.4 1 semote shutdown Monttertag Instrumentatton Surveillance Requirements 3/4 3 83 Acendent Monitoring Instrumentation 3/4 3.g4 l
Table 3.3.7.5 1 Accident Monitoring Instrumentatton 3/4 3 g5 l
Table 4.3.7.5 1 Accident Monitoring Instrumentation l
survetilance Requiremaints 3/4 3 37 Source Rances Monsters 3/4 3 33 Traversing In-Core Probe System 3/4 3.s5 Radioac ve Liqu Efflue Monttori Inst tation 3/
3-31 Tabl 3. 3. ~7 9
Radte ttve Laqu Effluen Mont orang Ins ntatt 3/4 39 l
.able 4.
7.9-1 dioactive aquid If uent stortng
. Ins t rumen e on Su 111ane Require nt 34 3 94 R toactiv Gaseous fl Me stortng natrums atton 3/4 39 Tacle 3 3.'
10 1 da et Gaseou Effluen Mon 43r6r g Inst ntatto 3,4 3-ti e 4.3.7 1
1 ettve eous Et uent Mon arang In rumenta on Surve lance treme s 3/4 31 i
3 4.3 3 ::Eh 1
3/4 3-103 I
3 4 3 9 FEEDWATER/ MAIN TURSINE TRIP SYSTEM ACTUATION INSTRtMI3rTATICII 3/4 3 1C5 l
Table 3.3.9 1 Feedwater Main Turenne Trap System Actuat &on Instr.mntation 3/4 3 106
-e-J D\\
l i
12 GEE LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREM SEC*IQW 3/4.3.11 RESIDUAL HEAT RINOVAL AND COOLANT CIRCULATION E.h3E I
Migh Water Level.....
3/4 9-17 Low water Level............................
3/4 9 is 3/4 10 Spre!AL Trtt ExcrPT!ONE PRIMARY CONhAINMINT INTw RITY.................
3/4.10.1 1
3/4 10 1 3/4.10.2 RCD WORTH MINIMIZER...................................
3/4 10 2 {
3/4.10.3 SNUTDOWN MARGIN DEMONSI1LATIONS.........
3/4 10 3 3/4.10.4 RECIRCULATION LOOPS...................
i 3/4 10-4 3/4.10.5 OXYGEN CONCINTRATION....................
3/4 10 5 l
3/4.10.6 TRAINING STARTUPS....................................
3/4 10-6 3/4.10.7 SPECIAL INSI1tUMENTATION - INITIAL CORE U3ADING.......
3/4 10-7 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING..............
3/4 10-8 3 /4 11 RAS
- 0 At'"*!VE E FF1"EN* S 3/4.11.1 1.ICUID EFFLUENTS
( Concener tion.
/4 11 1 7 le 4 1.1.1.
1 Ra osctive squad W ste S
lin Analy a Prog am.,
3/4 1 2 I
Do e.
l 3/4.1 5 1qua Waste rest t...Q..............
4 11 6 Liquid Moldup Tanks.......
3/4 11 7 3/4.11.2 GA.5BOUS EFFLUENTS se te...
3/4 10 able
.11.2.1.
1 Rada ctive secus aste Sa ing an Analy a Progt 3
11-9 j
se -
ble Gas
..f.....................
/4 11 13
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Dose Zodine 31 I no-
. Trit 1 and Rad' nuclides in Pa' iculat Fo 3/4 11-3 seous R waste eatman 3/4 1*14 Vental son ust Tre taant stem....
3/ 11-15 l
HOPE CRIEK xv Amendment No.
1E11 LIMITING CONDITIONS FCR OPERAT:0N AND S'wltVE '_USOE RE;t,*!ADer."5 l
C FA E Main condenser.
3,
'Ogt,,g 7@
Vs.. tang or Parg ng.
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Tat' 4,12 1 ' Oete:::: Capas:1 ::e For Envar:n ntal Samp e alys ts.
3/.: ;L 3/4.1:.2ms erns::s.
3/4 12. u DCM e:m.,A;sCRA* RY I;** PAR:50N ROGRAM.
3/4 1 -;4
/O y
afg Amendment No
INDEX l
easts SE m ew 2 AGE ins nt9eprA?!cw (Continued) f l
Remote Shutdown Monitoring Instrumentation l
i and Controls 1
Accident Monstering Instrumentation 3 3/4 35 Source Range Monttore 3 3/4 35 3 3/4 3-5 Traverstng In Core Probe Systee 5 lie 3 5 r"Radica ave La Rifluen Mont et I
f In rumenta on
. /..
B i4 36 l
Ra osctive aseous Ef uen orang
- nst rum tation
()
5 3/4,- 6 _J
- 3. 4 3 I DELETED E 3/4 3-1 3 4.3.9 FEEDWATER/ MAIN **.*R3!NE T1t!P SYSTEM ACWATION INSTRUMENTA*:0N B 3/4 3-1 l
Ftrure 33/4 3 1 Reactor Vessel Water Level 3 3/4 3-8
- 3. 4 4 REA N R ?OC'M SYSTEM l
} 4 4 RECIRC"LA* 0N SYSTEM 3 3/4 4; 3 4 4 : SAFETY /REL EF VALVES t 3/4 a
3 4 4 3 REAC*OR 00CLANT SYSTEM ' M N E Leakage Cetection Systema B 3/4 43 Operational Leakage B 3/4 4J 34 4 4 CMEMISTRY B 3/4 43 3 4 4 5 SPECIFIC ACTIVITY 5 1/4 64 34 4 6 PRESSURE /TEMPERATURK LIMITS B 3/4 45
- able 33/4.4.5-1 Reactor Vessel Toughness 3 3/4 4*
hayure 33/4.4.5 1 Fast Neutron Fluence itelmeva at ft/4tT as a Punct ten of Service lif e B 3/4 40 l
l l
l HOPE REEK avset Amendmsnt No jd l
g BASES S EL""*T ON P.h?iE 3/4.10 SPECIA1. 'fTST EXCEPTIONE 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.
B 3/4 10-1 3/4.10.2 RCD WORT 11 MINIMIZER B 3/4 10 1 3/4.10.3 SNUIDOWN MARGIN DEMONSTRATIONS B 3/4 10 1 3/4.10.4 RECIRCUULTION LOOPS I
B 3/4 10 1 3/4.10.5 OXYGEN CONCENTRATION B 3/4 10-1 3/4.10.6 TRAINING STARTUPS B 3/4 10-1 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING B 3/4 10 1 3/4.10.8 INSERVICE LEAK AND KYDROSTATIC TESTING B 3/4 10-2 3/4 11 RADICAE!vE ETTI.UENTS 3/4.11.1 LIQUID EFFLUENTS
/
l one trat Y
B 4 11 1 Do 3/4 11-1 quid dwaste.reat t Syste B 3/4 11-;
Liquid Holdup tanks B 3/4 11 l
l 3/4.11.I GASEOUS EFFLUINTS l
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B 3/
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,4 11-3 se - odine-1.
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3/4 1 3
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Gas us Ra este Tr ement S stem and i
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11-4 Main Condenser B 3/4 11 5 Venting or Purying B 3/4 11 5 Dd%51GQ 11 y 2 / 4.11. 3 A SOLID I
.IvE TE.
B 4
5
/4.11.4)
3/4 5
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l HOPE CREEK xx1 Amendment No.
h
~
1
r INDEX BASES l
i SECTION PAGE 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING DWN
/
3/4.12.3 MONIT ING P d
GRAM........ 4.
B3 12-1 "D N 3/4.12.3 LA USE NSUS........ g....................
3/4 12.
DO# 3/4.12.h NTERL ORATO COMP ISON P RAM......
B 3/4 2-2 l
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HOPE CREEK
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OEFINITIONS LINEAR HEAT GENERATION MATE 1.21 LINEAR HEAT GENERATION HATE (LHGR) shall be the Isngth of fuel rod k
iated with the unit length.It is the integral of t per unit transfer area assoc.
_ LOGIC SYSTEM FUNCTIONAL TEfT, t
1.22 A LOGIC SYSTEM FUNCTIGNAL TES
- ents, i
etc of a logic circuit, device, to verify QPErA8ILITY.from sensor through a:1d including the actuate ements.-
k performed by any,tries of sequential, overlapping or such that the ent ue logic system is tested.
s MAXIMUM FRACTION OF LIFITIPG POWER DENSITY 1.23 The MAXIMUM FRACTION 0/ LIMITING POWER DENS value of the FLPC which exists in the' core, MEMBER (5) 0F THE PUBLIC 1.24 MEMBER (5)0FTHEPUBLICshallincludeal associated with the plant.
the utility, it contractors or vendors.This category does not include employ Also excluded froni this category are persons who enter the site to service equipment or to make deliveri This cate aticaal, gory does include persons who use portions of the site for recre-occupational or other purposes not associated with the plant.
MINIMUM CRITICAL POWER RATIO
- 1. 25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the exists in the core.
smallast C.GR -nien
(
CF:-GAS RADVASTE TREATMENT SYSTEM
?
1.26 An OFF-GAS RA0 WASTE TREATMENT SYSTEM is any system de tem offghses from the main concenser evacuation j
delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
OFFSITE DOSE CALCULATION MANUAL 1.27[The FF5I 005 CALC TIO L (0 ' M) all ntai the urr t thee ph ol a
par ters sed n^
cal ati of fsi dos a
to eacio fy g g.-
, ive gaseo and ioui ents in e ca ulat on of gas us d
a tau effl ent itor rm/
io s opoin
,a in ee duc of e
rao ologi 1 en ro nit ing rogr
~
HOPE CREEE l'8 A"'"d"'" * "' 'W l
LCR H99-02 INSERT A 1.27 The OFFSITE DOSE CALCULATIONAL MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gmeous and liquid effluents, in the calculation of gaseous and liquid effluent i
monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monito ing Programs required by Section 6.8.4 and (2) descriptions of the information that s' -). 'd be included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by Specification 6.9.1.6 and 6.9.1.7.
INSERT B 1.33 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and
/
packing of solid radioactive wastes based on demonstrated processing of actual or timulated wet solid wastes will be omplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1 I
DEFINITIONS 1
- 1. 33 5g._
OC S CD R
(
th t
SOLI FI TI or wa rin and acka ng ra 'oact' e =a oes in e pr isi s to assur r sui in Mh::.x T was e p ckag wit pro rti th mee the inim an tae' ity equ' em ts a 10 FR P rt and ther requ' eme s fo tr s-pc atio to e
ispo 1 s' e a-S IDIF CAT N,
he P s
11 11 y th pro ss p ame rs i lu cin re ipt t th dis sal ite.
dit OLID IC 0 such s p, ci f
' nt, 50 e ten sol' s e ten rat'o of lid ic ioh gen to s g nd/o nec sary ddi ves r
en ce o ant ip ad w te, and opt ab nda con tio fo the roe s ar er sha be den i
for ch ste e,
ased n1 or cry sea a
ful se et tp re orie e.
ith at ing the CP all i
u an ont ica con tio the sus es isf ed, ase on 11 cale es ng, re at d ater go boa res s,
wde d re ns, df ter lud s wi re it i vol s
fre wa r,
the t'
of ais sal with' th limi of CF Part 1 do the ow-1 vel acio tiv was di osal ite.
PURGE - PURGING T
1.34 PURGE or PURGING shall be the controlled pro:ess of d l'
from a confinement to maintain temperature, pressure, humidity tion or other operating condition, in such manner that replacement a
, concentra-gas is required to purify the confinement.
RATED THERMAL POWER T'
1.35 RATED THERMAL POWER shall be a total reactor co f
the reactor coolant of 3293 WT.
L REACTOR oROTECTION SYSTEM RESPONSE 'IME 1.36 REACTOR PROJECTION SYSTEM RESPONSE TIME s m
when the monitored parameter exceecs its trip setpoint at the channel 8 !
1VI sensor until oe energization of the scras pilot valve solenoids.
The total steps such that the entire response time is measured.
REPORTABLE EVENT 1.37 A REPORTA8LE EVENT shall be any of tnose conditions specified in l
Section 50.73 to 10 CFR Part 50.
R00 DENSITY 3
b 1.38 ROD DENSITY shall'be the numoer of control rod notches inserted as a fraction of the total numoer of control rod notches.
All rocs fully inserted is equivalent to 100% R00 DENSITY.
\\.
' HOPE CREEX I
g 1-6 AmendmentNo.[
DEFINITIONS SOLIDIFICATION blot oSED
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1.42 l 50L FI ION all et i
i[i ion
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actiewdes eva rato ot s,
ent e
, slu es no r ers osm is.nce w
ra sca ra as res o a or s
the ug mi 'ng t wa r :- e n'.n a s
idif ati ag (s) a fr s ndin mono th th.emi 1
l nys ' Ic rac ris/ts.
ifie in e PR E55 NTR PR RAM PCP l
SOURCE CHECK Q
l.43 A SOURCE CHECK shall be the qualitative assessment of when the channel sensor is exposed to a source of increased rad ivity.
i SPIRAL RELOAD 1.44ASPIRALRELOADisacoreloadingmethodologyemplop after a complete core unload.
During a SPIRAL RELOAD the fuel is to be loaded into incividual control cells (four bundles surrounding a co d
blade) in a spiral fashion centered on an SRM moving outward i
initiating a SPIRAL RELOAD, up to four bundles may be loaded in th Before bundle locations immediately surroundinq each of the four SRMs to our the required channel count rate.
1.45 A SPIRAL UNLOAD is a core unloading estoodology employed t the complete core is to be unloaded.
The core unload is performed oy first removing the fuel from the outermost control cells (four buncles surrounding a control blade).
Unioading continues in a spiral fasnion by removing fuel from tne outermost periphery to the interior of tne of the four SRMs. core, symmetric about tne SRMs, except for the four bundles When sixteen or less fuel bundles are in the core.
four around eacn of tne four SRMs, there is no need to maintain tnee-ouired enannel count rate.
)
5?AG0ERED TEST BASIS
/
1.46 A STAGGERED TEST BASIS shall consist of:
A test schedule for n systems, subsystems, trains or other cestgnatec a.
components obtained by dividing the specified test interval into n equal suointervals.
The testing of one system, subsystem, train or other designated b.
component at the beginning of each subinterval.
THERMAL DOWER 1.47 THERMAL POWER shall be tne total reactor core heat transfer rate t l
' OPE CREEK 1-S A**"d"*"t N
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.3.7 10-1 300P3 CREEE 3/4 3 91 Amendment 6a.
4 PAGES 3 / 4 3-92 THROUGH 3-95 INTENTIONALLY BLANK
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HOPE CREEK AMENDMENT NO.
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With nume of ch els OPE LE le than r uired e ne Min um Cha els OP 8tE. re rement effluen release via tn' hway conti e provi d that ior to itiati a rele' e:
a.
t' leas two ind endent les analy in ac rearce with ecific on 4.1.
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least tech cally o (fied Staff ers ly the the Faci ty opend
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efflue via ACT 111 -
With e numbf of chan is CPE LE less an re red b he Mir' um Chan is OPE LE re
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- that, least a per hours grab s es ar ellect and an led fo gross r ioactivd at a sit of etecti of at I st 10 ? terocu es/al.
he r-wi
, susp roles of rad etive fluent in this athway.
ACT M 112 -
with numbe of chan s OPE E les han re red by Min Cha is OPE LE reo
- esent, fluent leases a
s pat y say e inue p vided flow r e is es ted at east a per a curs a ng act roles Pump rformance cury genera d in p1 e say b used to stimate ow.
l HOPE CREEK 3/4 3-93 Amenement No.W!
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CHAh4(L NCTIONA IST sn alle e nStrate at aut tic 1 f this n=ey a entrol alare nuncia n occur 4t'en follow' g conett s eats any tne
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Instr nt inst tes asas et lessi steve t Al rip 5et nt. or
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cuit f ure, or Ins nt'in ates a scale lure.
) The AmtL F T!0 MAL T shall so astrate at cent room rm aARb ation oc rs if o f..
olleet concitt entsts:
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strument dicate asure fels.
we the re.5etpoi or dL/
- Circu fatlur, or i,
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strumen inetca cale fall (3) init CMAm CALI 10al snal perfo using e or more of the re rence neares artiftet the 184%
41 lures f Stansard (N05) or ng s ares t have ottai w res suas et that pa icipate e.esur nt as ance act ties wi C 5.
The staneares all per t calier ng t ystem av its intepe6d range energy a asurea re For secuent L CA}!DRATI0lt, etes that we seen latea t
ne in al calit ten er -
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C L CHECK s I consi ef vtrif indicat of f1 uring per as o release.
EL A shall - asse at 1 t once 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> says on n sentin ua, part c, er 64 release ce ease.
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,,, c
- u.,,8
inugunerrarion 3 3. ~7. J/
ONLG W mantas.wiva amagsgs a m,um.i mostrTad rusTatre.,.mtrow I,IMITING COND FOR OF 3.
.11 The radi ive gas a offluen nitor inet sation annels own in Tabi
.3.7.11-11 be CP wi their
/ Trip spointe set to ens that t imits of ifica ns 3 11
.1 and 3
.2.6 a not eme The Al Trip Set to of se ch a meeti specif tion 3.
. 1 shall deterni and ad ed in ordance h the hodel parame e in the APPL aff. TTY:
howd i able 3.
.1 Y
W a.
Wi a radi tive gas e afflu monito inst ation annel rs/ Trip point 1 conee ive than trod b he pecificat immed ely sus d the re se of ra active us eff1 to monit ed by t affected nei, or clare t channel i
- rable, change setpoin it is captably conse ive.
b.
th less an the a numbe of radio ive gas e
offlue monitori instrume tion cha is OPE
, take t ACT shown able 3.3
.11-1.
I best orts to r en the strument o OPERAS status wi n 30 da and, if u ccessfu explain the nort adioactiv ffluent lease pursua to spee cation 6.
.1.7 why a inoper 11ty was correc in a t
ly manne The y sions of pecifica n 3.0.3 ar not appi le.
SURVII MCI REQU s
4.3.7.1 ach rad ive gas effluent nitor not ation chan shal demon sted o by perto ce of N*
_ CRICK, so CALIERATI and FUNCTI TEST a the freque es shown le 4.3.7.
1.
1 30PE CREEE 3/4 3*IO A"**d**"t
6 4
l h
PAGES 3 / 4 3 97 THROUGH3-102 INTENTIONALLY BLANK
- 1 HOPE CREEK AMENDMENT NO.
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Amendment No M
/ Ht s PAGa IN72N770 WALLY ~~6 Lim K
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M MOPE Ctitt 3/4 3 w Amendment No. /
iM-1 TAR 3 3 i
(~c inued)
? LE NCTA2' ION At 1 time ACT 122 With he a of C als RABLE ese t)-
requir by tt Mar um C cls CPE LE r treme.. effl at rol ses vi l
t s path may c etnue rovide' the fl rate i esta ed t least e per hou. Othe ase. e end re ase of radios ave off eats a his athway i
A
.CW 123 Wit the n r of PERAE less t n requ ed by
..e M tmum als E
5 equire nt; of uent r eases
.a is pat ey ma con prova d grab mples e tak at least ce ye 2
and t se samp s are lysed or 1
gros activs w
24 hou. Othe ase, a pend r ease o' i
rad etty e s via is path y.
)
A0"1CN 24 ACT NN 125 Uit the n r of C annels ERABLE.ess th requi d by th M 1 mum Ch als C RABLE r trem
- t. eff' ent re* ases vi se pas ay may entinue rovide that w han a curs sarr aes are co laucus collec d with uxilia sampi
.g equip nt as requa d in T le 4.11
.1.2-
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TABLE 1.11-onti ed)
TABL NOTATI At a times.
t 1)
CMANNE CTIO TEST 11 als demo trate t con el som ela annunct ion oc a if of a folle ng condata a exist 1.
nstrume indica e meas ed le is abo the arm setpot
/
\\
2.
Cir at fail e.
j 3.
trume indie es wnscale ailur (2)
Initia CHANNE C TION s 1 be rformed sing o or of t.e refer n dards rtafte by the attona Rureau of Stan rds (
)
r ing at dards at have een ob ained f rom pplier tha rctespa in me suremen assura e 1
act attes th NBS These andard shall rmat c thrating system ver 1 anten d rang of ener and surement
- e. F subs ont L
.3EATIO. sourc that ha r ated t the an tal ca bratto or are 5 tracea e shall use T N ).s Acas /H YmmontAcl Y d&K HOPE CREEK 3/4 3 102 Amendment No
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS SJ //. I, / DSL C76 L.um tMIRATIOPVQ LIMITING DITI OR OP ON 3.1.1.1 T
concent ation of adioacti e materi relea d in li vid effi ents to NREST TED ARE (seeFigure5.1.
- 1) shal be limi ed to t concen a-ons sp ified in 0 CFR P t 20, endix 8 able I, Colum for r io-l nuclid other t n disso ed or en ained n le gas For ssolved r entra ed noble gases, t concen a ion s 11 be 1 fted to x 10
- l mier curies /s total a ivity.
1 PLICA 81L
- At I times.
ACTION:
(9 with he conc tration f rad'io tive ma rial re ased in iguid eff vents j
to NRESTRI D AREAS xceedin the ab e limit, immedi ely resto the e ncentrat' n to wi in the ove lin' s.
SURVEIL NCE REQ REMENTS
/
/
/
/
/
/
/
/
1 4.
.1.1.1 adioacti e licui wastes all be s spled and analyzed cording the sam ing and nalysis program Table
.11.1.1.1 V
)
4.11.1.
2 The sults the rad' activit analyses hall be ed in actor ance i
with e metho logy an paramet s in th ODCM to sure that he concent ations 3.1;;.1.l, at e point relea are mai ained w' hin the sits of ecificatio
_J HOPE CREEK 3/' 11-1 t
4 l
1 1
PAGES 3 / 4 112 THROUGH 11-4 INTENTIONALLY BLANK i
HOPE CREEK AMENDMENT NO.
7~N/s PA sG i^'~r^vv ~r'*AL L Y ~e Lw K 11.
1 ICAcT
!.!cUI AsTE I.ING ANALY.5 PROG
/
/
/
/
/
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ower :...::
Min um Type of De c::en quid Rel se amplin lysis Act sty
( 1.1.3 Typ Frequ cy equenc ysts (a /ml)
A.
acch see "P
Prin' pal Relea Each B ch ch Ba Ga 5x10
Sam e
atter T
s (3)
[ I-13[ [
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atc/h
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Relea s'
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Wa* r s em I-1 i
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M ssolve and 1x10 as cacM Gr Samp Entrai d Ga by ACS -
(Gam Emit s)
CS sy.em.
f H[
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[ ix10 N
M ite,[ Gross
-omp lpha 1
N Q
Sr 9.
S 90 x10
C=mpos e,
[
lx1T' e-5 c/
/ /
/ /
/
/
/
l HOPE CREEK 3/4 11-2 Amendment No. f
l T/-N 5 PA 6&T /n'7m 77 WALLY
~BLArJlt LE 4.1 1.1 ntinu TABLE TATION a f LD is ined, f purpo s of the speci cations, s the 11est entrat n of re oactiv material nas le that 1 yiel a not ount, a ve syst back und, t will detected 1th 9 robabil y with o y 55 p abilit of fals conc 1 ing that bidtk, servat
~
repr ents a " eal" a nal.
)
F r a pa cular asurene syst which incl adioC cal separat n:
/
+-
b EV.2.22 08 Y
exp (-
e:
LLD the " priori" r Ife de tion as afined ve, a
icrocur es per u t mass v une s
is e stand devia n f backg counti rate gi' tNe unting r e of a ank /
e as riate, s coun per si te, 1
E is th countin e i i y, as e nts per sintegr ion, Vi the s e size units mass or olume,
.22 x 1 is the, umber o disint tions r minu r mict urie, Y is he fra onal ra ochemic
- yield, n app cable, is the adioacti decay notant r the p ticular adionuct (sec 1, and
/
at or plan effluent is the apsed bet the si int of le co oction time counti (sec).
Typic values f E, V and a should used in ca) ation.
It s Id be ogniz at the LD is ned as a eri i (before the act) 11 t rep enting t capabi y of a asu t systes as an, poster ri (aft the fac Itait f a pa cular os resent.
A be roles is the scharge liquid stas a discre volume.
Pri to s ing for nalyses, ach be shall tecla
, and then rough) sized by method scribed the
.A to as represe ative sampli MOPE CREEK 3/4 11-3
l e
eis d 11.1. /1,e..d'.2...
/
,/. -m/
~
/
' The riacipe gamma ters f which LLD e ificat n a lies as usively re Mn-
, Fe-59 Co-58,
-60, 3 5, Mo-e-134,
-137, co-14p Co-144 11 al sea red, b with aa
,f5m Thi does an the only
- ee sue des are to consi ed. oc peaks atifi e, t her wit I
t se of t above clidas, ha al be med report in e
he Radi etive fluent e
et pur ant to pocific ion W
o 6.9.1..
A i
sample ich t quant y of 1 id o es a pr.
Lonal t
ity of iguid sto die in which he est of its in spec that i e
sentati of the,,quida lea
- A conti ous role is t disc rge of id w as of a nondi rete yo
- e.
, fr a voi of a o tem the as an in flow d ing th conti us role s.
l g
mops CREIE 3/4 11-4 A"*"d"*""
[
RADI0 ACTIVE EFFLUENT 5
. t, 2.
D 5 L,GE T V LIM TING'CONO P aTION l
/
3.1'.
2 rne e e or oose ommitmen
.o a ME R OF TH USLIC f o ive mater' s in 1 to 'd efflue relea
, f os n reactor nit, to rac o-UNRESTRICT AREAS ( e Figure.. 1-1) all be I ited:
Duri any cale e cuar r to les han or a 1 to 1.
to Docy a to les han or al to 5 rems :
s to a orgsn.
b During y cale r year ess tha e equal 3 mrems.o t.e tota ody an^ to less an or eau to 10 ms to a cegin.
aPPLICAB Y:
A 11 time ACT a
With t cale dose f the ese of r oactiv aterial in guid eff1 nts ex ding a f the limit, prepare it to Commis on with 30 days, rsuant Specif
.c tion 6.9
, a See al Repo that ide fies t cause(s or i
.excee ng the
'mit(s) defines cor ive act s that ha been t en to r e the asas a the pro ed corr -,e tions be tak to assur hat s-auent r asas wi ce 'm I
comp 1 nce wit ne above sits.
b.
prov ons of 5 cificat 3.0.3 not ap caele.
VEIL REQUIR S
l 7
.2 umulativ dose con butions If oufi ts f the current calen quarter the c int cal r year
- ) be date ned in ac nce vi the set logy an parameter n the 00CM least once per days.
l i
HOPE CREEK 3/a 11-5 Anenoment No. /
RADI0 ACTIVE EFFLUENTS 1 L,3 ~D&2AY@
1
,,w. m e iutATMENT /
LIMITING CONDI
/
1
/.-
3.11.
3 The 1 uic ridw te tre nt sys a shall e OPER E and ao w riate oc ions of a system all be see to e uce th actoa ve materi s in iouid wa s prior their senarge non the roject doses ou to the liquid, fluent, om each eactor it, to ESTRI D AREAS Figu 5.1.1-1 ould e eed *0. 0 ree to e tot ody or o area e
o n in an 1-cay iod.
any APPt.IC LITY:
all ti s.
A i
[
/ V_
With dioact liqui as b(i dische ed and excess the ab e limit and an ort he lio '
radwa e tres syst t in o
- ation, a
sutait the C ission w in 30 s
pursu to So f
1
.3.2 a cial R rt that ludes e
foi ing in rea Ex anation why li d radw e was be disch ed wit ut eatment dentift ion of ny inope le equ nt or b-systass nd the ason f the ino ability 2.
Ac on(s) n to r ore the perab) equipes to OPE atus, a Suse descr tion of ion (s) ken to vent a currenc The ovision of Spect cation
. 3 a re t appife e.
SURVEI NCE RE REMENTS 1
.1 Dose us to 1 id rei ses from ch reac unit UNREST TED AREA shall be reject t leas nee per days i ccordan with a
coology d par rs in 00CM.
4.11.1
.2 The stalled guid ra ste tre nt sy shal demo rated OPE LE by ing S fication
.11.1.
no 3.11
.2.
/
/
HOPE CREE <
3/4 11-6 Amendment No. [
Q
RA0!0ACT!VE EFFLUENTS 3/4.IL2 GA5E0US EFFLUENTS
- 3. ij. z i nm nano
" Dost RATE l
LIMITINIVCON0!TI5N FOR OPER47!0N
/
/
/
/
3.
1 T'
sose re due to r foecti e aster Is rol sed in soeus eW1uents ren the si to ars' at beyond SITE Y see
/
pure 5
.1-1) she he limi to follow ng:
For e gases:
Less er 1 to arems/
to the tal besty less or 1 to yr to
- skin, b.
For fedine-
, iodi 133, t tium for al redt ides in iculate em wi half-1 ves gre, er than days:
ss than 1 to yr to e
APPLIC LITY: A all ti s.
ACT!
//
W h the de rate (s exceedi thy we limits famedi ly reste the lease ra te vi n the ve (s).
SURVE!
E RE IREE
/
l l
/
- 4. 1.2.1.1 The de rate to netle p ses in seous off uents shd11 be temi to be thin the ve lial s in ac reance wi the me legy and par ters i the 00CM 4.11.
1.2 7 dose ra due to 1 ine-131 tedine-13, triti
, and all radio-nuci des in rticula fare with If-lir s greater 4
in gas s
off wenta 11 he es coined t be withi the abov limits i accorsa e with the 1
and par ters in 00 01 attaint represe tive s les and rfers analyse in acce a with sampli and ysis p as specified in Tab 4.11.2.1 1.
MOPE CAEEK 3/4 11 4
PAGES 3 / 4 119 THROUGH 11-11 INTENTIONALLY BLANK HOPE CREEK AMENDMENT NO.
k' M$ 4 hb1 N-
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Acss //v'7%iN770 HALL'f
~~ bland X-
~7~
/ s TABLE 4.11.M.2-1(Contind r
__ABLE' NOTATION (a)The is defined, or purposes o hese specific
/
co entration of dioactive mat ial in a sampi hat will yiel a net ons, as the s lest unt, above s tem backgroun, that will be with only 5 robability of aisely conclud g that a blan bservation ected with 95 robability.
represen a "real" sign For particular me urement systes which may inc1 e radioches al s aration:
- 4. 6 LG =
b
/
E V
2.2[ 10' Y
ex
-Aat)
Wh LLD is t "a priori" I r li t of taction as defi d above, I
1 as mi curies per un mass o
is the standa devia the background ounting rate of t e counting e ot/
a minute.
sample as appr fate, as cou per
/
E is counti e' iciency, as cou s per disint
- ation, is the sampi size in units o mass or vol 2.22 x 1 is the number disintegrati s per minute microcurie,
/
Yi he fractional iochemical y d, when appl
- ble, is the radios ve decay co ant for the p icular radi clide (sec 1), and at for nt effluent s the elapsed me between t sidpoint of sampi collection a time of coun g (sec).
ical value f E, V, Y, a t should be d in the cal ation.
should be ognized that e LLD is defi as an a, priops (before the fact) limi presenting t capability of measurement s ter nd not as an a pos riori (after t fact) limit f a particular asute.nt.
e HOPE CREEK 3/4 11-10
7]% s Pads h/wwwoau-Y w K 4.d.2.1.2-1 tbntinuedt TERf f
/Taafa
/
gyrogg (b) princi genea ami are for ch the specificat n applies esclusive are the f lowing r onuclides Kr=87, Kr-
, 1e-133, I
Ie-133m, e-135, Ke-138 in le gas leases and
-54, Fe-5 co-58, 40, In-
, No-99, 131, Cs-1
, co-137,
-141 and 144 in lod and part late rol ses. This ist does mea
- that niy thee ides are, he consi red. Othe gasuna peak that ase i tifLabi,
n her wi those of above c11 des, s i also be lysed a reported the Radt ive Eff1 Rei pure t to specifi tion 4.9.
(c) s ing and yeis shal alas be ormed fell ing shu own, e
up, or change seding 15% f RATED ERNAL POWE ithin a la e period This requi at does apply (1) analy a shows the the DOSE IVALENT I 31 concentt ion in primary lant has not nereased to than a ctor of 3; (2) t noble gas nitor shows hat efflu t activity as not iner sed nor than a fa e of 3.
(d) T tium grab amples sha be kan a least o per 7 day from the pont fuel 1 area, nov spen fuel is the spent uel pool.
- 4) The rat of the e le ta to the led stre flow rat shall be kn for the ime e ered by ach dose o dose rate cal lation ma in an with 8 ifications
.11.2.1,
.11.2.2, a
3.11.2.3.
(f samples e 11 be ng at less once per 7 ays and a lyses shal be complet within urs afte changing, after r al from o pier.
sampi shall al perto at less once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for t least 7d a following ach shut startup or THERMAL R chan exceedin 1
of RATED in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> analyse shall be e lated ithin 48 hou of e ing. When s les coli ed for 24 ours are analysed, t corres ing LLDs y be incre sed by a f or of 10 This requirene does apply if i analysis that t e DOSB B VALENT I-131 e contrati in the pr ry coolan has not in eased no than a facto of 3s (2) the e gas moni e shows th effluen activity has incro more t a factor 3.
k
~
gayg g J/4 11-11 Amendment No
aA010ACT1vt EFFLutwts 2:
TJ_: r""
- 3. //, 2., 7_,
VELET @
Ite!TI C sumn new.ros Ort & TI F
/
/
3.11.2.2 The air eve te netle ga released in each reacter uni, to areas at and seems effluents, the 517 shall to lie to the followl (see Figu 1.1 1)
During any cal e cuarter:
s than er eeuel erees for restatten ess than er 1 to 10 erees for radiation k.
Duri calendar
- Less than er to 10 or r game r
ation and less or 1 to 20 ads for tota istion.
f,k 49eLI ILITY: At all mes.
ON a.
th the caleu e
dose free r' eactive nette ses in geseems effluents esce i any of the e limits, y and suesit to the Commission tain 30 days ursuant to testion 6.9.2, a Special to that identi s the cause(s er escoeding the 1 t(s) and esfi the correc actions that we been taken to e
the e ases and in roseses correc e actions to be n ta as e that sees ont releases vi te in compliance the we lietts.
The are ons of Specift ion 3.0.3 are no 11 cable.
Survf!L REQUIREMENT 5
.2 Cumulativ se centributto the current cal e cuarter and current calencar er for neale sa shall be esteret n accercance with tne matheoelo ans parameters 1 00CM at least per 31 ears.
- )
/
n M0tt CRtEK 3/4 11*12 A""8" I " '
d
"?23H3
RADI0 ACTIVE EFFLUENTS 3
- t. 2 3 unon&
00SE - 100!NE-131. 100!Nf d 3. TRITIUM. M R L MITING CONDI FOR OPERAT!
I 3.1
.3 The dose a MEMBER OF TH BLIC from to
-131, iocine-tius, and all-dionuclides in rticulate fore th half-lives than 8 days i aseous effluen released, fr och reactor un eater at and bey the SITE 800N Y (see Figure
.1-1) shall b imitec to *. e to areas followi a.
During calendar quar Less than equal to 7.5 mr orga nd, to a.
1 b.
uring any cal ar ye Les an or equal to areas to y ---
AP CA8!LITY:
At I times
/ ACTION:
h With the e sted dose from e release iodine-131 odine-133,
- tritius, d radionuclide n particul form with f lives grea than sys, in gaseou fluents eeding any he above limi #.
t-
- pr re and subeit the Cossi on within 3 ys, pursuant -
- ecification 6.., a Speci Report tha ntifies the se(si for exceedin a limit defines t orrective acti tnat a.e, been take o reduce releases a the proposed rective ac /a:
to be en to ass that subs nt releases w s
be in como wi he above its.
b The prov ons of Spe cation 3.0.3 not applic e.
,{
SURVEIL REQUIR l
4.11.2.3 lative dose tributions f current cale r quarter and curren alender year f iodine-131, ine-133, tritius nd radionuclices in iculats fem half-lives eater than 8 day nail be determined accordance wi the methodolo and parameters i 00CM at least once per 31 days.
l
)!
i h (k e
\\
RADI0 ACTIVE EFFLUENTS
- 5. / /. 2. 4-D ditLA 7'esT "GA5E005 RADWAsit i niATG~v 4
LIMITING CONDITI OR OPERATION /
/
/
3.11.2 The GASEOUS WASTE TREAT T SYSTEM.all be in oper ion.
LICA81LITY: W never the
' operation.
condenser team jet air ctor system s in ACTION:
a.
With ga cus radwas from in noenser air ector syst bein ischarged thout reatne for more th 7 days, or a
submit to e Co i n w' nin 30 days re ion 6.9.2, 5
i por hat include he followi information:
ursuant to eci fica-1.
I ntific of e inoperahl equipment o ubsystems an he reason or e inoperabil y,
f Action (s aken to rest the inoper le equipment OPERA 8LE status and 3.
ry descrip n of actio taken to p ent a recurre e.
b, prov'; ions Specificat 3.0.3 are applicable.
RVEILLANCE RE REMENTS 4.11.2 The readi s of the rei nt instrument shall be checke 12 rs when tn in condense air ejactor i every sous raowas treatment s is functio ng. n use to ensu hat the C
f HOPE CREEK 3/4 11 14 Amendment No.
r
RA0!OACT!VE firLUENTS VENTIt.ATION EXHAUST *REA NENT Sv5*EN 3 s). 2. G 2 12k. e re o
' :w!'!NG CON 0!*!0N roe 08r
/
[
3.11.2 Sh VENTILATION Epa REATW[NT Sy *
- ce the Reactor sc mg anc t ervice anc Raowas wilcing snal e OPERA 8LE ano acer e ate :ce-s of nis systee ce used to a u'.e celease of rac cttvity.rea te projected cosas i cays eue to seous effluent role s ' rom eacn wnit -
areas at an yone the SITE
. OaRY (see Figure 5.
- 1).owie exceec-0.2 erad t r from ganma radia
, or e.
0.
rad to air free est diation, or 0.3 mree to any an of a ME ER OF PutLIC apet!cA8!LITY:
at times.
ACTION:
a.
With radioac ventilation exhaust ng discharged withe reat-ment and '
excess of the acove I ts, creoars and sw to see C oma '. on witnin 30 days our nt to Specification 2 a 5:ec at ort snat includes tne owing information:
f 1.
Identificati f any inoperatie e4 nt or swesystems ar the reas or the inoperacilit 2.
A on(s) taken to resto the inoperaale equi to CPERA8LE status, ano 3.
S m ry asse ton of action (s) tat
.o prevent a recurren e.
The previs s of Spectfication 3..
are not applicaele.
,j SURVEIL REQUitEMDtT5
/
4.11.2.5.1 Deses gaseows celeases each unit to aress a no eeyond the SITE RY shall ce oro ed at least once per 3 ys in accordance w the metnosology an arameters in the 00CM, a the VENTILAT EKMAUST TREATMENT EM is not Deing fully ized.
.2.5.2 The instal VENTILATION EXMAUST TREA NT SYSTEM shall b on-I sinered CPERA8tf D ting Specifications 3.1
.1 and 3.11.2.2 a
.;*.2.3.
/
M0PE CREEK 3/4 11-15 Amendment No. 19 sa :i mi
EMIMcTIVE EFFLilDffs V MTIM et PIR$1M
.3.//.2 8 'Ds2s-rm r trarrima ensortten set OPERATION [
[
[
/
3.11.2.8 or PURSIM the Mark I c tainment de 11 shall rough either the actor buildi entilatten s es er the f tratten, r rculation and vent tien system.*
t ILITY:
the con t is von er pur W.
a.
th the regu of the specifi ion not sat fied' suspend all IM and IM of the 11.
b.
The siens of ication 3.0 are not app le.
SURVEftt E REQUIRDtWT 4.
.8 The conta shall be etermined to aligned for IM or In through reacter bull ng ventilati system, the fi
- ation, irculatten ventilation tem, or rdened torus within 4 i
prior to s of and at 1 ence per 1 during M or F1RSIM e the dryue t
i i
i e
/
.t.d
.te rest, i_t
.,eJln4.a,1m.e dr m,,
ed d t.
Ammwhent me. 58 3/4 11-1s Hopt caEIK
RADI0 ACTIVE EFFLUENTS nm re:o a
3/4.11.3 5OLID RADIMCTIVE WASTE TjfbMENT GlHITINGCONDI FOR OPERAT
/
/
3 :.1. 3 adioactive w es snall be LIDIFIED or d atored in ace tne OCE55 CONTRO OGRAM to shipping and c4nce..;
ing transit, d discosal ansportation outremer:s/
site.
a requirements en received the oisco APPLICA8 4TY: At all ines.
ACT N 5
/ a.
/
With LIDIFICATION or.swa ng no eting dis sal site a.
s ' ping and transr tatic uir nts, suso a shipment
- e
.nacequately pro,ses a
correct th PROCESS C0 ROL ::..;;#
the procedures nd/o ol recurrence.
waste sys as neces to pre, i
b.
With SQL FI or aterin RAM, (1)g n performed accordan witn the P E55 P
natrate test or lysts tha he i r1 processed te in sac ontainer ets the uirements or ransportat n to the d osal site nd for rece'.
t the dispos site and take app riata aos strative ac :n ::
prevent ce rence.
c.
' The pro sions of 5 ification
.0.3 are n applicable.
l k
SURVEIL REQUIREME
/
7 4
. 3.1 The P 55 CONT PROGRAM s 1 be fell to verify t ttheo":-!
rties of t packaged w te meet th einfeue stab ity requi ts of 10 09 Part 61 a other requi nts for ansportatio the dispo site anc r 1
caipt a disposa site.
4
. 3. 2 The P SS CONT PROGRAM sha include suf cient evalit entrol d assurance thods to sure the sol fled wasta t from a process
('either in-use er e acted vendor meets the irements for ransporta-tion and eipt at disposal s a.
V HOPE CREEK 3/4 11*19
RADI0 ACTIVE EFFLUENTS C>e L.eE. Te:O 3/4.11.4 707:1 00-4 LINITiNGCONDITION OPERATION 3.11.4 Th nnual (cale r year) cos r dose commi THE PUB due to role es of radios-vity and to diation from anium fuel nt to any M ER Oc cyc1 ources shall limited to ss than or e 1 to 25 mren no or any orga except tne,t ro16., which s 1 ne limite o less tha to tne tota ual to 75 mr s.
e APPLICA8I At all es.
ACTI
[ a.
With a calculated sesfroM,ht lease of r osctive sa rials in iouid or gase efflu r
eding twie he limits Speci fi-tion 3.11.1.2., 3.1 1.
.11.2.2a'.. ~. 1.2.2b., ~. 1.2.3a.,
3.11.2.3b.,
eviat
/
d be made luding di t radiati contributi s fr n' s includi utside sto go tanks, c.
to date ne e
aoove limi of Specifi tion 3.11.
have been coeded.
I s
is the ca
, prepare submit he Coe-mi on within 30 ys, pursuan to Specifi tion 6.9.
a Special ort that def s the corr tve actio be take reduce sub-seguent reisa s to preven recurrenc f exceedi the above li and includ the schedul for achie g confo a with the a ve s
limits.
is Special enort, as fined in CFR 20.405c 11
./
inclu an analysis hat esti s tne rad ion exposure, dose) to a ME OF THE PU C from ur ius fuel c e sources, i uding all luont pathw s and dir radiatio for the cale r year that includes th<
elease(s) overed by is report.
I shall also e scribe
's af rad ion and c entrations o adioactive erial involv and the use of the xposure level or concentra ns.
If j
the
' imated (s) excee the above li s, and if t lease co ition res ting in vi ation of 40 C Part 190 has t already en corre d, the 5 41 Report sh include a st for a va ance in cordance the provisi s of 40 CFR P 190.
Subst 1
of th port is idered a ti y request, a a variance i gra ed untti s f action on request is late.
b.
e provist of Specific on 3. 0. 3 a re t applicable 50 EILLANCE R
! REPENTS 1
4.11.4.
C aulative d e contributto from liquid d gaseous efflue shall be 6 ermined in ac dance with Sp fications 4.
.1.2, 4.11.2.2, d 4.11.2.3, a
in accordance th the method ogy and par ers in the 00CM.
4.11.4.2 C ative dose ce ributions fr direct radiatto ros the units 2
! including tside storage nts, etc. sn De cetermined accordance with
.the met ology and par ters in the CM.
This reovir nt is applicaDie only der conditions et forta in ecification 3.11
, ACTION a.
HOPE CREEK
/,
3/4 11-20 Amend:nent No. g,,
l
3/4.12 4AD!0 LOGICAL EWIR000 ENTAL IGN!730 3/4.12.1 S
/
I LIMIT!8ECdt?!0mPoa0 7 ton 3.
The radio ital envi ntal sent ing prese shall be enducted a specified in ele 3.12.
APPLICA8!LI : At all
- mes, g:
a.
With radiologic envi 1 sonitor ng progr
, t being ce tad as spec ted in Te 3.12.1*1 apppare sutoittot/
ission, in Annus) A telegical avtronese Operating rt utred by ifi. tion 7, a scripti f the rease for not conewc the p a recer e.
and lans for p enting j
t.
With level of edi IV y as the uit of plan affluents 1 an nvironmenta i
ius at a ified lac ion exceedi mporti e
le 3.12.
when avera over any lenda h,
quarter, p e
it to emoission v in 30 days pursuar to Specif
, a Spect Report the dentifies t.
cause(s) for ese di att(s) fines the rrective ac ens to be-taae steactive fluenta se t the se tal annual se to a 0F THE LIC is les the cal r year 11 ts Specif1ca ens 3.11.
, 3.11.2.2 and 3.11.2.3 when sere an one of the eatenuc11 s in Tale
.1 2 are ted in t sampli is, th report she he semit if:
concentrar en (11 concentrati (25
, * *, g, g reperti evel (h) reporting I el (2D when redi 11 des e than these Tele 3.
are detecte and j
are the sult of p t affluenta.
is report 11 he sweet se if l the tal esses to A (A 0F LIC free reste-aus des is to or greate than the oneer year 11 ts of ificati 3.11.1.2, 3.
.2, and 3
.2.3.
This rt is not l trod if esasured 1 el of radt twity sea the result eti plant off ts; homever in such an
, the c ition shall be rese and described n the Redfelegica tavironmental Oper ng Report pu t to fication 6.9
.6.
c.
th alik er fre leafy v 1e sample vallele free e or more of the e locati required ele 3.12.1-1, t ntity spectfic lac tons for ining rep 1 t samples and ed taes to '
the restel ital envi ntal sent ring progree vi 30 asys.
"The methodel used te stimate the tantial annual e to a MEMER @ DI PUBLIC s De indi se in this rt.
M0Pt CattK 1/4 12-1
i 8
9 I
PAGES 3 / 4 12-2 THROUGH 12-12 INTENTIONALLY BLANK HOPE CREEK AMENDMENT NO.
+
RASIof rwtIrant-ENVT at teost2 TORY W LIMITIss ON FOR OPERAT (Continu (Continued The ific loca one from whi samples were available then Lated f he monitor program. Fu ant to Spec ication
.9.1.8, i
tify the ca of the unava 111ty of a pies and identif new loca n(s) for obte ng replac t samples in the Radioacti filuent Role Report pur ant to l
8 ification 4
.1.8 and also
- de in the et a revi igure(er able for the r* Aecti he new loca n(e).
d.
The siens of Spee ca 3.0.
not appi le.
l SURvBI CB REQUI
....p.
4.12.1 The ra logical and ntal moni ing samples e 1 be collected pursuant t able 3.12.1-rom the e ic locations en in the tabl nd figure (
in the 00cM, shall be lysed pursuan o the requir a of Tabl
.12.1-1 and detection 111 ties r red by Table 4.
.1-1.
(
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,mmtw[12,11, cone dg,
]l
,,. --w,cs (1) Specific par ers of distane and direction ector from t centerline of one rea r, and additio description era pertinent shall be provided Lr each and eve sample locati in Table 3.1.1-1 in a table and fi e(s) in the
. Refer to
-0133, "Pr ation of Radi ogical Effluent echnical Speci cations for N lear Power F1 s,*
oc ber 1978, and Radiological essent Br Teeknical Post on, ision 1, Nov r 1979. Deviat ne are permi from the r red k,
sampling sched e if specimens unohtainab due to hasardo conditions, sonal unavail lity, malfun on of automati campling ipment and et legitimate sons. If spec e are unobts le due to samp equipment function, ove effort shal made complete cor tve action pr r to the end of he nort s ing All deviatto from the s ing schedule e 1 be docume ed in per t
Annual Radiol cal Environne al Operating rt pursuant o pecification 6.
.1.6.
It is r ised that, a ines, it ma not be possible or pr icable to co inue to obtain amples of t media of choice at t most desired stion or time. a these ins ances suitabis specific ernative modi and 1 ations y be chosen or the particul pathway n question and pyropri e sub itutions na within 30 days the 1ological Envi amonta ito ng Program von in the 00CN.
Pur ant to specifi tion 6. 4 e
t in the Radioactive 9
I luont Release port do nta on for a ch go in the 00CM i luding revised figur (s) and f
the 00CM r lecting the new ocation(s) with support info ni ntifying t cause of the un a11 ability of samples r th wa justify the selection the new location for a samples.
(2) One o more inst e, such as pressurised ibn amber, for suring an ecording dose ate continu sly may be used' place of, o in ition to, int rating des ers. For the ses of thi, abis, a hermoluminose t dostmoto (TLD) is conside to be one osphor; two or more phos are in a et are consider as two or e dosimeters.
Film badge shall not used as dosimo e for measur g direct radiatio. The frequ cy of analysis -
readout for systems wi depend pon the e acteristics of a specific ey se used and ould be a octed to sin optimum dos information w h minimal fa ng.
(3) rborne culate sample ters shall analysed for a beta radioacti y 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or re after samp ng td allow f raden and thorse ughter decay. I gross beta a vity in air iculate sample is ter than 10 t the yearly of control les, gamma i
is analysis e 1 be perto on the indiv ai samples.
(4) amma isotopic lysis means identificat n and quantific ton of gamma-amitti radionuclides t may be at ibutable to the ffluents from the f lity.
(5)
The *u tream sample" 11 he tahan a distance d significant inf1 nce of the dio
. The
- stream" sample all be taken an an at beyond but the mining no. 'Dyetream" s les in an estuary at be takee f enough upstr to be beyond t plant influence. Salt water shall sampled only the receit stor is utilised for recreationa activities.
[
HOPE CREIE
/4 12-7 Amenee.t
r
/
TA8LE 3.12.1 7 fContinued)
T NOTATION (6)A coepo sample is in which the antity (all t) of liquid led is p rtional to quantity of f ing ligeid d in which t thod of ampling emplo d results in pecimen that representati of the k
quid flow.
this program osite samp1 aliquets shai'.a collected at tim's int als that are short rela ve to the camp tting prio in order assure obtai a represen (we sample.
(7)Gro ter samples all be taken n this sourc s tapped for rinking irrigation pu.ses in areas re hydrau e gradient o recharge properties a uttable for temi n.
(8)The dose 11 be calcu o
max organ and group, usin the logy and ame r the (9) harvest occur mor ronce year, sampli shall be perfo d during each discrete rves.
f ha t occurs con nuously, sampli shall be monthly.
ention sha 1 be aid to inci samples of t rous and root food pr ts.
t J
i pis P AG-E t NrTEra Tt O N ALLY E*^
I l
HOPE CREEK 3/4 12-8
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HOPE CREEK 3/4 12-10 Amendment No 1
gts F A G1E i f4 TliE:.N T1 CW AL LM B L. W N TAh4.12.1-1 ntinued TA8LE TATIONS (1)This I st does no mean that ly these lides at to be e sidered.
Othe peaks that re identif ble, tog er with ose of e above 1
nu ides, shall 150 be an yzed and ported i he Annu Radiologic E ironmental perating R ort purs nt to Sp ficatio
.9 1.6.
( Required action cap (11 ties f thermol inescen dosimeters u d for environne al measu nts shal be in ace nce w h the rec ndations of Regul ory Guide
.13.
(3)The L is define, for pur ses of th se speci cations, as he smalle conc ntration of radioact e sa eria in a s le that will ield a n co t, above s tem back ound the will be tected wit 95% proba lity w' h only 5% robabili of f I conclu ng that a bl k observa ion opresents "real" s nal./
For a par icular sur%y stes, w ch may inci e radioch ical separat n:
.66 s LLD =
b V V 2.22 Y
exp(-
)
+
Where:
LD is the ' a prior lower limit f detecti n as define above, as picocur es per ft mass or
- lume, s
is e stand d deviation f the bac round count'ng rate or of tNec nting r te of a blan minu e, sample as appropriate as counts er E s the unting effi ency, as unts per di ntegratio,
V is t sample siz in units mass or vo 2.2 is the numbe of disin grations per minute pe picoeurie is the fract nel radi emical yiel, when ap icable, A is the ra osctive d cay constant or the p ticular ra onuclide
(,sec-1),
d at for nvironnen I samples is he elaps time betw en sample colle ion, or e of the L e collect n period, nd time of cou ing (sec) ical valv s of E. V, Y and at sh Id be use in the calculation.
t mor recev
p
_A6LE 4.12.1-1 A ontinued)
TAB TATIONS It shoul e recognized at the LLD
- de ined as a priori (bef e the fa limit repres ting the c bili of a asurement syst and
/
not an a posteri (after th fact t
r a particular asurement.
A yses shall De erformed i uch uner hat the stated Ds will be chieved under utine cond onsy' as nally backgrou luctuations unavoidable 11 sampie zes pre nce of interferi
- nuclides, other unco rollable.c umst render these LL unachievabl In such ses, the e tributi ors shall be ide fled and de ribed in th nnual Radi ogical Envir ntal Operating eport pursua to Spe fication 6
.1. 6.
1 TK i S
' Pacs _
1 t4 TEN TION A.LLY 16tw K e
HOPE CREEK 3/4 12-12
1 maararmre me muyr m at rey g me L,e. Te. D 3/4.12.2 r_ r r_-
,7 LIMITING CONDIT20s FOR ERATION 9
3.12.2 A land eeneus shall conducted and e identify withi distance of 8 (5 miles) the ation in each o the 16 meteoro1 cal a
sectorg of nearest milk Anal,tp) prod nearest asidence and t garden greater than 50 arest (600 ft broad leaf ation.
47 merttTT At a times.
j/
a.
W a land c'ene identifying a 1 ation(s) that yi de a alculas or se commitment stor than the va es currently bei at a specification
.11.2.3, identif he new loc i the nort Radios we "Iffluen N e e Report, l
~~
pur to pecifica..on 6.9
.7.
b.
With a and use conova i-nt.fying a locat n(s) that yist a
cal ated does or dos commitment (via same esposu pathway) 2 greater than at location from w ch samples are trently ing obtained in ecordance with 3 cification 3.1
, add the a locationte) to e radiological e ironmental son ering program within 30 da The sampling cationte), emel ing the conte station 1 tion, having the owest calculat dose or does
~
commitee (s), via the o exposure pathw, may be dele from this itoring program fter october 31 f the year in ich thie lan use census was ucted. Purou to specifica on 6.9.1.8, i atify the new 1 ation(e) in the at Radioactiv Iffluent l!
lease Report a aloe Laclude i the report a r toed figur e) and teble for occM rerlect the new loca n(e).
c.
The provi one of specific ion 3.0.3 are t applicabl.
SURVI!LIAN
.IREMEhTs 4.12 19e land use nous shall be neucted dur the growing soon at le t osos per 12 ha using that formation t t will provide best seulte,'eush as
. a door-to-door rvey, viou survey, seria eurvey, or by consulting loc agriculture au rittee.
results of the and use census shall be lac in the Annu Radiologic Environmental rating Report purevant t specification 6
.1.6.
- Br d leaf vegetati campling o t least three fferent kinde o ation may be rformed at SITE in each of two different d os sectore th the highest edicted D/9s in Lou of the garden us.
Specif ations for b leaf vegetation ampling in Table 3
.1-1, Part
.c.,
shall be f owed, includ lyeLe of control lee.
NOFE CREEK 3/4 12*13 A"**d"*"" "**
RADIOLOGICAL ENv!Ross4 ENTAL MONITORING
$hbb C=:I'S ?"0C:=
3/4.12.3 LIMITINGCONDITIONF0/0PERATION
[
[
i 3.12.3 Anal s shall be p ormed on rad active mater s supplied s part of an Inte aboratory C rison Program hat has been rowed my Commissi APP ASILITY: At I times.
ION:
a, th analyses n being r 'o as requi above, rope the corrective ac ons t a revent a re rence to the osaistion in the Annu Rad Environment operating Re et pursuant to Specif ati b.
The visions o ocificatica
.3 are not licable.
SURVEIL E REQUIR 5
/
/
4
.3 The In riaboratory C arison Progr shall be ribed in th 00CM.
summary of he results o ined as part the above utred Inte laborato onparison Pr as shall be i luded in the nual Radio gical Enviro ntal Operatin sport pursua to Specifica on 6.9.1.6.
N
(
S D 2 8 808 [ j Amendment no.
HOPE CREEK 3/4 12-14
ADMINISTRATIVE COtrTROLS j
6.8.4.f Primary containment Leakane Rate Testina Procram
\\
A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54 (o) and 10CFR50, Appendix J, Option 5, as modified by approvgd exeniptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.153,
- Performance-Based Containment Leak-Test Program *, dated September 1995.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P.,
is 48,1 psig.
The maximaan all.eable primary containment leakage rate, 4, at P.,
shall be 0.5% of primary contain= ant air weight per day.
Leakage Rate Acceptance criteria ares Primary containment leakage rate acceptance criterion is less a.
than or equal to 1.0 4 During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 4 for Type 3 and Type C tests and less than or equal to 0.75 4 for Type A testas b.
Air lock testing acceptance criteria are:
1) overall air lock leakage rate is less than or equal to 0.05 4 when tested at greater than or equal to P.,
2)
Door seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater than or equal to 10.0 psig.
The provisions of Specification 4.0.2 do not apply to the test frequeneses specstted in the Primary Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the..PIlmary Containment Leakage Rate Testing Program.
$H SC27 C-1 I
l HOPE CREEK 6-16b Amendment No.1(%
i I
s l
ADMINISTRATIVE CONTROLS J N 5 e72 7 C
o.........o2.=.........o......................................................
PROCEDURES AND PROGRAMS (Continued) 6.8.4.g.
Radioactive Effluent Controls Program A program shall be provided, conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER (S) OF THE PUBLIC from radioactive effluents as low as reaso,nably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3' shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following
. elements:
- 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
- 2) Limitations on the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,
- 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,
- 4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,
- 5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and calendar year in accordance with the methodology and current parameters in the ODCM at least every 31 days,
- 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the-appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conf orming to Appendix I to 10 CFR 50,
- 7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B.
Table II, Column 1, HOPE CREEK 6 16e Amendment No.
8 I
b M b:
ADMINISTRATIVE CONTROLS-PROCEDURES AND PROGRAMS (Continued) i 6.8.4.g.
Radioactive Effluent Controls Program l
l
- 8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I_to 10
.CFR Part 50,
- 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131 Iodine-133, tritium, and all radioactive nuclides in particulate form with half-lives greater than 8 days in gaseous affluents released from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
- 10) Limitations on venting and purging of the containment through the Reactor Building Ventilation System, Hardened Torus Vent, i
or the FRVS to maintain releases as low as reasonably achievable, and
- 11) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
I h.
Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways. and (2) verification of the accuracy of the effluents m:nitoring program and modeling of the environmental exposure pathways.
The program shall (1) be contained in the ODCM. (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling. analysis, and reporting of radiation and radionuelades in the environment in accordance with the methodology and parameters an the ODCM,
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
- 3) Participation in an :nterlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radicartsve materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
llOPE CREEK 6 l hJ Amendment No.
ADMINISTRATIVE CONTROLS
[ describe maintenance), waste processinginse ce g
dosimeter, themoluminescent dosimeter (
and refueling).
The dose j
measurements.
Small exposures totalling less than 20% of the indiv-osimeter idual total dose need not be accounted for.
be assigned to specific major work functions;80 In the aggregate at least ould and b.
Documentation all challenges to main steamline safety / relief valves.
ANNUAL RADIOLOGICAL ENVIR000 ENTAL DPERATING REPORT 6
9 ( op.9.1.63 Routine r logical env neontal rating rting cover the eration of the it durina t P previous alendar ye shall be s tted f
prior to May f each year.
he init report s I be submit prior to May 1 of t ear followi initial iticality.
The a 1 radiologi enviro ntal opera reports s 1 include s
- ries, in rotations, en anal s of tre of the resu of tha radio ical tronmental s e111ance tivities the report riod, includ parison with rati I studies rational a com-and previo enviro I survei ne reports trols as nd an asse(s riste),
observe spects of plant rati on environment.
he reports 11 l
of the also lude the suits of u
s required by pecification
.12.2.
If arsful off ts or evi eo i
v ible damage detected b he
- nitoring, report 11 pm analysis of problem a a planned course of ction to a evia i
len.
The nual radio ica y ntal operat reports s 1 include s rized a
tabulated sults in format of Re atory Gui
.8, December 5 of all adiologica environments samples tak during the rt period, viations from the ling propda identified n Technical ification :
.1 shall be report In the e it that some sults are available fo 'nclusion wit the port the port shall submitted ng and expla ng the rsaso f
the r f ossible
., results.
insing da hall be subei as soon as supplementa report.
i The re s shall al include t o11owing:
radi ogical envi ntal moni ring program; a ry descrip n of the
/
least two 1 le naps, one e
ring sampli locations er the SITE ARY, and a s nd covering the re distant ations, a kayed to a t e giving dista s and direction from one ctor; and results of 1 nsee participa on in the Inter 1 o r-atory C arison Pro am, as require y Specificati 3.12.3.
T port shal also include results of s fic activity a sis in ich the pr ry coolant ex the limits f Specification
.4.5.
The following formation sha be included:
Reactor power tory starting 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the f st sample in wh the limit was caeded; (2) Results of t last isotopic lysis for rad odine performed rior to exceeding the n/
1 t, results of lysis while li t was exceeded results of one analysis T
HOPE CREEK 6-18 Amendment No. W
ADMINISTRATIVE CONTROLS
' aman [were m' m-
- = -e n C, fac :-
l (cont ued) afte he radiot activity a redue to an limit, a h result s
14 include to and time sampli and I iotodine e centrations;
) clean-up ystem flow h tory at ing 4 e prior to first sample in which limit was er f he I-131 co entration and o other r Loiodine i co ra i
crocuries gram as a func on of t for the dur ion of t til ctivity the steady-stat le 13 and (5) time dur ten i
specific a tvity of the pr ry laat ese the rad' odine lieb mantamMrva myyrivene met.m.. nw
[5GM s.g.1.9[madios release res cover the operation the unit shall g
be submitted May 1 of ch year and accordance with requirements 10CFR50.36a f
N The r etive'of uent reloae. a rt shall inclu a summary of th
()
quan ties of ra oactive liquid gaseous effl to and solid wa e re ased from unit as out1 in Pengulato Guide 1.21. " Mea ring,
- atuating, Reporting Ra oactiv y la so d wastes and Re1 see of Radioacti Materials in L id and soous.ffluents from Li t-Water-cool Nuclear r Plants,"
ision 1,j 1
4, with data e ised on a quart ly basis follow g the fosthbt of prendia 3 thereo
[
T radioactive of uent to re et shall include annual summa of
('l ourly esteorol cal dat e
over the provi e year. This ual l
summary may be ither to of an hour-by-r listing of w d speed, wind directi, and a er stability, and ipitation (i osasured) magnetic t
, or in t to of joint fc;;:
i distribution of wind e wind dir ion, and atmos eric stability.
report shall nelude an lI asses nt of the radia on doses due to radioactive guld and g oous eff1 ats released fr the unit or sta on during the tous cal dar year.
Th report shall al include an asse at of the ra ation dose from 1,
dioactive liqui and gaseous effl nts to MEMBERS TER PUBLZ due to the activities Lasi the SITS SOUND (Figure 5.1.1-during t report port All assumptio used La making se assessments i.e.,
spec ic activity esposure t and location, e 11 he included these re
- s. The his rical annual a age meteoroloTY the meteorolog al conditi e concurren* with the t of release of r osctive materia in gaseou effluents (
date by sampling squency and esa t) a 1 he used to det iag the g pathway doses. he asses t of radiati doses shat perforund La ac with the SITE DOSE
Radioactive I luont melaase rt shall tify those adiological i
environmental e le parameters locat ce it is possible practicable t oostinue to okt samples e the media of boice at t most desired loc les or time. It ition, t cause of the va11abili of samples f the pathway be new loc ion (s) for mining rep 1.ement samples bould be identif
. The should al include a r toed figur s) and table (s) e the CDCM flecting t locatio s).
(
t ha- -t o/ (
. 1,
l ApurwIsTRATIVE CONTROLS e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
.-1M mm_/...... -m/.e (continu ee..es...........,
n
)
The adioactiv effluent re ase report all also i ude an a esament r Lation do e to the 11 ly most a sed MEMBER TER PUBL from re ter eleases other near uranium f i cycle sou es (inclu doses com primary fluent pat ye and dir radiation for the tous 12 cono ve months show conf ce with CFR 190, avironne a1 Radi ion Protect a Standar ior Nuclear Oper ion. Acc able math to calculat he dose e tribution f liquid gaseous ffluents ar von in tory Gui 1.109, Rev.
The radi etive off at release et shal include t following info Lon for class of id waste defined 10 CFR 61 shipped offs during report ye ads a.
tainer vol b.
otal curie antit ify whethe determined esasur or estimate),
Princi radi (specify ther dote ined by me r
ramentor[
est e),
d.
of w
(
g.,
spent r in, compa dry waste, aporator i
ton.),
e.
of con iner (e.g.,
, Type A Type e, quantity),
l f.
Solidific ton agent (
.g., cement urea formal hyde).
Th radioactive ffluent rei se report 11 include nylanned to asas from l
e site to t UNRESTRI AREA of r loactive ma rials is gas us and liquid effl nts on a qu erly basi.
The rad active off1 at release oport shall clude any e es to the l
PROCI CONTROL P RAM (PCF),
FFSITE DOSE TION AL (ODCM) or rad active wast systems na during the sporting per MONTEI.Y OPERATING REDORTS 6.9.1.8 Routine reports of operattag statistics and shutdown esperience shall be submitted on a monthly basis to the U.S. Buslaar Refulatory Commission,e Document Control Desk, Washington, D.C. 20555, with a copy to the UsNRC Administrator, Region 1, no later than the 15th of each month following the calendar month covered by the report.
coma orEnATInn Limits REpont 6.9.1.9 Core c y attag limits shall be established and documented in the PSE&G generated OCRE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technicai specifications:
3/4.2.1 AVERAGE PLARAR LINEAR REAT newennTION RATE 3/4.2.3 KINIMUN CRITICAL POWER RATIO 3/4.2.4 LINEAR IIA! GENERATION RATE Y
pors CRazz 6-20 atNo.N 4
LCR H99-02 INSERT D 6.9.1.6 The Annual Radiological Environmental Operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shallinclude sumrnaries, interpretations, and analysis of trends of results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the'ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix l to10 CFR Part 50.
lNSERT E 6.9.1.7 The Annual radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
4 i
I 4
ADM8N85TRAT8VE ColffRO7.3 PECORD RCENTION (Continued) h.
Records of annual physical. inventory of all sealed source mater:
record.
41 Of 6.10.3 The following records shall be retained for the duration of the unt:
operating L1:ense:
Records and drawing -hanges reflecting unit design modifica:: ens ade ::
a.
systems and equipme.it described in the Final Safety Analysis Repert.
b.
Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories, Records of radiation exposure for all individuals entering ractat :n c.
control areas.
d.
Records of gaseous and 11guld radioactive material released to the environs.
e.
Records of transient or operational cycles for tnose unit components ident !ted in Table 5.7.1-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h Records of inservice inspections performed pursuant to these Te:.1:a; Spec ficati:ns Records =f quality assurance activicles required by the Ouali:y 1
Assurance Program Ree:rds of reviews perf ormed f or changes made to procedures or equ:; en:
cr reviews of tests and experiments pursuant to 10 CFR 50 59
/')
k Records of SCRC meetings and activities of the Nuclear Review Beard sn:
l ac:av:::es of its predecessor. the Offsite Safety Review 0 SRI staff l
Ree:rds =f the snubber servtee lif e mons:= ring pursuant :o Te:n..;:a.
Spec ft:stion 4 ? 5 Reccrds of analyses requ: red by sne rad: log :al environmen:a; m
men: tor ng program wht:h would perma: eval.a::en of :ne ac:ura:. :.! -.e ana.yses at a later date This should include pr=cedures e!!e::
.e a:
spect!1ed times and ;A re: rds snowing :na: :nese procedures.ere
- 3. M 5 f 1;:.ed F
n.
4.
- A.*AT*?N FPI?t""!!N FPMPM 1
i ;; ; Pr:ted.res f:r persennel rad:stion protec:Lon shall be prepared ::nsisten
- :n :ne require ents f 10 0FR Par: :: and snall be approved, ma int a a..e d. an:
a1..ered :o f:r a;'. :perattens :nv=1vang pers:nnel rad:ation exposure.
HOPE CREEK 6 ::
Amendment N:.
l
LCR H99-02 INSERT F Records of reviews performed for changes made to the OFFSITE DOSE n.
CALCULATIONAL MANUAL and the PROCESS CONTROL PROGRAM.
)
ADMINISTRATIVE CONTROLS eseoeseosesseesseeessessasseseessesseessessessesseesseesses 6 13 PROCESS CONTROL PROGRAM fPCP)
Aall be ap veo by th Consnission rior to lementati
{6.13.1 Tne rcP N
6.13.2 Lie see inicia changes t the PCP:
Shall be itted to e conunisui in the dioactive fluent Releas eport for e period i hich the hange(s) w made. Thi s
- tal shall e tain Sufficie ly detaile info K
to totally upport the ratio e for the age benefit o additional sup ementa} inf ti b.
A eterminatio tha nge did no reduce the erall onformance th e ied waste oduct to exi ing crater for solid stes:
Documen ion of th act that t change has en reviewed nd found cceptable b the SORC.
2.
Shall come effee ve upon rev' w and accept ce by the 5 C.
~
6.14 0FFSITE DOSE CALCUI.ATION MANUAL fODCM) 14.1 4-vocM shall approveo me w-is s a prior to i lamentation.
6.14 Licensee i tasted chan s to the CDCM-1.
Shal be submatted o the Co
~ on in the R loactive Effl ent
/
Re ase Report f the pert which the e nge(s) was e.
This attal shal contain:
a.
Suffic ently det i t nf err at ion totally supp rt the rati ale for the nge without nefit of add' lonal or su lemental info tion.
Inf tion submit d should cor ist a package of hose pages o the CDCM to changed wit each page numbered d provided th an approva and date be.
together wit appropriate alyses or ev uations Just fying the changeIs):
b.
A determ ation that e change will et reduce th accuracy o reliab ity of dose alculations or etpoint dete ination:
.d c.
Docu ntation of t fact that th change has n reviewed and fc acceptable y the 50RC.
2.
Sha become effe ave upon rev1e and acceptan by the SC C.
Ud O i U b o# SMANCES *O Pr!!AM!"E *_!?**b OASECUS AND SCtID WASTE TPEATVEF f
S Y.[TEws 5. Licensee
- 1. taated ma;or :P nges to the r loactive w ste system
,atd. gaseou and solidt f
Sha be reported to tne Comiss10, in the UFS for the p tod in w.ch the evaluatt was re.lewed y 50RC.
"" e discuss a of each
.nange snall :en* in cps :7.ctr.
- "S**"
t
LCR H99-02 INSERT G 6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
Shall be documented and records of reviews performed shall be retained as a.
required by Specification 6.10.3.n. This documentation shall contain:
(1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and (2)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effec'ivt after review and acceptance by the SORC and the approval of the P Int General Manager.
INSERT H 6.14 OFFSITE DOSE CALCULATIONAL MANAUAL (ODCM)
Changes to'the ODCM:
Shall be documented and records of reviews performed shall be retained as a.
required by Specification 6.10.3.n. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and
- 2) A determination that the. change will maintain the level of radioactive effluent control required by 10 CFR 20.106. 40 CFR Part 190,10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calcuk'tions.
b.
Shall become effective after review and acceptance ny the SORC and the approval of the Plant General Manager Shall be submitted to the Commission n the form of a complete, legible copy of c.
the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the page that was changed, and shallindicate the date (e.g., month / year) the change was implemented.
1 ADMINISf IVE CONT MMOR HANGES TO SIDACTI LIQUID.
SE005 SOLID ASTE EATMENT!
5Y3TEMS (Contin
)
f
/
a.
As of the valua?,io that 1 d to t deterni ation t t the c nge coul be made acco ance w h 10 CF 50.59; Suf icient iled in mati to to ly sup rt the ason f
the c witho benef of a tional suppi ntal formati c.
A data ed descr tion o the eq paent, non and proce es invol ed and he inte faces wi other lant sy ens; d.
An valuatio of the change, ich s the edicted leases o radios iv ma rials in iquid gaseo s ffluents and/or er f solid aste t differ from those p viouslyprp i d in the icense 11 cat n and ame ts the e.
An aluati o t
- change, ich s the acted sax m
a osures f
ual in t unres icted a and to %
neral jo that dif er f those p viously e insted in the plicatio and nts reto; f
Ac er s f the predicted r leases radioac ve sat ials, liquid d gase s eff1 nts and i solid wast,
the act I releas for tpe perio prior to n the anges to be e de; g.
An est te of t expos re to ant opera ng personn as a resu of the e ange; d
h.
Do umentatio of the fact tha the ch was rev d and und accep le by the 504C.
factiva/
/
Sk 1 become upon r view an acceptance y the 50R.
/
7p,s g u a /iv w n ~ w y
~B w K
~
HOPE CREEK 6-25 AmendeentNo.g
ins"91 4 '*17!!N SAsts
.eeeeeeeeeeeeeeeeeeeeeeeee..........,,,,,,,,,,,,,,,,,,,,,_,_
TM?**R!MS IMS?RtHEw"1 !ON 'Contanuo1) 3'e 3 -a the tssuance o$ the Full powetThe matortal* ortstnally contained in Section 3/4.3.7 license.
However, to maintain numerical conttnutty between'the succeeding secttons and entstang station procedural roterences to those Tecantcal spectfatattons secttons 3/4.3.7.8 has been ententtonally left blank.
3/4 1 9 9 LScar.DAAT SETrc=!cy gyg ggs THIS SECTION DELETED 1/4 1 7 is
- Arteac-!*tt treu!m ErrttTw=.sowitearwe tws-atr.,z;iTAT!ew
"'~~
TP radtoa ave it d efflu nitorIng inst neat a is pr ided to mont* r and c trol. 4 applica e.
esses e radios ive mat tais tn 11 ad ef f1-nts du g actua or pWh tal rol ses of gutd of uents.
. arm /t; potnes or tTese nat a shall cal sted an d3 us ted accord ce with he met i
e paramet s is t ODcM to asure t the ala trip wt occur p or o coeding e list of to part 20 The OP ILI.
nd use o this 1 trument on is istan with the quarem es of Oe al Des cette a 60.
and 64 f Appendt A to 10 C art 5
? 4 3 11 ur:0Ac !vr cAsroes trritTwT neewf-earuc !wstntr,.ruiTAT!cw m-(~
Th radtea ve gaseo eff1 t monito ng inst tation a provided to mor tar an control.
s appl able. th releases o radioacts matertal
.a seous fluents rang a al or ents/1rol es of ga ous afflu ts.
T ala - trip set nts to these an rume a
1 he cal ated and d;ust in accor ce wt the met i
rameters a the o This
-til asure th larm/t p will o ur exceeding he lamats f 10 crt Fa 23.
Th' inst ntatten so a provtsio for monte tag and entro11tn the cc entratton of 11y amplos e gas sta res in t
-atn :en neer o gas treat at s a
The CP LITY and e of ths
.nste" ntatto ts coasts t wath e requtreme s of Gene 1 Destgn riterta 63.
and of Ap A to 10 rt part 50 x
,)
D 6 L.G 6 c::.C Amendment No.I Hept : REEK B 3/4 3*6
r 1
3/4.11 RADI0 ACTIVE EFFLUENTS
_ BASES
$Gwn-.O 3/4.11.1i LIQUID EFFLUENT)'
[3/4.11.11 CONCENTRA This speciff tion is pr vided to e ure that he concen ationof radioactive sat fals role ed in liqu waste e luents to RESTRICTED EAS will be less an the co entration vois spe fled in 10 FR Part 20, ppen-dix B, Tabl I, Col This 1 itation ov des ad ional assur cethat{
f the level f radica ve materi s in bod sa water n UNRESTRIC AREAS will re t in exp res withi (1) the etio I.A si l
}
dix I 0 CFR Par 50, to a M ER 0F T (2) gn objec ves of Ap n-Part 0.106(e) the popu tion.
T con ra on limit for dissolved the li ts of 10 R
en ained nob gases is ased upo he a on that Xe-is the ntrol-r ng radict tope and s MPC in r(
on) was conv ted to a equival t
concentr on in wat using th me cribed in I rnationa Commiss n on Radi ogical Pr action (I P ion 2.
The requir d detecti capabi es for radio.tive sat ials in iquid w te sample are tabul ed in te of the lowe limits o detecti (LL0s),
etailed d cussion o the LLO, d other date ion limi can be ound in
- Currie, A., "L Limit of etection:
0 inition Elabor ion of a Propos Position or Radiot ical Effluen and Envir neental asuremen i
NUREG/CR-4007 ( ptember 1954), and in t HASL Pr edures ual,_HASL_ 00 bre/1sedannu i %.
/
e S:tELc nov 3/4.11.1.2fDUIE
/
This specif ation is prov'ded to i enent t requirene s of Sections II.A.
I.A. and IV.
of Appen x I, 10 R Part 50.
The Limi ng Condition for paration imp nts th guides s forth in ection II of Appendix I.
The ACTION s tenents ovide th required o rating f1 xibility and at t same time i esent th guifess forth in etion IV.
of Appen-dix !
assure that releas of r di etive aster al in lig d effluent to U STRICTE0 ARE will be inkith"w as is rea onably ac evable."
so, ept for fresh water s es with or supplies hat can potentia 11 octed by pla operati s, t re' reasonabl assurance hat the op ation of the facili will no resul adlonucli concentra ons in the inished drinking we r that er in e e of the req esents of 40 CFR Part 41.
The dose calc ation as parameters n the 00 implement e require-ments i Section ndix I that onforinanc with the g des of Appen x I be s lational p edures be d on models nd data, su tha the actu expos f a MEMER 0 THE PUBL through ap opriate pat ays
)
in/unlikely be subs ntially unde stimated.
The equatio s specified n the i
,6DCM for c culating doses due o the act I release r es of radio tive material in liqui effluents ar consisten with the se odology prov ded in Regula ry Guide
.109, "Calcul ion of wal Doses to n from Rcu ne Rele es of Re or Effluents or the Pu se of Eval ting Compli ce with 10 FR Par.t 5, Appendix I," Revision, October 197 and Regulat Guide 1.113
" stimatin quatic Otsper ton of Eff vents from A idental and outine Reactor Releases r the Purpos of Implene ing Appendi I," April 19 L
HOPE CREEK 8 3/4 11-1
RADI0 ACTIVE EFFLUENTS BASES Wm4 Tr=O 3/4.11.1.3{LIdUIDR46WASTEIREATMENTSdTEM
]
The 0 RA81L Y of t e liquid r to t eatment s tem ens es that th system w 1 be a allabl for use wh new i uid efflu ts req re treatmen
{
prior their elease to the env o The requi ement t t the appr riate porti s of t s sys be used, en e fied, pr ides as rance that he rol ses of edioac ve matcri si id efflue s will kept "as w as is easona y ach vable." T ss cation i lesents he requir nts of neral sign C terion 60 f A to 10 FR Part 0 and the sign objecti give in Section I pendix I 10 CFR art 50. T specified limit govern the use f ste porti ns of t liquid ra este treat nt syst were pecified a a suit fractio of the se design jectives s for h in 5 tion II.A Appendi I, 10 CF Part 50 for liquid ffluents.
t 3/4.11.1.4 LIQUID HOLOUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix 8, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASE0US EFFLUENTS ruc i.=. reso 3/4.11.2.1 ! 00SE RATE pecift ation is rovided to nsure that e dose any time and beyon the SITE ARY rom gaseous ffluents f all un s on the s te will be thin the nnual do limits of 0 CFR Part to UNRE RICTED AR 5.
The an al dose sita are doses a ociated wit the conc ntrations 10 CFR P tt 20, Ap ndix B, able II, Co n
Thes limits p ovide reas able ssurance t radi ctive mater al d arggd in gase s affluent will not result i the expo re of a ME ER EP LIC in a UNRESTRICT
- AREA, either thin or utside the TE RY to annua average e centration exceed ng the 1 its specifi d in ndi
- 8. Table II of 10 CF Part 20 (10 R Part 2.106(b)).
Fr 0F THE PUBL who may a times be thin the ITE SOUN ARY, the oc any th MDSER THE PU8LI will usua y be su ficienti low to c satt r an increase n the atmo pheric dif usion ctor abo that for S
U RY.
Ex les of cal lations f such EMBERS 0 THE PUBLIC wit t e ap opriate cupancy fa rs, shal be given in the CM.
The s cifteu eleape rate 11 ts restric, at all mes, the
)
i corres ndtng g and beta dos 4 rates ab e backgrou d to a ER OF THE l
PUBLI at or beyo theSITE89dNDARYto ess than or equal to 0 meems/ year j
to total bo or to less pnan or og, I to 3000 ess/ year o the skin.
]
1 HOPE CREEK 8 3/4 11-2
RADIDACTIVE EFFLUENTS BASES
_00SE RATE (Co tinued)
These rei se rate li its also r trict, at 1 times, he corre encing thyroid ose rate a ve backgro d to y chi d via th inhalatic pathway t less t norequalto1500 mees / year.g The requir d detectio capabi for rad active a erials in aseous
{w te samples re tabulat in te f the 1 r limits detectio (LL0s).
etailed dis ssion of L
ther det tion limi s can be und in Currie, L.
., " Lower mit ction:
D inition d Elabora on of a Proposed osition for adio Effluen and Envir neental NUREG/C 4007 (Sept er 1984) and in th NASL Pro dures Man al, HASL-O surement,"
t(revis annually) 9,5 tJ!E ren
/n 3/4.11.2.2 1005F - NOBLE GA6ES This sp ification s provided to impi nt the r uirement of Sections I 8, III.A. nd IV.A o Appendix
, 10 CFR et 50.
e Limiti Condition or Operat n impleme ts the gu es set f th in Se ion 11.8 Appendi 1.
The AC ON state nts provi the req red oper ing flexi 111ty and at he same t implene t the gui ss for in Sec on IV.A o Appendi I
to a ure that t e release of radios tive te al in ga ous efflu'nts to UNR TRICTED A AS will b kept "as ow ai casonably achievani The sur-
{
11ance Reg irements ijaplement e req /
nts in 5 tion !!!.. of Appencid v
at confor144nce with the guides App hdh I be sh n by calc ationalprofe-dures base [ on modelty/and data ch th e actual xposure o a MEM8ER OFf THE PUBLM through pppropriats pathw y unlikel to be sub antia11y u er-e s t ima te'd.
The dose calculation m@
logy and arameters stablished n the 00CM for calcula)4ng the doses Yo he actua release r tes of radi etive noble' gases in gaseous afflue r consiste with the thodology ovioed in Regulatory,duide 1.10F, "C fon of A ual Doses o Man from outine Reieases of Keactor Effluents for the Purp e of Eval ting Compli ce with 10 CFR Part 50, Appentin I," Re ston 1, tober 197 and Regulat. ry Guide 1.
1
/
" Methods for Estina dng Atmos.
ric Tran port and spersion of aseous Eff ent inRout%eReleasegfromLi
-water C led Reac s," Revisto
- 1. July 19 The 00CM equatior)4 provide for eete ning the r doses at nd beyond ' e (SITE p uMDARY afe based n the higorical ave / age atmosph ic conditions.
3/4.11.2.3 5
100 W -131. IQ0!NE-133. Tg! TIUM, AND 440!0NUCLIDES/IN ARTICULATE / FORM
/
Thi.apecifi tien l' p vided i
lesent the equirement of s
Sectio II.C, I
.A and IV A of Ap x I, 10 CFR art 50.
T Limiting Condi ions for peration e the g s set forth n Section
.C of Append x I.
The CTION st eeents pr vide th utred opera ng flexibi ty and at t s
time i esent t guides e forth in Sec ton IV.A of Appendix ! t sure the the rele es of r etive mater is in gase 's affluents o UNRESTRI O AREAS 11 be as low as i reasonably achievable." The 1 00CM ca ulational methods ified in th Surveillanc/ Requirement -implement
/
HOPE CREEK 8 3/4 11-3
RADI0 ACTIVE EFFI.UENTE BASES Dost-Ionm-1/i. Toetwt/33. TRITTtM AND RADIO t*C'! des I PART;ca.j(-g repy {
(Continued) j ormance!sththe the requi nts in S tion III.A f Appendi I that co guides o ndix shown b calculati i procedu es based, din models a data, a that th actual e ure of a ER OF PUBLIC @ rough appr late pathw e is unli ly to be s stantiall underesexfnated. The ocM cale ational
_ _ ~'alogy a paramete for cal ating th doses due the act al release ates of th subject ertals ar consiste with the f
hodology p ovided in gulatory ide 1.109, Calculat on of Annu 1%ses Man from outine Re1 ses of Re ter Efflu to for t Purpose o
}
aluati osy11ance ich 10 CFR art 0,
ndix I,' Revision 1 Cetober 1977 and latory ide 1.111, *Meth af Estimat Atmosphe ac Transpor and Das raion of seous Effl nts ine teleases from L1-t-water-Coole eactors," evision 1, uly 1 1 ese equa/ ions also ovide for date ning the cual doses sed n he histo cal averag atmosphers co ations. The release ra spec ic tons for odine-131, odine-133, t
tium, and dionuclide in pa ate form ich half 1 es greater han 8 sys are dep dent upon e ex t radionue de pathway to man, in he areas at beyond th SIT Y. The p hways that era examin d in the devel of these leu tod were (1) Individual nhalation o airborne /
posit des onto gr en leafy v station umption Dy/gi' radionue radionu ides, (2) man, (3) position o o grassy a as where
/
with a sequent co milk anals and at produc4ng animals,g, raze with nsumption the milk pnd maa by man, an (4) deposition on tha< ground wit subsequent xposure of stan.
' C E.1.Je.7 5 B d
7 NCASECtJS s1DWASTE TREA".3 RENT AND VENTILATION EXMAt'ST 3/4 11. 2 4 AMD' 3 /4 11. 2 s
j-w_
/
ne PERASILITY f the GAS US RADWAS TREAmENT STEM and t VENTILA.0W EXMAUST TMENT fYSTEM neur that the stem will availatle /
fer us whenever g 'seous ef f1, dents r 1r treatment rior to rel ase to t..e
/
j env1
- c. The equirement/ that t p repriate p tions of th se systems -
us when spec ted, provydes rea e assurane that the r eases of i
ra tosctive ma artals in gaseous 1 nts will b kept *as 1 as is rjasonably acMaevable. '
,is spe i tion imple ents the re trements e eneral Deep Criteri 60 of A dix A to 1 CFR Part 50 and the de.gn Mobjectives/gtven in S ction I Appendix I/ o 10 CTR rt 50. The t
of appropr'inte portio of the sys ems were specif teflaatts govprning of the dead design ob) ettves set. rth in specifipd as a sultdble f r dtz I, 10 C#R Part 50, or gaseous grt fluents t o Sections 11.3 and 41.C of
/
/
3/4 u2. est, RED 3 3/4 11-4 Amendment No HOFS CREEK
l l
l l
l I
RADIOACTIVE EFFLUENTS SASES l
3/4.11.2.7 MAIN CONDENEER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this affluent is inadvertently discharged directly to the environment without treatment.
This specificatien implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
D212,"7'GO -
3/4.11.2 NTING OR b CI Th specificat' n provides easonable aurance e t release from d ell pur ng operatio will not coed the ual dose
.mits of 1 CFR Par 20 UNRESTRI.
ARIAS.
Di G. T E!O w-3 /4 11. 3150ufD RADIDAC*7hr WASTE *RE[TriENT
)
p This ecificatio implements he re ir nts of G eral De gn Criter on E0 of pendix A t 10 CFR Par 50.
T ocess par ters i luded in esta 1shing the ROCESS CON % L PRO @
y inclu but a not lima d to wa e type, was e pH, waste aquid 1 ification agent /cs alyst rat s, waste e
content.
see princt 1 ch constitue s, and xing and ring smes. The urpose of pe PRO NTROL PR RAM is provide ality (assurance hat the solidified was meets 1 CFR Par 61 require ents.
h6 3/4 11 TOTAL DOSE i
m -.
/
This specift tion is pr ided to et the se limitat ons of 40 CFR Part 190 that have een inco ated int 10 CFR P rt 20 by 4 FR 18525 The speelficati requires e prepara son and attal of a Specia Report whenever t.e calculat doses fr plant nerated ra cactive ffluents an to [/
direct r sation exe ed 25 mre he otal body any org except th I
thyrot. which sha be lima d to than or e al to 75 rems.
For tes cent ning up to reactors at 1 hly unlike that t resultant se to a
ER OF PUBLIC wi exce he dose li ts of 40 TR Part 190 f the 1 dividual r ctors re a wit twice the se desi objectives o Appendix and if rect rada ion d
from the r actor uni s including taide storage t a, etc.
re t
11.
The ocial Re rt will des abe a course i
of acti that sho d reau in the lam atton of he annual do to a MEMBER OF TH PUBLIC to athin 40 CFR Par 190 11mira. For thp. p rposes of the the dos,e'consaitment spo al R. port it may assumed e t the MzxnER Or l
/
d c
1 l
gopg CREEK B 3/4 11 5 Amendment No.
l
RADI0 ACTIVE EFFLUENT 8ASES TOTAL 005 ontinued THE P LIC from o er uranium el cy e sou es is nog gible, wit the exceo/
tio that dose ntributions com ot r nu ear fuel cle facili es at the/
s e site or hin a radi of 8 s
e consic ed.
If th dose to apf EM8ER OF T PUBLIC is e imated eed the r utrements 40 CFR Paft 190 the Specia Report with requ f r a variance (provided t release 'onci-tions re 1 ting in vi ation o R Part 19 have not a eady bee correctec),
in ace dance with e pro s f 40 CFR rt 190.11 d 10 CFR art 20.405c f i
is c sidered to a time e est and f fills the r quirement of 40 CFR Pa 190 until C sta<
is comp 1 ed.
The v lance on1 relatestot[e mits of 40 R Part (,
d does noyapply in a way to the other requ '/e-1 ments for d e limitati f10CFRPart20,asadressed1%pecifica-tions 3.1.1.1 and 3.11.
1.
An indfvidual is t consideyed a MEMBER THE PUBLIC ddring any peri in whichjfse/she is e agedincyryingouta i
tion at is part o he nuclea,r fuel cycle, opera-
./
/
7A6.5 P A 6 a n v r. a u v o n A u. y B % (
l l
l 1
l l
HOPE CREEK 8 3/4 11 6
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 9 @ E Te:2>
3/4.12.1(MONITORINGPRQ9dhM l
/
The radiologica environment monitori specification prov es represen tive meas ements of adiation d of radi
)
program r4guired by is active materials n those exp ure pathw and for hose radio clides th t i
lead to the hi est potenti radiation xposures f MEM ERS THE PUBL resulting f the statio operation.
This mon oring pro impleme s section IV
.2 of Appen x ! to 10 R Part and the supplemen the radiol
' al effluent nitoring ogram by erifying t the sea rable i
concen ations of r foactive erials a levels of ediation a not hi e
than xpected on a basis of he efflu t measur ts and th modeling th environment exposure thways.
uid nce fo this inoni ring prog is ovided by t Radiologi 1 Assess nt nch chnical P ition on viron-mental Moni ring, Ravi on 1, Nov er 9.
The initi y specif d monitor ing progr will be e ective f at 1M e first 3 ears of c reial operati Followi this per od, ott changes be initi ed based on opera onal exper nce.
The requ ed detect nc les for e ronmental ample anal re tabulat in terms f
limits of tection LDs).
The Ds es required Table 4.fl.1-a pensidered o inum for utine envir antal measure nts in inabstri 1 ahdratories. jIt thould recognize LLD i defined a /an a prior / (before tDe fact) 11 hat the t represent g the capa /
bil y of a me uremeiit s tem and not'as an a p teriori (af r the fac 1
it for a rticular asurement.
Det led discu ton of the LD, and o er detectio limits, be found in Cur e, L. A.,
ower Limi of Detecti Definit n and Ela ation of a Prop ed Positi for Radio gical Eff1 nt and Env neental surements,"
NU G/CA-4007 eptember
), and i the MASL P cedures ual, MASL-300 evised an allyl D.bs:GO~
J 3/4.12.2TLANDUSECfdSUS specif 'ation is vided to e ure that c nges in the us of areas at and beyond SITE ARY are id tified and hat modificati s to the radiological nvironnen monitori p
an er made if requir by the
/
results of his census The best formp n
on the door-to oor survey, from aer 1 survey, om visual rvey A consulting wi local agric tural thorities 11 be use.
Th can s satisfies th requirements f Sect n IV,.B.3 o Appendix I o1 C P t 50.
Restric ng the censu to gar-e of greate than 50 en rovi s
rance that sig icant expos e pathways a leafy we tables wt1 f d and monitored ince a garde of this size is th minimum re tre o I uce the quantit (26 kg/ year) f leafy vege-i tables af used in Re atory 1.109 for cons tion by a c 14.
To deter-mine tMs minimum rden size, following as tions were de:
(1) 20% of the perden was u d fo'r growi broad leaf we tation (i.e., similar to lettuce angcabbage),
d (2) a ve ation yield of kg/m,
a HOPE CREEK t 3/4 12-1
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_3/4.12 RADIOLOGICAL ENVIRONMENTAL MONTTORING BASES p eu = -re--
3/4.12.3 M TEB d80RATORY M PARISON PR0 DRAM a
("hogram The r utrement f participa oningnap oved Interla ratory Com riser provided o ensure th inde @n checks on th practsion o accu-racy the measu nts of ra osctiv t ial in envir ntal sa e
matr ces are pe ormed as pa of a ty assurance rogram for nviron-l al monit ng in order o ra that the re its are va d for the utposes of tion IV.
of a di I to 10 CFR rt 50.
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e HOPE CREEK 83/412-2