ML20205E810
| ML20205E810 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/29/1999 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20205E800 | List: |
| References | |
| NUDOCS 9904060033 | |
| Download: ML20205E810 (81) | |
Text
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I HOPE CREEK GENERATING STATION l
FACILITY OPERATING LICENSE NPF-57 1
DOCKET NO. 50 354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)
TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES l
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 l
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 11.2.1 3 / 4 11-8 thru 11-11 3 /4 11.2.2 3/4 11-12 3 / 4 11.2.3 3/4 11-13 3 /4 11.2.4 3/4 11-14 3 /4 11.2.5 3/4 11-15 3 / 4 11.2.8 3/4 11-18 3 /4 11.3 3/4 11-19 3 /4 11.4 3/4 11-20 3/4 12.1 3 / 4 12-1 thru 12-12 3/4 12.2 3/4 12-13 3/4 12.3 3/4 12-14 684 6-16b 4904060033 990329 PDR ADOCK 05000354 P
PDR,
l
I 3
i 6.9.1.6 6-18 6.9.1.7 6-19 and 6-20 6.10.3 6-22 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 B 3 / 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 83/411.1.3 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 B 3 / 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 83/411.3 83/411-5 83/411.4 B 3 / 4 11-5 and 11-6 B 3 / 4 12.1 83/412-1 B 3 / 4 12.2 B 3 / 4 12-1 B 3 / 4 12.3 B 3 / 4 12-2 l
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_IN_D EX DEFINITIONS SECTION s
DEFINITIONS (Continued) l
_PAGE 1.26 0FF-GAS RA0 WASTE TREATMENT SYSTEM.............................
14 1.27 0FFSITE DOSE CALCULATION MANUAL..........................,,,,,,,,,
14 1.28 OPERABLE - OPERA 8ILITY...............................,,,,,,,,,,,,,,
15 i
1.29 OPERATIONAL CONDITION - CONDITION.............
15 1.30 PHYSICS TESTS.......................................................,
15 1.31 PRESSURE BOUNDARY LEAKAGE.......
...................a 1-5 1.32 PRIMARY CONTAINMENT INTEGRITY......................................
1-5 1.33 PROCESS CONTROL PROGRAM............................................
1-6 1.34 PURGE-PURGING..............
1-6 i
1.35 RATED THERMAL POWER................................................
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 1.39 SECONDARY CONTAINMENT INTEGRITY...............................
1-7 1.40 SHUTOOWN MARGIN.........
1-7 1.41 SITE B00NOARY............
1-7
- 1. 42 (gIOyICFIgC. u.9 7..v.d eR 1-e 1.43 S0uRCE CHECK.............
1-8 1.44 SPIRAL REL0AD..............
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1-8 1
1.45 SPIRAL UNL0AD............
1-B i
l 1.46 STAGGERED TEST 8 ASIS.....
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1-8 1.47 THERMAL P0WER..............
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1-3 1.48 TURBINE 8YPASS SYSTEM RESPONSE TIME.
l 1-9 ]
1, HOPE CREEK
.i 1 Amendment No.
f
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INDEX I.IMITI3fC CONDITIOtf8 POR OPERATION AND SURVEILI ANCE REQUIR.EMENTS M
EAfsE Table 3.3.7.4 1 Remote Shutdown Monitoring Instrumentation 3/4 3 75 Table 3.3.7.4-3 Remote Shutdown Systems Controls 3/4 3-77 Table 4.3.7.4-1 temote Shutdown Monitoring Instrumentation Surveillance Requirements 3/4 3 82 Accident Monitoring Instrumentation 3/4 3-34 Table 3. 3.7. 5-1 Accident Monitoring Instrumentation 3/4 3 05 Table 4.3.7.5 1 Accident Monitoring Instrumentation Surveillance Requirements 3/4 3 37 Source Range Monitors 3/4 3 04 Traversing In Core Probe System 3/4 3 33 Radioac ve Liqu Efflue Monitori Inst tation 3/ 3 91 Tabl 3.3.7.9 Radio tive Liqu Effluen Moni orang Ins ntatt 3/4 3-9
.able 4.
7.9 1 dioactive aquid If uent itoring 7
Instrumen e on Surv 111anc Require nt 34 3 94 R toactiv Geseous fl Mo atering natrums ation 3/4 39 Taele 3 3.7.1. 1 adi et Gaseou Effluen Mondh6r Inst ntatto 3/4 3 97 7
e 4.3.7 1
1 ctive eous Et uent Mon cring I
rumenta on Surve lance j
,re s
3,4 3 10.
3 4.3.8 OEdETED 3/4 3-103 3/4 3 9 FEEDWATER/ MAIN TUR3!NE TRIP SYSTEM ACTUATION INSTRUMENTATION 3/4 3 1t5 Taele 3.3.9 1 FeedwaterrMain Turnine Trip System Actuation Instrumer.tation 3/4 3-106 Ao.n.m.n..o.,4-(t)
.c.E =REER ta
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M LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMDTIS SEC* ION E.b5In
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3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level..
3/4 9-17 Low Water I4 vel..
3/4 9-is 3/4.10 SPECIAL *EST EXCEPTIONS 3/4.10.1 PRIMARY CONhAINMDrr INTEGRITY.
3/4 10 1 1
3/4.10.2 RCD WORTH MINIMIZER.......
3/4 10-2l 3/4.10.3 SHUTDOWN MARGIN DD90NSTRATIONS....
3/4 10 3 3/4.10.4 RECIRCULATION LOOPS...
3/4 10-4 3/4.10.5 OXYGEN CONCENTRATION...........
3/4 10 5 3/4.10.6 TRAINING STARTUPS..........................
3/4 10-6 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE I4ADING..
3/4 10-7 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING.........
3/4 10-8 3/4 11 PADICAC*IVE EFFi?JENTS 3/4.11.1 LIbUID EFFLUDrrs l
(~Concener tion.
/4 11-1 7 le 4 1.1.1.
-1 Ra oactive aquid W ste S
lin Analy a Prog am..
3/4 1 2 De e.
3/4 1-5 squi Waste rest t...
4 11 6 Liquid Moldup Tanks.
3/4 11
3/4.11.2 CASBOUS EFFLUDrrS se te....
3/4 1-8 able
.11.2.1.
1 Radi etave seous aste sa ing an Analy a Progr 3
11-9 se -
le Gas
...fY......
/4 11 12
/
Dose Iodine 31 I e-
, Triti and Rad nuclides in Pa 1culat Fo h 3/4 11 3 o
l s.ous
.aste eat.en ut 1-14 c.ntil lon ust Tr.. ant st..
3/
11-15 HOPE CREEK xv Amendment No.
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- .rHIT:NG ceND:TIcNs rea openA : N AND senvr::.LANet at;c:Roer s S EC*
- 3 p3;g l
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DE LE.76iiO ven::ng or Purg:ng.
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3/4.11.3 sc., RA::: :::vt -
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3f4 * *..,
3/4 11. h v.A:,
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3/4 1: RAO * "!.0C * !A* Ot'/
- R O NvDr*AI. =c N!?t R !NG DELG7dEO J/4.12.7 "MCN:T:RIN" 7 Roc j
3 4 ;;.,
Ta:1 3 ;;.;
- Rat :*:.=al Env;r n en:al M: : ing Prog 3/ ::.3 able 3.;.1-2 / p ::ang :.ev.s F r Radio tava:y
.:e.::a:to
- n Env;.ren en:al t
1 a ples.
O Tab' 4.;; ; ' Oete ::= Capabala e For 7
Envaren. ntal Sample 41ysis.
3/. :. ; :j 3/4.12.2n;.AND 05 CENSUS.
3/4 12.;3 DC IN*I A3CRA*0RY h0MPAA:50N ROGRAM.
3/4 ;;. 4 u
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_ ne.ent.
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INDEX RASES SEM ION IAGE ins 1ttfMrw AT!cN (Continued)
Remote Shutdown Monitoring Instrumentation i
and Controls 3 3/4 35 Acetdent Monitoring Instmmentation 3 3/4 35 Source Range Monitors a 3/4 35 Traversing In Core Probe System adica ave La d Effluen Mont rt 3 3f4 3-5 I
rumenta on B /4 36 I
Ra cactive aseous Ef uen orang Instrum cation B 3/4 - 6i 3/4.3.s DELETED 5 3/4 37 3/4.3.9 FEEDWATER/ MAIN TL'RBINE TRIP SYSTEM AC"MJATION INSTRLHENTATICN 3 3/4 3-7 Figure 53/4 3-1 Reactor Vessel Water Level 3 3/4 3 s 3/4 4 R EAC'*OR COOM Sg B 3/4 41 3,4.4.1 RECIRC"1ATICN SYSTEM 3, 4 4.2 SAFETY / RELIEF VALVES 3 3/4 a
3i4 4.3 REAC""CR COCIANT SYSTEM LEAKAGE Leakage Cetection Systems B 3/4 4-3 Operational Leakage a 3/4 43 34.4 4 OKIMIST1tY a 3/4 4-3 3 4.4.5 SPECIFIC ACTIVITY B 3/4 44 3~4 4.6 PRESSURE / TEMPERATURE LIMITS B 3/4 45 Table 33/4.4.6 1 Reactor Vessel Toughness 3 3/4 4'
F1 e 33/4.4.6-1 Fast Neutron Fluence (E31Mevi at (1/4)T as a Function of Service life B 3/4 40 HOPE CREEK xvitt Amendment No
r Inn BASES SECTION 212E
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3/4.10 SPECIAL TTST EXCEPfigjjj i
3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.
B 3/4 10-1 3/4.10.2 RCD WORTH MINIMIZER l
B 3/4 10 1 3/4.10.3 SHtTrDOWN MARGIN DEMONSTRATICNS B 3/4 10 1 3/4.10.4 RECIRCULATION LOOPS 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 INSTRUME}rfATION - INITIAL CORE LOADING B 3/4 10-1 3/4.10.8 INSERVICE LEAK AND HYDkOSTATIC TESTING B 3/4 10-2 3/4.11 RADICAC"*IVE EFFLUENTS l
3/4.11.1 LIQUID EFFLUDf!S
/.
F.
Av l Cone trat n B
4 11 1
{ De 3/4 11-1 1' quid ~ dwast_e.reat t Syste B 3/4 11-:_
Liquid Holdup tanks B 3/4 11-I 3/4.11.2 GASEOUS EFFLUENTS
/
Rate.
Y B 3/
11-2 se - N le Ga e B
4 11-3 ose - odine. 1 I e-33.
citium, ad Ra onucli e in Pa iculate Forte.
3/4 1 3 Gas us Ra aste Tr taent 5 stem and u
enttia on Exha t Trea t Sys ma
./.
B 3/
11-4 Main Condenser B 3/4 11 5 Venting or Purging B 3/4 11 5 MLT 11 7 3/4.11.3 SOLID I
IVE TE.
B 4
5 AI. DO
.D 3/4/s me"? - D i
HOPE CREEK xx1 Amendment No.
o
7-INDEX BASES SECTION PAGE 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING D E.t E T6 0
.4...........
B3D 3/4.u. B M0iitT INc P RAx......
teunSo 3/4.u. A u USE NSUS........ g........
3/4 u.
D 3/4.12.h NTERL ORATO COMP ISON P RAM..
B 3/4 2-2
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l HOPE CREEK mati
DEFINITIONS I
LINEAR HEAT GENERATION RATE l
1.21 LINEAR HEAT GENERATION RATE (LHGR) shall be the length of fuel rod iated with the unit length.It is the integral of the transfer area assoc.
LOGIC SYSTEM FUNCTIONAL TEST 1.22 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all lo
).
etc, of a logic circuit, from sensor through and device, to verify OPERABILITY.
The LOGIC SYSTEM FUNCTIONAL TEST may me performed by any series of sequential, overlapping or total system ste such that the entire logic system is tested.
MAXIMUM FRACTION OF LIMITING POWER OENSITY 1.23 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (M value of the FLPD which exists in the core.
MEMBER (S) 0F THE PUBLIC 1.24 MEMBER (S) 0F THE PUBLIC shall include all persons who a associated with the plant.
I the utility, it contractors or vendors.This category does not include employeei Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recre-ational, occupational or other purposes not associated with the plant.
MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be th exists in the cere.
[
OFF-GAS RADWASTE TREATMENT SYSTEM
\\
1.26 An OFF-GAS RA0 WASTE TREATMENT SYSTEM is any system designed and i to reduce radioactive gaseous effluents by collecting reactor coolant sys-s tem offghses from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
OFFSITE 00SE CALCULATION MANUAL 1.27ffh'e FFSI 005 CALC TIO n
h L (O M) all ntai the urt t th l
ol a
par ters sed
/
cal ati of fsi dos d
to adio Lg ;-
a ive gaseo and igui ents in e ca ulat'on of gas us d
,iou effl ent itor rm/
io s poin s, a in ee duc of e
rac'ologi 1 en ron nit ing rogr HOPE CREEK l'4 Amendment No.,y '
r 1
LCR H99-02 INSERT A i
l 1.27 The OFFSITE DOSE CALCULATIONAL MANUAL (ODCM) shall contain the l
methodology and parameters used in the calculation of offsite doses resulting from i
radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid eff;uent 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 Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should 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 D 1.33 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, j
sampling, analyses, test, and determinations to be made to ensure that processing and i
packing of solid radioactive wastes based on demonstrated processing of actual or s.imulated wet solid we tes will be accomplished 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.
l
DEFINITIONS i
1.33 [ OC S C0 R0 R0 AM CP) shal con in F G pr isi s to assur i
t th SOLI FI TI or ewa rin and acka ng rad'eact' e wa
.ul in NSEE"RT was e p ckag wit pro rti th mee the inim an es ab' ity equ em ts o 10 FR rt 6 and ther reou' eme s to te s-por atic to e
ispo 1 s' e ce ipt t th dis sal ite.
dit S IDIF CAT N,
he P s
11 i y th pro ss p ame rs i lu cin OLIO IC 0 such s p, oi y nt, 20e ten, sol' s ce ten rat ~o of lid ic ioh gen to sp, nd/o nec stry ddi ves r
en ce of ant ip ed w te, and ept,le b nda con tio fo the proc s ara er sha be den i
for ch sta pe, ased n1 or cry sea a
ful se et tp re erie c.
ith at ing the CP all i
u an ' ent ica con tio tha mus es isf ed, ase on 11 cale es ng, re at d ater' O o boa res s,
wde d res'ns, df ter lud s wi re it i vol s
fre wa r,
the.
t' e of dis sal with' th limi of CF Part 1 do the ow-1 vel adio tiv was di osal site.
PURGE - PURGING 1.34 PURGE or PURGING shall be the controlled process of discha k.
tion or other operating condition, in such manner gas is required to purify the confinement.
RATED THERMAL POWER 1.35 RATED THERMAL POWER shall be a total reactor core he the reactor coolant of 3293 MWT.
i REACTOR PROTECTION SYSTEN RESPONSE 7tME gk, 1.36 REACTOR PROJECTION SYSTEM RESPONSE TIME shall b r
when the monitored parameter exceeds its trip setpoint at the cnannel
\\ IV sensor until de energization of the scram pilot valve solenoids.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
REPORTABLE EVENT 1.37 A REPORTA8LE EVENT shall be any of those condition; specified in tT Section 50.73 to 10 CFR Part 50.
^
R00 DENSITY 1.38 R00 DENSITV shall be the nuncer of control rod notches inserted as a fraction Of the total numoer of control rod notenes.
All rods fully inserted is equivalent to 1007, ROD OENSITY.
L'
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' HOPE CREEx 1-6 AmendmentNo.[
I
DEFINITIONS i
SOLIDIFICATION 1.42 SOL FI ~ blot useD ION all et i
i[i ion ve[ra a eva rato et s,
ent e
, slu Yes, no e ers osm is nce act ew es ucn ta as res o a or s
tho tg mi 'ng t wa e t' e w'.n a
't idif atic ag (s) a fr s* ndin mono th th.emi 1
I nys' Ic rac rist' s ifie in e PR ESS NTR PR RAM PCP l
SOURCE CHECK 1.43 A SOURCE CHECK shall be the qualitative assessment of chann when the channel sensor is exposed to a source of increased radi SP,IRAL RELOAD h
1.44 A SPIRAL RELOAD is a core loading methodology tmplopet after a complete core unload.
During a SPIRAL RELOA0 the fuel is to be d
loaded into individual control cells (four bundles surrounding a control blade) in a spiral fashion centered on an SRM moving outward, initiating a SPIRAL RELOAD, up to four bundles may be loaded in the fou 8efore bundle locations immediately surrounding each of the four SRMs to obtain the required channel count rate.
1.45 A SPIRAL UNLOAD is a core unloading methodology employed to defuel w I
I the complete core is to be unloaded.
Tn'e core unload is performed by first removing the fuel from the outermost control cells (four bunales i
surrounding a control blade).
Unioading continues in a spiral fasnion by removing fuel from the outermost s..'iphery to the interior of the core, symmetric about the SRMs, except for the four bundles around eacn of the four SRMs.
When sixteen or less fuel bundles are in the core, four around each of. the four SRMs, there is no need to maintain tne e-quired channel count rate.
)
SJAGGEREDTESTBASIS 1.46 A STAGGERED TEST BASIS shall consist of:
,'\\
A test schedule for n systems, ubsystees, trains or other designated a.
components obtained by dividing the specified test interval into n equal subintervals.
b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL DOWER 1.47 THERMAL POWER shall be the total reactor core heat transfer rate to thel reactor coolant.
HOPE CREEK 1-p Amendment No.)(
-3. 5. 7.1 O De:.Le. TIED m TauxxurarIOm RAninmeTivE LI D EF NT TORI INii. uni.1AT LIMITING ITION R OPE TION 3.3.
10 The adioac ve 1 id e luent nito ng in rune.atio che is sh in T is 3.3
.10-sna11 OPE LE w the Al
/Tri set nts t to e use th the imits f spee icat 3.1.1.1 no ese ed, he Alarm / ip set ints f the ch ee be erni adj ed acco ce w h th t
logy r
(
).
d APPLIP ILYTY At time.
Wi a ra oscti 11 d off ent nitor ng in atio annel lars/ ip 5 int es neerv ive r
ir by t eb:ve pecif stio immed tel suspe the eles of dios ive 11 d etf ente nitor by su af eted hann, or ect th e nnel oper e, or han the tpoi so is cept y
on6erv tive.
j wit less han t ein n
eo radi etiv liqu et uent itor g ins n tion anne OPE LE, ake eA ON own
{
nT e 3.3
.10
. Ex bas effo e to stur the not nts to ERAS stat wit n 30 d e
, if neuce esfu, esp sin t
next dio tive fluen Re1 se P rt sua to pecif stio 6.9.1 why is i r
lity as t co oct in a timal aan r.
c.
T pro sion of c ific ton
.0.3 en appi cable
/
sURVE Rago NTs
...................................=====..============
==
.3.7 0 Bac radi ive igu effl nt itor g in rumen tion hanne sha be astra o AAS by to o t
'""*L CK, SOURC CK, -
""*L I
- ION, at fr enci e Table
.3.7 10-1 WOPE CREEK 3/4 3-91 Amendisent tis.
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PAGES 3 / 4 3-92 THROUGH 3-95 INTENTIONALLY BLANK HOPE CREEK AMENDMENT NO.
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_ABLE 3.
n ACT N 110 -
With nume of ch els OPE LE le than r uired b ne Min um Cha els OP 8LE. re resent effluen release via tni o hway conti e provi d that ior to itiati a rele' e:
a.
t less two ind endent moles analy in ac rdarce with ecific on 4.1.
1.2; d
b.
least o tech cally e ified Staff opende ers the Faci ty ly the r ase re calcula ons
- inq, ri and scharg ng; othe ise, s e
se of dioacti efflue via s
p sy.
ACT 111 -
With e numer of chan is OPE LE less an re red b he Mt um Chan is OPE LE re
- roment, fluent elease ia thit hway contin provi
- that, least e per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> grab s es ar ellect and an zod fo gross r toactiv y at a sit of etecti of at 1 st 10 ' icrocu es/al.
he r-wi
, susp relea of rad ctive fluent 14 this athway.
ACT M 112 -
with nuste of chan s OPE E les han re red by Min Cha is OPE LE req
- esent, fluent leases a
s pat y say c inue p vided flow r e is est ted at east a per 4 ours d ng act relea Pump rformance curv genera o in p1 e may b used to stimate ow.
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Tatt 7.10-ntin fa NOTAT!
(1) f CMahn(L NCTIONA.(57 sna aise natrate at eut sie i at'en f tais n=ay a ontrol e os alare nuncia n occur any tne follow g conett s esis
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Instr et inet tes asas ed level ateve t Al rip 5et nt. or c.
Cult f ure, or Ins!' bent'in atos a d scale ivre.
) The ANNEL F TIONAL T shall se nitrate at cent room rm aMb ation oc rs if o f,.tn ellowi canditi esists:
a.
strument sicate asure[els.
we the re. Setooi or Circu failur, or c.
strumen indica cale fail (3) init CHANN CALI 10N shal perte using s or more of the rence ndares ertified the Nat 1 Surea - f Standare (N95) or ng s ards t have ette t,,.
res suas es that pa scinate l
measu nt as ance act ties wit 5.
The s tandares all per t 3
calier ng t ystee ov its inte range eno m a asure ra For secuent (L CA
- 4ATION, rces t ut we seen latea t / he in al calib ten er N85 tr le shall used.
C L CN(CK s 1 Coisi of verif indfCat of fl uring Der as o release.
(L K shall made at I t once 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cays on n gentin us, poet c, or 64 release re ases.
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LIMITING COND FOR op 3.
.11 The radi ive gas e offluen nitor inst tation annels own in Tabi
.3.7.11-11 be OP wi their
/ Trip tpoints set to one that t imite of ifica no 3.11
.1 and 3
.2.6 a not exceed The Al Trip Set ts of se ch a meeti specif tion 3.
.1 shall deterni and ad ed in ordance h the hod;1 d parame e in the AP mir. TTY:
hewn i ablo 3.
.1
/
&GZlGE8 a.
Wi a radi tive gas e efflu monito inst ation annel rs/ Trip point I consor ive than ired b he abov pecificat
, immed ely sus the re se of ra active e effl to monit ed by t affected el, or clare t channel i
- rable, change e setpoin it is ceptably conse ive.
b.
th less
- an the a n
of radio ive gas e
afflue monitori instruse tion cha is CPI
, take t ACT shown able 3.3
.11-1.
I best orts to r rn the I
strument o CPERAS status wi a 30 da and, if u accessfu l
explain the next adioactiv ffluent lease pursua to Spec cation 6..1.7 why e inoper lity was correc in a t
ly manne The pr sions of pecifica n 3.0.3 ar not appi le.
SURVII CE REQU S
4.3.7.1 ach red ive gas offluent nitori not ation chan shal demon ated OPE by perto ce of N*
CRICK, SO j
, N*-
CALIEhATI and NS""*_
FUNCTI TEST a the freque es shown La le 4.3.7.
1.
1.
1 3/4 3-ge AmendmentNo.M
r--
1 l
PAGES 3 / 4 3-97 THROUGH3-102 INTENTIONALLY BLANK I
HOPE CREEK AMENDMENT NO.
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T LE NOTAr;CN At 1 time I
ACT N 122 With he a of C els RABLE esa e requir by th M1 um C
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{
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24 hou. Othe see, e' pend r ease o' rad etty e.
s via is path y.
)
ACTICN 24 ACT H 125 Wit the n r of e annels ERABLE.ess th requi d by th M 1 mum Ch als C RABLE r quirem t,
off ent re' ases vi is pat my may entinue rovide that w han 8 ours sam.es are co inuous collec d with uxsita sampi g equip nt as requi d in T le 4.11
.1.2-
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i EPE N 3/4 3-99 Amendment No
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TAaL OTATIO At a times.
i 1)
CHANNE CTIO TEST 11 als demo trate e con el l
com ala annunci ton oce rs if of a folio ng i
conditi s exist l
1.
natrume indica e meas ed le is abo the arm setpot l
2.
Cir at fail e.
3.
strume indie es wnscale ailure I
(2) initia CHANNE' C TION s 1 be rformed sing e or of t e refer n dards reifle by the attona Bureau of Stan rds (
)
r ing st dards at have een ob ained 1
from pplier tha reicipa in me suremen assura e act' ities th NBS These andard shall mit c Abrating system ver 1 inten d rang of ener and m surement
- e. F subs ont L
.BRATIO, soure that ha r ated t the in tal ca bratto or are 5 tracea e y:
shall e use.
p:
TNis pac +G w mv no.usay ~73 uw K l
HOPE CREEK 3/4 3*102 Amendment No L
1 l
1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS S/ //. f. / DSL676 l
, LuMLtNr RATIOVQ LIMITING 017I OR OP ION
/
/
/
/
/
/
/
/
3.1.1.1 T
concent ation of adioacti e materi relea d in li vid eff1 ents to NRESTR TED ARE (see Fi ure 5.1.
- 1) shaly be limi ed to t concen.a-ons sp ified in 0 CFR P t 20, A endix B able I, Colum for r io-nuclide other tt n dissol ed or en ained n le gas For ssolved r entra ed noble gases, t concen ion s 11 be l' ited to 2 x 10 4 mier curfes/m total a ivity.
PLICABIL Y: At I times.
ACTION:
((/
Wit he conc tration f radio tive ma rial re ased in iquid eff uents to RESTRI ED AREAS xceedin the ab e limit, immedi ely resto the centrat n to wi in the ove lim' s.
SURVEIL NCE REQ REMENTS
/
/
/
/
/
/
/
/
4
.1.1.1 adioacti e liaui wastes all be s spied and nalyzed cording the sam ing and nalysis program Table
.11.1.1.1 4.11.1.
2 The suits the rad'oactivit analyses hall be ed in accor ance with e mothe logy an paramet s in th 00CM to a sure that ne concent ations at e point relea are mai ained w' hin the mits of ecificatic 3.11.1.1.
)
HOPE C"EEK 3/4 11 1
r.
f l
1 PAGES 3 / 4 112 THROUGH 11-4 INTENTIONALLY BLANK j
1 e
l HOPE CREEK AMENDMENT NO.
n TA/S PA 6G /N ~7A90 7 mal-LY ~~8 LM K I
/
z 1
_s_,E s._
/
/
/
/
/
/
ower t'.1:
Min um Type of De etten quid Re1 se amplin lysis Act sty (tto Typ Frequ cy requenc lysts (a s ml)
A.
atch ste P
Prin pal Relea Each B wch ch Ba Ga a
5x10' Sam e
E ltter T
s (3) i I-13 10" h[
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Relea s'
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1 S[90 N
Q Sr 9,
x10" Compo e,
[
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1x10" e-55 c/
/ /
/ /
/
/
/
l HCPE CREEK 3/4 11 2 Amendment No. f L
l 7^/-N 3 PA &6 //v'7sn ?70NALLY ~BL&iIt A8LE 4.1 1.1-ntinu TABLE ATION aTh LD is ined, f purpo s of the speci cations, s the liest centrat n of ra oactiv material nas le that 1 yiel a not ount, a ve syst back und, th will detected ith 9 robabil y with o y 5X p abilft of fals conc 1 ing that bidfk sEvati repr ents a " eal" s nal.
F r a par cular asurene system wt.fch as inc1 radioc cal separat n:
LLD =
b EV 2.22 08 Y
exp (-
e:
LLO the " priori" r lis det tion as fined ve, a
icrocur es per u t mass v une s
is e stand devia n f backg d counti rate gf tNe unting r e of a ank /
e as opriate, s coun per mi te, E is th countin e 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 micr urie, Y is he fra onal re ochemic
- yield, n app cable, is the adioacti decay nstant r the p ticular adionuct (sec 1, and at or plan effluent is the apsed betwo the et int of le co action time cowiti (sec).
Typic values f E, V
, and a should used in cal ation.
It s Id be ogniz t the LD is ned as a ori 1 (before the act) 11 t rep enting t capabi y of a asu t systes as an, poster ri (af the fac 11att f a pa cular ao resent.
A be relea is the scharge liquid stes a discre volume.
{ Pri to s ing for nelyses, ach be shall isola
, and then rough 1 mixed by method scribed the to as represe tive {
sampli s
HOPE CREEK 3/4 11-3
Tmm 11 1-fem undi t
- iso, j
- The cincipe gassia ters f which e LLD e ificat n a lies em unively re: Mn-
, Fe-59 Co-58,
~60, 5 5, Mo-s-134,
-137, a co-14 Co-144 all als sea red, b with an f5x Thi does no an the only t se nue des are
,/
to consid ed. ot peaks t
ntifi e, t her wit f
4 t se of t above clides, ha al be an med report in e
he Radi etive fluent es et pur ant to pecific ion 6.9.1..
7 d A omposi cample ich t quant y of 11 id e es e pr ional t
ity of iguid sto die arged in which he met of ng emp yed r its in spec that i r
sentati of the iguida lea
- A conti ous role e is t disc go of id w es of a nondi rete vo
- e.
, fr a voi of e tem the as an in flow d ing th conti us role e.
lb hh YDY Amendmentno.pfh nors caan 3/4 11-4
n 1
RADI0 ACTIVE EFFLUEN?3 l
/. /, E VG LG 7~@
LIMITING CONO ON FOR OP ATION 3.1'.
2 ine c e or cose ommitmen wo a ME R OF TH V8LIC f o racio-ive mater' s in l ia 'd efflue relea
, faos n reactor nit, to UNRESTRICT AREAS ( e Figure.. 1-1) all be l' Ited:
Duri any cale r cuar r to les han or a 1 to 1.c rems :
to bocy a to les nan or al to 5 es to a orgin.
b During y cale r year ess tha e equal 3 mrems.o tre tota ody an to less an or eau to 10 ms to a crgin.
p APPLICA8 Y: A 11 time ACT a
With t cale dose f the ese of r osctiv aterial in quid eff1 nts ex ding an f the a limit, prepare it to Commis on with 30 days, rsuant Specifi
,e tion 6.9, a 50 al Repo that ide fios t cause(s or
,exces the it(s) defines cor ive acti s that na been t en to r e the ases a the pro ed corr a,e tions be tak to assur hat su vent r asas wi ce
I comp 1 nce wit he above sits.
b.
prov ons of cificat 3.0.3 not ap cable.
VEIL REQUIR 5
7
/
.11.1.2 umulativ dose con butions liqui ffluenta f the current cale quarter the e nt cal r yeari 1 be date ned in ac nce wi the se logy a arameter / n the 00CM least once per days.
H0PE CREEK 1/4 11-5 Amendment N. M
r-RAD 20ACTfVE EFFLUENTS Li, 3 ' DEiL2YS 1.
m u.m g rutATMENT/
LIMITING CONDI N FOR QMRATION /
/
/
s
,/
/
,_~
1 r
s 3.11.
3 The 1 uic r3dv te tre nt sys a shall e OPER E and ao coriate po ions of a system all be see to e uce th adios ve matari s in iouid wa s prior their scharge non the reject doses du o the liquid
- fluent, om each eactor it, to ESTRI D AREAS Figu 5.1.1-1 ou)d e eed*0.0 rem to e tot ody or 0 mrem any e
o n in an 1-day iod.
APPLIC LITY:
all ti s.
A
/ 6[
With dioact liqui as bt i discha d and excess the ab e limit and an ort he lig radwa e tres syst t in o
- ation, af) submit the C insion w in 30 s
pursu to S f'
i p.9.2 a cial R rt that ludes e
foi ing in reat/
l Ex anation why li d radw a was be disch d wit ut satsent dentifi ion of ny inope le equ nt or b-systems nd the anon f the ino ability 2.
Ac on(s) n to r ore the perabl equipse to OPE atus, a Suas descr tion of ion (s) ken to vent a currenc The ovision of Speci cation
. 3 are t appife e.
SURVEI CE RE REMENTS 1
.1 Dose to 1 id rol ses froe ch reac unit UNREST TED AREA shall be reject t less nee per days i ccorda with e
odology d par rs in 00CM.
. 11.1
.2 The stalled guld ra ste tre nt sy shal demo rated OPE LE by ing fication
.11.1.
d 3.11. 2.
v 0- :
. E CR m 3,. 11 5 A_d_. o. x.
RAD!0ACT!VE EFFLUENTS 3/4.11.2 GA$E00$ EFFLUENTS s. a. z. i nm p,so
" 00$E RATE LIN! TING'CONDIT FOR OPfarr!0N
/
/
/
3.
. 2.1 T esse ra due to r feecti e mater is rol sed in seous e luents rea the si to are at a beyond
$!TE Y see l
gure 5.1-1) she be lisi to fellow ng:
For not e gases:
Less t" n er 1 to areas /y to the tal be%
less n er 1 to yr to
- skin, b.
For iodine-
, iodi -133, t tium for al radi ides in iculate em vi half-1 vos gre, er than days:
ss than 1u3
/yt u o
a Appt!C LITY: A all ti s.
ACT!0
//
if h the de rate (s exceed the we limits immedi ly reste the lease re te vi n the we (s).
$URVE!
E RE IREM NT 4 1.2.1.1 The de rate to noble ses in seous off vents s 11 be i
terai to be thin the ve liai s in ac reance wi the as legy and par ters i the 4.11.
1.2 7 dose ra due to 1 ine-131 fedine-13, triti
, and all radio-nuci des in rticula fe m with If-liv s greater 8
s in gas us I
eff vents 11 be de mined be withi the ahev limits i accorda o with the I
i 1
and par ters in 00CM ebtaint repres tive s les and rfem analyse in acco with sampli and ysis y as specified i
in Tab 4.11.2.1 1.
l r
IGPE CREEK 3/4 11*8
p l
l
}
l PAGES 3 / 4 11-9 THROUGH 11-11 INTENTIONALLY BLANK HOPE CREEK AMENDMENT NO.
k h
dE J
- )
fD oL t
i nm 1
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4 0
I 1
Lii
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7d/ s ?AG=G /N'7A;iN'7/ontALLY
~BLArJ K-
~
TBLE4.11.d.2-1(Contin
_ABLENOTATION/
(a)The is defined, or purposes o hese specific j
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 acted with 91 robability, represent a "real" sign For particular me urement system hich may inci e radiocher al s aration:
4.6 LLD =
b
,/
E V
2.2 108 Y
ex
-Aat)
Wh LLO is t "a priori" lo r1 of action as defi d above, as mi curies per un mass o
y is the standa dev the background ounting rate of t c counting eo
.a
- minute, sample as appr iste, as cou per E is counti 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 diochemical 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 midpoint of sampi collection a time of coun g (sec).
ical value f E, V, Y, an t should be d in the cal ation.
should be ognized that e LLO is defi as an a prio (before the fact) limi presenting t capability of measurement s tem and not as an a pos riori (after t fact) limit f a particular asurement.
-)
HOPE CREEK 3/4 11-10
77Vi s PA6E h/wvoiau y EtAa :
tant e 4. d. 2.1. 2-1 tdntinuads/
TA?LF IONS (b) princi gamma emi ers for ch the specificat n applies esclusive are the f lowing ra opuclides Kr-87, Kr.
, Xe-133, I
Xe 133m, e-135, Xe-138 in ble gas leases and
~54, Fe-5 Co-58,
-40, In-
-141 and 144 in lod and part late rol oes. This ist does r mean that nly the n
ides are!
he consi red. Other gamma peak that are id tifiabi,
her wi those of above clides, e 1 also be lysed a reported the Radi etive Bff1 at Relea Report pure at to specifi tion 6.9.
j (c) S ing and ysis shal also be formed fo11 inq shu own, s
up, or a change coeding 15% f RATED LAL PowE ithin a 1-r period This requi at does apply (1) analy a shows tha the DOSE IVALENT I 31 concentr ion in e primary lat c has not nereased re than a ctor of 3#
(2) t noble gas nitor showe. hat efflu t activity as not iner sad nor than a fac r of 3.
(d) T tium grab amples sha l
befaken a least o e per 7 day from the pont fuel 1 area, oneva spen fuel is h the spent uel pool.
j
) The rat of the e le f rat to the pied stre flow rat chall be kn for the ime e ered by ach dose o dose rate cal lation ma in o an with s ifications
.11.2.1,
.11.2.2, a
3.11.2.3.
(f samples e 11 be ng at lear once per 7 ays and a lyses shal be complet within urs afte changing, after r al from a 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 1samt 7d a following 'ach shut startup or THERMAL R chan saceedin 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 /> d analyse shall be e pisted ithin 48 hou of c ing. When s les coil ed for 24 ours are analysed, t corres ing LLDe y be incre med by a f tor of 10 This requirene does no apply if (
analysis owe that t e Dost B VALENT I-131 e contrati in the pr ry coolan has not in eased no than a facto of 33 (2) the e gas moni e shows th effluen activity has Lacro more t a factor 3.
i
~
g gaggg J/4 11-11 Amendment No
r RA010 ACTIVE (FFLUtiff$
^~_^ ~ ".':Ti
^
3.//,2,P.,,
VELEE.TE5D 17!CC-2sisen vu prufW f
f 3.11.2.2 The air due to netle released in each reacter uni, to areas at and soeus effluents, the 51T shall be lie to the folleni (see Fi
.1.1 1)
During any cali r guarter:
e than se oeval arads for radiation ess than er I to 10 erede for radiation b.
Duri calendar
- Less than er to 10 ered r gamme r
ation and less or al to 20 ads for beta lation.
k
&##L!
ILITY: At all
- mes, QN a.
h the calcu ed dese free r sective noble 6es in seous effluents esce i any of the e limits, y and sute t to the Casmission thin 30 days ursuant to ication 4.9.2, a Seccial Re that identi s the cause(s er escoeding the 1 t(s) and defi the correc actions that we been taken te e
j the e ases and th repeted correc e actions to te la i
as e that sues at releases vi te in cespliance the we limits.
The pro ens of $pecifi ten 3.0.3 are ne licable.
SURvf!L R(QUIR[M(NT$
a
.2.2 Cwoulativ se contributie er the current ca) e guarter and current calencar er for nette ga shall se deteret n accercance with tne motheeels ans parameters 1 00CM at least e per 31 ears.
~
t M0Pt cettK 3/4 11 12 Amendment me. [
g
" ? 2 3 '*t3
i RADI0 ACTIVE EFFLUENTS 3
t, 2,3 unMS DOSE - 100!NE-131.100!Nf/I33. TRITIUM.
LIMITING CONOI OPERAT!
3.1
.3 The dose a MEMBER OF TH 9 TIC from to e-131, iodine-tium, and all dionuclides in rticulate fore 5th half-lives eater,
than 8 days i aseous of flaan released, frc ach reactor un to areas i
at and boy the SITE B00N Y (see Figure
.1-1) shall b imited :s *. e followi 4
i a.
During calendar quar Less than equal to 7.5 mr orga nd, to r.
b.
uring any cal ar yeay Les an or equal to erees to
.y :--m AP CA8!LITY:
At I time h
CTION:
With the cd ated dose free e release iodine-131 odine-133, i
- tritius, d radionuclide n particul e form with f lives grea:
than ays, in gaseou fluents eeding any he above limiw,'
P pr re and submit the Commi on within 3 ays, pursuant
- ecification 6.., a Spect Report the ntifies the se(s) for exceedin a limit defines t orrective acti that ase, been take o reduce releases a the proposed rective act'
's to be en to ast a that subs nt releases w be in como ance wi he above its.
y; b
The prov ons of S cation 3.0.3 not applic e.
)
SURVEIL Rimjg 4.11.2.3 lative dose tributions f current. ale r quarter anc curren alender year f iodine-131, ine-133, tritiwi nd radionuclices in iculate fors half-lives eater than 8 day hall be determined accordance vi the methocol and parameters 1 00CM at least once per31 days./
p:
-s HOPE CREEK 3/4 11-13 Amendment No. W.
RADICACTfVE EFFLUENTS
- 5. //, 2. 4 D eliaL G.7d:Ts
" GA5EOUS RADWATit e nem-6ny LIMIT!NG CONDITI/OR OPERATION l l-
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3.11.2 The GASE0US P WASTE TREATT SYSTEM all be in oper ion.
LICABILITY:
W never the a operation.
condenser team jet air ctor system s in ACTION:
a.
With ga ous radwas from ain ndenser air jector.
bein ischarged thou reatme for a re tn 7 days, pr. ice a
submit to eC n w' nin 30 days t
ton 6.9.2, 5
i por hat include he followi information:
ursuant to ocifica-1.
I ntific of e inoperabl / equipment o ubsystems an he reason r
e inoperabil y,
e 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.
provisions Specificat 3.0.3 are n applicable.
RVEILLANCE RE REMENTS 4.11.2 The readi s of the rei nt instrument shall be checke every 12 rs when tn in condense air ejector i n use to ensu hat the peousraowas treatment s is functio ng.
t r'
-e-n1.p..
O.__,,
NO,E Co m m u.1.
RA0!OACTIVE ferLUENTS VENTILATION EXHAUST *REA78ENT Sv5 r4 3., 6 ). 2 6 'T)1EELLc~.TED L!w!!NG CON 0!*!0N FOR Oped
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3.;1.2 5 F
<EarttAttc~ Ex >
. REAR Esf Sv
<or tne Re.ctor
.4,,
and t ervice and Raowas' uilding smal e OPERABLE and acer riate cor-s of this system te used to - uce release of rac etivity. rem te projectec cosas i cays eue to seous effluent role s 'com eacn wnit. -
areas at an yone the 5ITE CaRY (see Figure 5 '
-1) woul execec-o 0.2 mrad t r from gamma radia
, or D.
O.
rad to air from bet diation, or 0.3 mren to any
~an of a ME ER OF PutLIC AP8LICA8!LITY:
At times. tb ACTION:
a.
With radioac ventilation exhaust ng discharged withe reat-ment and excess of the acove I ts, prepare and su to the Cooms on witnin 30 days our nt to specification
.2 a 5:ec al ort that includes tne owing information:
1.
Identificati f any inoperable og nt or suesystems, ar the reas or the inoperacilit 2.
A on(s) taken to resto the inoperable equi to OPERABLE status, ane 3.
Summary desc ion of action (s) tak prevent a recurren b.
The provi s of Spectfication 3..
are not appitcatie.
{
SURVEIL REQUIREMENT 5
/
4.11.2.5.1 Doses gaseous eleases each unit to areas a no beyond the SITE RY shall ee are ed at least once per 3 ys in accordance w the methodology an arameters in the 00CM, n the VENTILAT EXMAusi TREATMENT EM 's not ceing fully ited.
.2.5.2 The instal VENT! u r!CN EXHAug TREA M NT SYSTEM shall e on-sisered OPERABLE ting Specifications 3.1 # 1 and 3.11.2.2 a
.11.2.3.
M0PE CREEK 3/4 11-15 A8**d'*"t "'- U SEP : 31988
ADM8N3STRATIVE ColfrROLS 6.8.4.f Primary containment Laakaoe Rate Testino Procram A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR$0.54 (o) and 10CFR50, Appendax J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, 'Perf.stmance-Based Containment Leak-Test Program *, dated September 1995.
The peak calculated containment internal pressure for the design basis loss cf coolant accident, P.,
is 48.1 psig.
The maximum all.eable primary containment leakage rate, L.,
at P, shall be 0.5% of primary containment air weight per day.
Leakage Rate Acceptance Criteria are i
a.
Primary containment leakage rate acceptance criterion is less 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 L, for Type B and Type C tests and less than or equal to 0.75 L, for Type A tests;
)
b.
Air lock testing acceptance criteria are:
1) overall air lock leakage rate is less than or equal to 0.05 L, when tested at greater than or equal to P.,
2)
Door semi 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 frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the._Erimary Containment Leakage Rate Testing Program.
M 6tT::,T b HOPE CREEK 6-16b Amendment No.104
E ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.0.4 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 iow as reasonably 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 operabill.ty 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 AREA 5 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 current calendar year in accordance with the methodology and 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 conforming to Appendix I to 10 CFR 50,
- 7) Limitations on the dose rate resulting from radioactive matertal 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, i-i HOPE CREEK 6-16e Amendment No.
r~
ADMINISTRATIVE CONTRO14 PROCEDURES AND PROGRAMS (Continued) 6.844.g.
Radioactive Effluent Controls Program
- 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 effluents released from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, I
- 10) Limitations on venting and purging of the containment through the Reactor Building Ventilation System, Hardened Torus Vent, j
or the FRVS to maintain releases as low as reasonably i
achievable, and l
- 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 CFP Part 190, h.
Radiological Ent ironmental Monitoring Program A program shall be provided to monitor the radiation and rr.dionuclides 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 monitoring 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 radionuclides in the environment in accordance with the methodology and parameters in 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) Participat2on in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
. HOPE CREEK f"I rid Amendment No.
- LCR H99-02 I
INSERT D
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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 shall include summaries, 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) Gections IV.B.2, IV.B.3, and IV.C of Appendix I to10 CFR Part 50.
INSERT E 6.9.1.7 The Annual radioactive Effluent Release Report covering the operation of the urit during the previous calendar year shal! 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 l to 10 CFR Part 50.
j i
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1 L
i ADMINISTRATIVE COrTROLS
...............................~...............;;.....................
maadre m'
. nm e.
=-- E o Iso a-(cont und) to Jh afte he radioi no activity a redue limit. I h result a
14 include to and time sampli and 41V lotodine e centrations;
) clean-up ystem flow h tory at ing 4 e prior to first sample in which limit was eeded; Gr f he I-131 co entration and o other r ioiodina i conce ra i
crocuries gram as a fune on of t for the dur ion of t e
if L ctivity abov the steady-stat le is and (5) T time dur ion i
specific a ivity of the pr ary laat ese the rad iodine liaq, a
EADIQ&CTIVE EFFLUENT RELEASE REPORT hD 6.9.1.9 os release oports coveri the operation the unit shall g
[besubmitted May 1 of ch year and i accordance with requirements f
{
The ra active of uent releae.- 5 rt shall inciu a summary of th quan ties of ra osctive liquid gaseous effl nts and solid wa e re ased from unit as out1. ed in Pegulato Guide 1.21, " Mea ring,
- aluating, Reporting Ra osctivi y in so d wastes and Re1 ses of Radioacti Materials in L id and seous ffluents from Li t-water-cool Nuclear r P!. ants,"
ision 1 1
4, with data e iaod on a quart ly basis follow gthefosk, tt of prendia 5 thereo 9
T radioactive of uent re a re et shall include annual summa of ourly meteoro1 cal dat oc over the previ e year. This ual suassary may be ither fo of an hour-by-h r listing of w d speed, wind directi, and a er stability, and ecipitation (i measured) magnetic t
, or in t to of joint freque distribution of wind e wind dir ion, and atmos eric stability.
report shall nelude an l
asses nt of the radia on doses due to radioactive guid and g oous effl nts released fr the unit or sta on during the evious cal dar year.
Th report shall al include an asse at of the ta ation dosa from l
dioactive liqui and gaseous effl nts to MEMBERS TER PUBLI due to the activities insi the SITE SOUND (Figure 5.1.1-during t report port All assumpti used in making ee assessments i.e.,
spec ic activity exposure t and location, e 11 1=e included these re
- s. The his rical annual a ege esteorology the meteorolog al conditi e concurren with the t of release of r osctive materia in gaseou effluents (
dote by sempling equency and sea t) e 1 he used to det ing the g pathway doses. he asses t of radiati doses shal performed La ac with the SITE DOSE TION AL (ODCM).
Radioactive B luent Release et shall tify those adiological l
environmental s le parameters locati re it is possible practicable t contiamo to okt samples o the media of boice at t most desired loc Lam or time. In ition, t cause of the vallabili of samples f the pathway he new loc ion (s) for aining rep 1 ement samples hould be identif
. The should al include a r ised figur s) and table (e) e the 0008 flectLag t locatto e).
L Y
BOFE cREEE 6-13 Amendment No.
ADMI:n3TRATIVE CONTROLS eanram nFFt.
e,eaer 33;=.
(Continu )
The adioactiv offluent re ase report all also i ude an a esament r istion do e to the li ly most om sad MINAER TER PUBL from re ter 1
eleases other near uranium f I cycle sou es (inct ng doses rom f
primary fluent path ye and dir t radiation for the tous 12 con ive months show conf ce with CPR 190, avironneT al Radi ion Protect n Standar for Nuclear r Oper Lon Acc able moth fo calculati he dose e tribution f liquid gaseous ffluents ar von in tory Gui 1.109, Rev.
The radi etive off nt release rt shal include t following into ion for e class of id waste defined 10 CPR 61 shipped offs e during report ye ods
/
, fj a.
tainer vol b.
otal curie antit ify whethe determined esasur or estimate),
Princi radi t weify ther dote ined by me rament or est e),
d.
of w
(
g.,
spent r in, compa dry waste, sporator t,
e.
of con iner (e.g.,
, Type A Type 8, Quantity),
d f.
Solidific ion agent (
.g., cement uros formal hyde).
Th radioactive ffluent rol se report all include aplanned re ases from I
e site to t UNRESTRI AREA of r ioactive sa rials in gas us and liquid effl nts on a qu erly basi.
The rad active off1 at release oport shall clude any c ges to the l
PROCE CONTROL P RAM (PCP), FPSITE D083 TION AL (00CM) or
)
duringtht/oportingper rad active wast systems ma j
MONTELY OPERATING REPORTE 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be suhaitted on a monthly basis to the U.S. Muslear Regulatory casenission,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.
CQER Q2ERATIEE 11XITE EXPQRT 6.9.1.9 core operating limits shall be established and documented in the PSE&G generated CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technical Specifiestions:
3/4.2.1 AVERAos PIAEAR LINEAR EIAT GENERATION RATE 3/4.2.3 MINIMUM CRITICAL POWER RATIO 3/4.2.4 LINEAR REAT GENERATICE RATE
[
morE CREER 6-20 h at No.
r.
l ADM8N857 RAT 8VE CONTROLS PECORD RETENTION (Continued) h.
Records of annual physical inventory of all sealed source material :f record.
6.10.3 The following records shall be retained for the duration of the uni:
Operating License:
Records and drawing changes reflecting unit design modifications ade ::
a.
systems end equipment described in the Final Safety Analysis Repert.
b.
Records of new and arradiated fuel inventory, fuel transfers, and assembly burnup histories, Records of radiation eeposure for all individuals entering radia:
c.
1:n control areas.
i d.
Records cf gaseous and 11guld radioactive material released to the i
environs.
j Records of transient or operational cycles for enese unit e.
components identified in Table 5.1.1-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the uni staff.
h.
Reccrds of inservice inspections performed pursuant to these Te:r.nl:a; Specifications.
Records of quality assurance activities required by the Qualt:y 1.
Assurance Program.
Records of reviews performed for changes made to procedures or equip en er reviews of tests and experiments pursuant :o 10 CFR 50.59 i
- n..
Records of SCRC meetings and activities of the Nuclear Review Beard and j
activities of its predecessor, the Offsite Safety Review (CSRI staff l
1.
Rec =rds of the snubber service lif e monitoring pursuant :o Technt:a; Specification 4.7 5 Records of analyses required by the radiological environmental m
m.cnttoring program which would perm 1: evaluation of :he sc:uracy :f :n=
analyses at a later date This should include procedures effe::1ce a:
specified times and "A re:ctds showing that these procedures sere
,,LNb felicwed.
FL rs, f 11 :A*'!AT*0N 7POTE**"!!N Fr VM 6.;;.; Pr:cedures f:r perscnte1 radiation protection shall be prepared ::nsister si:n the requirements of 10..R Part 20 and shall be approved, maintained, an:
adhered to f er all Operations involving personnel radiation exposure.
HOPE OREEA 6 22 Amendment N: '
s-7 1
LCR H99-02 i
.\\
INSERT F 1
n.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATIONAL MANUAL and the PROCESS CONTROL PROGRAM.
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i j
i
T ADMINISTRATIVE CONTROL 3 assessessesseeessessess...................................,,,,,,,,,,,,,,,,,,,
6.13 PROCESS CONT!OL PROGRAM fPCP)
I (6.13. F Ine PCP 1all be ap vec by th Conuna ssion rior to plementati W
6.13.2 Lie see initia changes t the PCP:
h*
Shall be itted to a Conunissi 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 eso to totally upport the ratio e for the nge o
benefit o additional l
sup ementa) int ti b.
A eterminatio tha ange did no reduce the o erall onformance th a ied waste oduct to exi ing criteri for solid stes Document 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 O C.
6.14 OFFSITE DOSE CALCULATION MANUMg (ODCM)
.14.~1 i
vocM shall e approves can w -assa prior to i lementation.
6.14 Licensee i ciated chan s to the ODCM-4]5[
1.
Shal be submitted o the Co
'on in the Ra loactive Effl ent Re ase Report f the pert which the e nge (s) was e.
This ittal shal contain:
a.
Suffic ently det I nformation totally sup rt the rati ale for the nge without enefit of add' ional or su lemental info tien.
Inf tion submit d should cc ist a package of hose pages o the CDCM to changed wit each page numbered nd provided th an approva and date bo,
together wit appropriate alyses or ev untions just fying the change (s);
b.
A determ atton that e change will et reduce th accuracy o reliab icy of dose alculations or etpoint dete ination:
d c.
Docum ntation of t fact that th change has b n reviewed and e
b
~ foy acceptable y the SORC.
2.
Sha ecome offe ave upon revie and acceptan by the SC C.
d A BOW "10 tJGES *O RA0!?ACI*.'E *.!OU2b SASEOUS AND SOLID WASTE ""AEATVEh*"'
I S v.l TE"S f 5 Licensee 1 tasted ma;or.* nges to the r loactive w see system 21d. gaseou and solidt:
.4 j
1.
Sha be reported to M Conwnissio in the UFS for the p tod in 1
w.ch the evaluati was retiewed y SORC.
" e discussi of each j
.hange shall con-in-
/
HOPE CREEK 6.:4 Amendment No.
t
I LCR H99-02.
lNSERT G l
i 6.13 PROCESS CONTROL PROGRAM (PCP)
Changes' to the PCPi l
a.
Shall be documented and records of reviews performed shall be retained as 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.
l b.
Shall become effective after revmw and acceptance by the SORC and the
^
approval of the Plant General Manager.
INSERT H 6.14 OFFSITE DOSE CALCULATIONAL MANAUAL (ODCM)
Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as 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 equired 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 calculations.
b.
Shall become effective after review and acceptance by the SORC and the approval of the Plant General Manager.
c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent l_
Release Report for the period of the report in which any change to the ODCM was l
made. Each change shall be identified by markings in the page that was 4
changed, and shall indicate the date (e.g., month / year) the change was implemented.
i
.m
1 I
ADMINIST IVE CONT S
MAJOR HANGES TO 10ACT
- LIQUIO, SE005 SOLI WASTE EATMENT!
SYSTEMS (Contin d)
/
a.
As of the valuatiory'that 1 d to th deterni ation t t the e nge coul be made n accor ance w 'h 10 CF 50.59; Suf icient ailed in reati to tot ly supp rt the ason f
the cha go witho benef of ad tional suppi ntal nformati c.
A data ed descr tion o the eq paent, onen and proce es invol ed and he inte faces wi other lant sy eas; d.
An valuatio of the change, ich sh the edicted r leases o radica iv ma rials in iquid d gaseo s ffluents and/or ar f solid aste th differ from those p viously pr i
d in the iconse pplicat n and amen ts the t e.
An aluati o
- change, ich sh s the e acted max um e osures ual in t unres icted a and to e
neral o
that dif er from those p viously e inated in the plicatio and as doents reto; f
Ae ar s f the pred eted r leases f radioac ve sat tals, liquid d gase s eff1 nts and i solid wast,
t the act I releas for t e perio prior to hen the anges to be a de; An est ' ate of t expos re to p ant opera ng personn as a g.
m resu of the e ange; d
h.
Do umentatio of the fact th t the ch ge was rev d and und accep le b the 50 55 1 become fectiv upon r view an acceptance y the 50R.
ga
.p m,g,,muray BLwK l
t HOPE CREEK 6-25 AmendmentNo.g
?Nn ei m 1T! N t,
3ASE5
'*CN!?! RING INSTRGENTATICM 'Contanu+1) 3's 1 -a The matortal originally contained in Section 3/4.3.7.8 was deleted with tne tasuance of the Full Power license.
Mosever, to maintain numertcal continutty between'the succeedang ee=ttons and existtag station procedural references to those Technical specificattons sections 3/4.3.7.s has been intenttonally left blank.
3/a 1 5 s toesr.pA.AT SETEC*tCN SYS me
" MIS SECT CN OELETED U4 3 7 is s.Af !CAc"!*.T t.!OtMS E FFtiTN" 44CNf ?cRIMC INSTRtMENTATICN 7
radica ave la d efflu nito ng inst neat' n as pr ided to
- onta e and e trol. 4 applica e,
n esses o radios ive met tais tn 11 ad et fi-nts du g actua or palu tal rol ses of quid of uents.
e i
. a rm/ t,
potats or tTese nat a shall cal ated an 43usted accord ce wtth he meth 1
r parames e in t occM to ensure t the als trap wt occur p or o coeding a limi of 10 Part 20 The k
OP ILI.
nd use o this t trument on is isten with the quirem ts of Ce al Des Crtte a 60. 6 and 64 f Appendi A to 10 C Tart $
3>4 1
11 uSICAc Ivt CAfy EFFLUElff MQWITORING INSTRGuntrATIQM f
- Th radtea ve gaseo effl t monito ng inst tation t provided to mo tor an control, a appl able, th releases o radioacts material in seous fluents ring a al or ents/1rol ses of ga ous efflu ts.
T ala trip seep nts to these in rume i
s 1 be cal ated and d3ust in accor ce wt the met 1
rameters a the This
- til naure th alarm /t p will o ur exceeding he Itmits f to crR Pa 23.
Th inst ntation so a provisio for montt ing and entrollan the es entra; ton of 11y emplos e gas six res in t atn con naar o gas treat at s a
The CP LITY and e of thi
- .n s t r neact is conste t wtth t requar a of Gene 1 Destyn etterta 63 and of Ap A to 10 FR part 50
,)
}
D 6 LG l C:.C HCFE CREEK 3 3/4 36 A**"d"*"E
- g.
,k
3/4.11 RADI0 ACTIVE EFFLUENTS j
_ BASES l
$ G w m.D 3/4.11.1i LIQUID EFFLUENTY 3/4.11.1 1 CONCENTRA This specifi tion is pr vided to e ure that he concen atfon of
~
radioactive mat ials role ed in liqu waste e luents to RESTRICTED EAS will be less an the co entration vels spe fied in 10 FR Part 20, open-dix B,.Tabl I, Col This 1 itation ov des ad icnal assur.ce that
/ the level f radios we materi s in bod so water n UNRESTRIC AREAS will re t in exp res withi (1) the etic I.A esign objec ves of Ap n-clx I, O CFR Par 50, to a MBER OF T P
(2) the li ts of 10 R
Part 0.106(e) the popu tion.
Th co ra on limit for dissolved en ained nob gases is ased upo he a on that Xe-is the ntrol-r ng radiof tope and s MPC in r(
on) was conv ted to a equival it concentr on in wat using th met yp/c d
cribed in I rnationa Commiss n 7 on Radi ogical Pr action (I P)
G ion 2.
The requir d detecti capabiPi es for radio tive sat fals in iquid w te sample are tabul ed in te of the lowe limits o detecti (LLDs),
etailed d cussion o the LLD, d other date ion lial can be ound in
- Currie, A., "L Limit of etection:
D inition Elabor ion of a Propos Position or Radio 1 ical Effluen and Envir neental asuremen l NURE R-4007 ( ptember 1984), and in t Urearlsed annu y).
/
HASLPryedures ual, HASL 00 3/4.11.1.2
<T This specif ation is prov ded to i ement t requirene s of Sections II.A.
I.A, and IV.
of Appen x I, 10 R Part 50.
The Limi ng Condition for peration lap nts th guides s forth in ection II of Appendix I.
The ACTION s tements ovide th required o rating f1 xibility and at t same time i seent th guigess forth in etion IV.
of Appen-dix I assure that releas of f di ctive mater al in liq' d effluent to U STRICTED ARE will be nkid"w as is rea onably ac evable."
so, opt for resh water s es with er supplies hat can potentia 11 octed by pla operati s, t re' reasonabl assurance hat the op ation of the facili will no resul adionucli concentra ons in the inished drinking we r that a in e c of the req resents of 40 CFR Part 41.
The f
dose calc ation se parameters n the 00 implement e require-ments i Section ndix ! that onfonnanc with the g des of Appes x I be s lational p edures ba d on models nd data, su thay'the actu expos f a MDGER 0 THE PUBL through ap opriate pat ays W unlikely be subs ntially unde stimated.
The equatio s specified n the
,00CM for e culating doses due o the act I release r es of radio tive material in 11gui effluents er consisten with the se dology prov ded in Regula ry Guide
.109, "Calcul ion of ual Doses to n from Rou ne Rele es of Re or Effluents or the Pu ose of Eval ting Compli ce with FR Par.t 5, Appendix I," Revision, October 197 and Regulat Guide 1.113, tisatin quatic Disper ton of Eff uents 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
RADICACTIVE EFFLUENTS BASES D3av=.: rt=D 3/4.11.1.3 b VID R46 WASTE /REATMENT S dTEM 1
l The 0 hAABIL Y of liquid r a to t eatment s tem ens es that th system w I be a allabl for use wh new i uid efflu nts requ re trea' in
{
prior t their elease o the env o The requi ement t t the app riate porti s of t s sys1 be used, hen e ified, pr ides as rance that he rol ses of edioac ve materi si J id efflue s will e kept "as w as 1
is easona y acht vable." T ss cation i lesents he require nts of neral sign C terion 60 f d
A to 10 FR Part 0 and the sign objecti give in Section I pendix !
10 CFR art 50.
T specified limit govern the use f ate porti ns of t liquid ra aste treat nt syst were pecified a a suit b 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 HOLDUP TANKS i
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 f
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 B, 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 rue i a rso 3/4.11.2.1 I DOSE RATE N s speciff ation is rovided to nsure that e dose any time and beyon the SITE Y rom gaseous ffluents fr all un s on the : te will be thin the nnual do limits of 0 CFR Part to UNRE RICTED AR 5.
The an al dose sits are doses a ociated wit the conc ntrations 10 CFR P rt 20, Ap ndix 8, able II, Co Thes limits p vide reas able ssurance ut radt tive mater al d in gase s effluent will not result i the expo re of a ER E
LIC in a UNRESTRICT
- AREA, either thin or side the TE Y to annua average e centration exceed ng the 1 fts'speciff in ndi
- 8. Table II of 10 CF Part 20 (10 R Part 2.106(b)).
F r ME OF THE PUBL who say a times be thin the ITE SOUN ARY, the oc any t
MEMER THE PUBLI will usua y be su ficienti low to c sat (
ra increase n the stao pheric dif usion ctor abo that for S
RY.
Ex les of cal lations f such EMBERS 0 THE PUBLIC wi t
ap opriate cupancy fa ors, shal be given i
in the CM.
The s ift lea e rate 11 ts restric, at all mes, the corres nding g and beta dos rates a e backgrou d to a ER OF THE PUBLI at or beyo the SITE ARY to ess than or equal to 0 nress/ year to total or to less an or eq 1 to 3000 eas/ year o the skin.
j HOPE CREEK 8 3/4 11-2
t RAD 10ACT!vE EFFLUENTS 6ASES DOSE RATE (Co tinued)
These rol se rate li its also r trict, at 1 times, he corre onding thyroid se rate a ve backgro d to y chi d via the inhalatio less t pathway t n or equal to 1500 mre s/ year.g The requir d detection capabi for rad active a erials in aseous w te samples re tabulat in te f the i r limits detectio (LL0s).
etailed dis ssion of eL ther det tion limi s can be und in Currie, L.
" Lower mit etion:
0 finition d Elabora ion of a Proposed osition fo tadio Effluent and Envir neental NUREG/C 4007 (Sep er 1984) and in t NASL Pro dures Man al, HASL-O surement,"
t(revis annually) g a ren
/
3/4.11.2.2 10057 - N08LE G45ES i
This sp ification s provide to impi nt the r ufrement of Sections !
- 8. III.A, nd IV.A o Appendix, 10 CFR rt 50.
e Limiti Condition or Operat n imp 1 ts the gu es set f th in Se ion II.8 Appendi I.
The AC ON stat nts provi the req red oper ing flexi ility 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 radica tive to al in ga ous efflu nts to UNR TRICTED A AS will b kept "as ow a /
asonably achievabl." The sur-j v 11ance Re trements i lesent t e req nts in S tion III.
of Appenoiv'.
at confo nce with e guides f App I be sh n by cale ational pro 'e-dures base on model and data ch th e actual xposure o a MEM8ER OF THE PU8L1 through pppropriate pathw unlikel to be sub antia11y u e r-estimate'd.
The defe calculation a[f) logy and arameters stablished n the 00CM for calculaJdng the do/es Yo he actua release r tes of radi etive nob 1r# gases in gaseous effiue r consiste with the thodology ovided Reieases of /y duide 1.107, "C inTegulator ion of A ual Doses o Man from outine eactor Efffuents for the Purp e of Eval ting Compli ce with 10 CFR ParV50, Appe in I," Re sion 1 tober 197 and Regulat ry Guide 1. 11
" Methods e Estina ng Atmos ric Tra rt and D spersion of aseous Eff ent-in Rout Release from Lig -Water C led React s," Revisio
- 1. July 19 The equatio provide for este ning the r doses at nd beyond e
tSITEAUNDARYa based n the hi orical av age atmosp ic conditig/is.
j 3/4.11.2.3 i D0st - 1003at-131. IQ0!NE-133. TgITIUM, AND MOIONUCLIDEVIN ARTICULATE / FORM Thi 4pecifi tion is p vided lesent the equirement of Sectio II.C I
.A and IV A of Ap x I, 10 CFR art 50.
T Limiting t
Condi ions for peration e the g s set forth n Section
.C of Append x I.
The CTION st esents p vide t utred opera ng flexibi ty and at t s
time i esent t guides e forth in Sec ion IV.A of Appendix I t sure tha the role as of r etive eater is in gase 's affluents o UNRESTRI D AREAS 11 be as low as i reasonably achievable." The ODCM ca ulational methods ified in tn Surveilla Requirement ~1mplement iN i
HOPE CREEK 8 3/4 11-3
l RADIOACTIVE EFTLUENTS BASES PARTICT Jb"E FCRM f Dost - Iobi - 1[1, TODINEI33. TRITIl d AND RADIO lC' ID ES I (Continued)
/
the requi nts in 8 ction III.A f Appendi I that co.ormance ich the guides o ndix shown b calculatio al procedu es based n models a data, e that th actual e ure of a ER OF PUBLIC $ rough appr late pathw s is unli ly to be s stantiall underesexfnated. The DCM cale ational m logy a paramete for cal sting th doses due the act al release ates of th subject erials ar consiste with the hodology p ovided in gulatory ide 1.109, Calculat on of Annu Doses Man from outine Re1 ses of Re ter Efflue es for t Purpose o valuati ompliance ath 10 CFR art 0,
ndix I," Revision 1 October 1977 and latory ide 1.111, " Met af Estimat/hg Atmosphe ac Transpor and Dis raion of G secus Ef fl nts i Ane Releasfes from L1 t-Water-Coole eactors,* evision 1, uly 7
hose equagtens also ovide for date ning the cual doses ased n he histo cal averag atmospheri cc ations. The release ra spec sc tons for edine-131, odine-133, t
trum, and dionuclide in pa ate form ith half 1 es greater han 8 ays are dep dont upon e ex c radionue de pathway to man, in he areas at beyond tb SIT Y. The p hways that era examan d in the develop of these leu tod were: (1) ndividual nhalation o airborne radionu ides, (2) posit
' radionue es onto gr en leafy v etation with a sequent co umption n,
(3) position e o grassy a as where milk imals and at produe g animals g, raze with nsumption the milk phd f
maa by man, an (4) deposit on on the. ground wit subsequent xposure of Wan.
^
h 7bT 7
11.2 4 AMD' 3 /4.11. 2 NGASECUS RADWASTE TREA" MENT AND VENTILATION EX 3/4 The PERA32LITY f the GAS US RADWAS TREA'iMENT STDI and tb VENTILA.cef EXHAUST TMENT JTSTEM neur that the stem will available
}
for us whenever g seous ef fl, dents r 1r treatment rior to rel ase to the env1
- t. The equiremen that t p repriate p tions of th se systems -
use, when spec led, prov es rea e assurane that the r eases of radioactive ma artals in aseous 1 nts will b kept *as 1 as is r4asonably a ' levable.*
1s spe 1 tien imple ents the re trements o eneral Des Criteri 60 of A dix A to 1 CFR Part 50 and the de gn J
Appendix to 10 CFR rt 50. The objectives given in S ceton of appropy'iate portie of the sys ens were speciti as a sui le fr t e of the dos 4 design ob) etives set reh in l
specifie limits gov rning dix I, 10 C/R Part 50, or gaseous fluents Sections 11.5 and tI.C of
/
f L
l j
3/4.11.2.E DELETED I
Amendment No B 3/4 11 4 HOPE CREEE i
I
RADIOACTIVE EFFLUENTS BASES 3/4.11,2.7 MAIN CONDENSER 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 effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
Du Le,~TGD -
s 3/4.11.2 NTING OR b CI Th specificat' n provides essonable surance t releas rom d ell l
pur ng operatic will not coed the a al dose its of 1 FR Par 20 UNRESTRICT AREAS.
DLCT O 3/4.11.
SoldD RADICAC*7YE WASTE TRTINENT p This ecificatio implements he re ir ents of G eral De gn Criter'on 60 of pendix A t 10 CFR Par 50.
ocess par ters i luded in esta 1shing the ROCESS CO L PR y inclu but a not limi d to wa e type, was e pH, waste aquid ification agent /ca alyst rat s, waste o
- content, ste princt 1 ch constitue s, and. xing and ring 1mes.
The urpose of phe PRO NTROL PR RAM is provide ality (assurance hat the solidified was meets 1 CFR Par 61 require ents.
DM 3/4.11 TOTAL DOSE
/
/
This specifi tion is pr ided to et the se limitat'ons of 40 CFR Part 190 that have een inco ated ant 10 CFR P rt 20 by 4 FR 18525 The specificati requires e prepara son and ittal of a Specta Report whenever t e calculat doses fr plant nerated ra oactive ffluents an to [/
direct r lation axe ed 25 mre he otal body any org except th thyrot which sha be limi d to than or e al to 75 rems.
For tes cent ning up to reactors it i hly unlike that t resultant se to a
ER OF PUBLIC wi exce he dose li te of 40 FR Part 190 f the
)
i dividual r ctors r n wgt twice the se desi objectives o Appendix y from the r actor uni s including
, and if rect radi ion taide storage e a, etc.
re t
11.
The eetal Re rt will des ibe a course i
i of acti that a d resu in the lim atton of he annual do to a MEMBER OF TH PUBLIC to thin 40 CFR Par 190 limi s.
For the p rposes of the Spe al Report it may assumed t the dos commitment t the MEMBER OF
/
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i 1
l MOPE CREEK 3 L/4 11-5 Amendment No.
m
BRA 010CTIVEEFFLUENT[
BASES 1
TOTAL 005 ontinued THE P LIC from o er uranium el cy e sou es is nog gible, wit theexcep/
tio that dose ntributions com ot r nu ear fuel cle facili es at th s e site or hin a radi of 8 st e consid ed.
If th dose to a EM8ER OF T PU8LIC is e imated eed the r utrements 40 CFR P t 190, the Specia Report with reque f r a variance (provided t release ndi-tions re Iting in vi ation o R Part 19 have not a eady bee errectec)'
in acc dance with e pro s f 40 CFR rt 190.11 d 10 CFR rt 20.a05c,-
is e sidered to a time e est and f fills the r quirement of 40 CFR relates to M '
Pa 190 until C sta is compip ed.
The v iance oni mits of 40 R Part d dcas nop apply in ay/way to the other requ /e-ments for d a limitatt f 10 CFR Part 20, as afdressed i pacifica-tions 3.1),.1.1 and 3.11.
1.
An individual is t conside d a MEMBER THE PUBLIC ddring any peri in which,rhe/she is e aged in c,arrying out a opera-tion at is part he nuclear fuel cycle, v
/
7Ab.5 PAcha nvr.auscwAuy B % (
HOPE CREEK g 3/4 11 6
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 8ASES D6t1= leo 3/4.12.1fMONITORINGPRQdAM The radiologica environment monitori program utred by is specification prov es represen tive acas ements of adiation d of radi f
active materials n those exp ure pathw and for hose radio clides th t f
i lead to the hi est potenti radiation xposures f MEM8ERS THE PUBL resulting fr the statio operation.
This mon oring pro an impleme sSection IV
.2 of Appen x I to 10 R Part 5 and there supplemen s the radiolo al effluent nitoring ogram by erifying t the sea rable concen ations of r ioactive a erials a levals of adiation e not hig'hir s
than xpected on a basis of he efflu t measure ts and th modeling f th environment exposure thways.
ui nce fo this moni ring prog m is ovided by t Radiologi 1 Assess nt nch chnical P ition on viron-mental Moni ring, Revi on 1, Nov er The initi ly specif d monitor ~
ing progr will be e active f at 1M e first 3 ears of c rcial operati Followi this per od, qt changes be initi ed based on opera onal exper nee.
The requ ed detect nc fes for e ronmental ample anal es re tabulat in term f
limits of detection LDs).
The Ds
' required Table 4
.1 nsidered o imum for utine envir ntal measure nts in i, stri poratories. / t should recognize LLO i hat the defined af an a. priop$ (before tbd fact) li t represent g the capp'/
bil y of a me urement s tem and no Vas an a p teriori (af r the fac)4 1
it for a rticular asurement. /
~
/
Det led discu ion of the LD, and o er detectio limits, c e found in Cur e, L. A.,
ower Limi of Detecti Definit n and Ela ration of a Prop ed Positi for Radio gical Eff1 nt and Env onnental asurements,"
NU G/CR-4007 eptember
), and i the HASL P cedures ual, HASL-300 evised an ally).
i D e.\\.e7EO --
J 3/4.12.2TLANDUSECidSUS 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 monitorin prog ar made if requir by the
/
e results of his census The best formp n
on the door-to-oor survey, from aer 1 survey, om visual rvey A r
consulting wi local agric tural thorities 11 be use.
Tbi can s satisfies th requirements f Sect n IV,.8.3 o Appendix I o1 L P t 50.
Restric ng the censu to gar-d of greate than 50 m8 rovi s rance that sig icant expos e pathways a leafy ve tables wil e
f d and monitored ince a garde of this size is t minimum re tre o
uce the quantit (26 kg/ year) f leafy vege-tables aptumed in Repe atory 1.109 for cons tion by a c Id.
To deter-mine tpfs minimum rden size, e following as tions were de:
(1) 20% of the pdrden was u d for grow broad leaf we tation (i.e., similar to lettuce anycabbage),
d (2) a ve ation yield of kg/m8 HOPE CREEK 8 3/4 12-1
I 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES y a, c. -n-u 1
3/4.12.3 k TE d BORATORYPARIS 0NPR9 DRAM s
('~~ The r utrement f r participa oningnap oved Interia ratory Com risor Program provided o ensure th inde @n checks on th precision d accu-racy the measu ments of ra cactiv t ial in envir ntal sam e mat ces are pe ormed as pa of a ty assurance rogram for nviron-al monit ng in order od ra that the re its are va d for the rposes of action IV.
of e di I to 10 CFR rt 50.
L i
l i
I HOPE CREEK y 3,4 1,_2
gARIAACTfW EFFLUENTS VETIM GR MBRIM 3.//.2 8 Dd2 6-r@
rtranrus c=rTras sefortaATION [
/
/
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3.11.2.3 or PUR$1m the Mark I c tainment dr 11 shall rough either the eter buildi entilation s an er the f tration, r eculation and vent tien systes.*
i ILITY:
the t is er purged, s.
ith the regu of the specift ten not sat fled, suspend all IM and IM of the d 11.
b.
The siens of fication 3.0 are not app le.
j SE Vtiti t arettiRENENT 4
.8 The conta shall be temined to aligned for Im er IM through reacter buil ng ventilati system, the fi
- ation, irculation ventilation tem, or rdened torus within 4
{
prior to s of and at 1 ence per 1 during er MARIM e the drywe
{
j i
1 l
j
\\
- Fell ng Type A ated Leak tate Testi Mark I inment /
de 11 may to through rdened y
A"d"'"" "** 58 Mpt caER 3/4 11-18
RA0!0 ACTIVE EFFLUENTS
-~xg-s re;D -
3/4.11.3js0LIORADIp(CTIVEWASTETBENMENT f" LIMITING CONDI FOR OPERAT t
/
- 3. ;1. 3 adioactive w es snail be LIDIFIE0 or d atered in ace c4nce ;
tne OCE55 CONTR0 OGRAM to m shipping and ansportation cuiremer s ing transit,.
d discosal site.-
e requirements en received the cisco APPLICAB iTY:
At all imas.
ACTd
/ a.
With LIDIFICATION or ewat Ing no eting dis sal site a,
s ping and transo atio uir nts, susp a shipment
- e nace.quately pro. sed a
correct th PROCESS C0 ROL %;ur the procedures d/o 01 recurrence.
waste sys as neces to pre.
b.
With SQL FI or aterin perfonned accordan witn RAM,(1)g the P S5 lN P
f4trate test or lysis tha he i rc r1 processed te in etc.
ontainer ts the utrements or ransoortat n to the d Osal site nd for rece'.
at the dispos site and take appr riate ads strative ac :n ::
prevent ce rence.
c.
~ The pro sfons of 5 ification
.0.3 are n applicable.
/
SURVEIL REQUIREME
/
4.
. 3.1 The P ESS CONT PROGRAM s 1 be fell to verify t t the ora-rties of t packaged te meet t sinimum stab ity requi ts of 10 0 9 Part 61 an other requ nts for ansportatio the dispo site anc e caipt a he disposa site.
4.
. 3. 2 The P SS CONT PROGRAM sha' include suf cient qualit ontrol d ast wince thods to sure the sol
' find wasta t from a process (either in-e er acted vendor meets the irements for ransporta-tion and eipt at disposal s
~
(a HOPE CREEK 3/4 11-19 Amendment No.
RADI0 ACTIVE EFFLUENTS DErLe. r 3/4.11.4 707;,;.
,;;6dD LIMITiNGCONDITION OPERATION 3.11.4 Th annual (cale r year) dose e dose commi THE PUB due to role es of radioa-vity and to diation from ranium fuel nt to any M ER OF cyc1 ources sna11 limited to ss than or e 1 to 25 mree to tne tota bo or any orga except the.t raid, which s 1 oe limite o less tha ual to 75 mr s.
r APPLICABI At all es.
ACTI
[
[ a.
With a calculated ses from h
lease of r osctive na rials in guid or gase efflugh t' eding twie he limits Specifi-tion 3.11.1.2., 3.1
- 1. W.
.11.2.2a.,
1.2.26.,
. 1.2.3a.,
3.11.2.3b.,
cula
/
d be made luding di t radiatto contributi sf
< s includin utside sto go tanks, c.
to date ne above limi of Specifi tion 3.11.
have been coeded.
is the ca
, prepare subatt he Coe-mi on within 30 ys, pursuan to Specifi tion 6.9.
a Special port that def s the corr ive actio o be take reduce sub-sequent relta s to preven recurtenc f exceedin the above li s
and includ the schedul for achie ' g confo a with the ve limits.
is Special sport, as fined in CFR 20.405c all inclu an analysis hat esti s the rad ion exposure, dose) to a ME OF THE PU C from ur tus fuel e e sources, i luding all e
luent pathw s and dir radiatio for the cale r year that neludes the elease(s) overed by is report.
I shall also d scribe le (s of rad ion and c entrations o adioactive erial involv
, r 4 the use of the xposure level or concentra ns.
If the ima. J (s) excee the above 11 s, and if t lease co ition y ting in vi ation of 40 C Part 190 has t already en corre 4 1, the 5 al Report sh include a st for a va ance in cortlance the provisi s of 40 CFR P 190.
Subai al of th port is idered a'ti y request, a a variance i gra ed unti', s f action on request is late.
b.
e provist' of Specific on 3. 0. 3 a re t applicable 5
EILLANCE R EENTS 4.11.4.
Cumulative d e contributio from liquid gaseous afflue shall be d ermined in ac dance with 5 fications 4.
.1.2, 4.11.2.2, d 4.11.2.3, a
in accordance th the metho ogy and par ers in the 00CM.
4.11.4.2 Cu ative dose co ributions fr direct radiatio ros the units including tside storage nks, etc. sn be determined accordance with
.the met cology and par ters in the M.
This requir nt is applicable j
only der conditior.s et forth in ecification 3.11
, ACTION a.
g HOPE CREEK
/
^
3/4 11-20 Amendment No. [,,
I
3/4.12 4AD!0 LOGICAL EWIA08pENTAL WNITORIE D eva rei a 3/4.12.1
"^E:***:t ^^::=a
/
r uL4m-d,(.An /
/
/ 7
'- s,e # ed a' a.le ;. r '.
a' - ' ri= >r -
aan -ted r
APPL!?A8!LI : At cil aer,.
g:
a.
With radiologi:
envi 1 monitor n6 preer t being'
/
ce ted as spec ted in Te 3.12.1-1 prppare suteft to t isaten,.in Annual R telegical avteenman Operating rt tred by ifi'etieH
. 7, a scripti f the pgggg for
\\
not conduc the p regu and lans for p enting jW a recur a.
b.
With level of edi tIV as the uit of plan effluents i an avironmenta s I'
la 3.12.
when aver
,over any lendar; fim at a ified loc ten exceeti reperti e
quarter, p s
it to ti.
assission w in 30 days pursuant!
to Specif 9. a fasci Report the dentifies t cause(s) for enc di sit (s) fines the crective ac ons to be-t take toective fluents se t the se. tal annual so to A 0F THE LIC is les the cal r year li ts Specifica ens 3. H.
. 3. u.2.2 and 3. u.2.3 when aere an one of tra tenucli s in Tele
.1-2 are ted in t saapit tun, th report she be submit f:
concentrat on G )
concentrati (2?
.nly...,a>~v.,.n,n,,
., w
. > 1 o When redi 11 des e than these Tele 3.
are detecte and l
are the uit of p t effluents, is report 11 be sweet ed if the tal desea to A tt 0F LIC from radio-nut. des is to er greate then the andar year 11 to of ificati
- 3. u.1.2, 3.
.2, and 3
. 2. 3.
This et is not trod if asasured 1 el of radt twity was the result of plant off ts; however in such an
, the c ition small be /,
reporta and descrthee n the Radielegica Environmental Oper
.ng Report pv t to fication 4.9
.6.
c.
th silk er fre leafy v le saeple valiele free e or more of the s e locati required ele 3.12.1-1, i attry spectfic lac tens for ining rep 1 samples and es teve to the radiel ital envi ital sent ing progran vi 30 says.
'The setnade) used to stimata the tantial annual a to a M R @ M LIC s te indi se in this rt.
MOPE CREEK 1/4 12-1
l I
l
)
1 PAGES 3 / 4 12-2 THROUGH 12-12 INTENTIONALLY BLANK I
HOPE CREEK AMENDMENT NO.
i t
i
+
RA3ferwefc1L ENYT af. MON 2? ORT V 1IMITING ON FOR OPERAT (Continu e
(Continued The ific loca one from whi samples were available then lated fr he monitor progress. Fu ant to Spec ication
.9.1.4, i
ify the ca of the unava 111ty of s pies and identif new loca n(s) for obts og replac samples in the Radioacti ffluent Role Report pur ant to l
3 ification 6
.1.8 and also
- de in the et a revi igure(sy able for the r+ lecti he new loca n(s),
d.
The pr.
sions of Spec ca 3.0.
e not appl le.
SURVII CI REQUI
....p.....................................
logical and r ntal moni ing samples e 1 be collected 4.12.1 The ra pursuant t able 3.12.1-rom the spe ic locations en in the tabl ad figure (
in tho 00CM,,.
shall be lysed pursuan o the requir e of Tabl
.12.1-1 and cetection 111 ties r red by Table 4.
.1-1.
Q
)
i i M \\ s 7 hM i N R E. N T I O N A L L Y
~~B L M K NOPE CREEK
./4 12-2 Amendment No.
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$ N M N ~ T ( C N Q (,,,' T 3Qgg Taar n 12.1-1 teanti edi 7
Thati goggTrogg (1)
Specific par era of distanc and direction ector from t centerline of one reac r, and additio description era pertinent shall be provided r each and eve sample locati in Table 3.1.1-1 in a table and fi e(s) in the
. Refer to
-0133, " Pro tion of Radi ogical Effluent.echnical Speci cations for N lear Power Pla e,*
Oc ber 1978, and t Radiological essent Branc Teeknical Posi on, vision 1, Nov r 1979. Deviat ne are permi from the r red sampling sched e if specimens e unohtainab due to hasardo conditions, asonal unavail lity, malfun on of automati sampling ipment and at legitimate r sons. If spec e are unohtai le due to samp g equipment function, ove offort shal made complete corr ive action pr r to the end of he next saa ing All deviatio from the s ing schedule sh 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, at ines, it ma not be possible or pr icable to co inue to obtain amples of t media of choice at t most desired ation or time. n these ins ances suitabis specific ornative modi and 1 ations y be chosen or the particula pathway n question and pyrope to sub itutions na within 30 days the R iological Envi neenta ito ng Program von in the ODCM.
Pur ant to Specifi tion 6. 4 s
t in the n Radioactive l
9 E luont Release port do nta on for a ch go in the ODCM i luding revised figur (a) and f
the 00CN r lecting the new ocation(s) with support info ni neifying t cause of the un allability of samples e th wa justify the selection-the new location for n samples.
(2) One o more inst
.e, such as pressurised ibn ambere for suring and scording dose ate continu sly may be used' place of, o in ition to, int rating des ters. For the ses of thi abis, a hermoluminose t dosimete (TLD) is conside to be one osphors two I
or more phos ors 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 ch acteristics of specific ey em used and ould be e octed to sin optimum dos information w h minimal fa ng.
(3) rborne culate sample ters shall analysed for e beta radioacti y 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or ce after samp ng tid allow f radon and thoron ughter decay. I groes beta a vity in air iculate sample is gr ter than 10 t the yearly of control ler, gamma i
ic analysis e 1 he perto on the indiv al samples.
(4) amma isotopic lysis means identificat n and quantific ion of gamma-esnitti radionuclides at may be at ibutable to the ffluents from the f lity.
(5) The "u roam sample" 11 be taken a distance d significant inf1 nee of the die
. The
- stream
- sample all be taken an an ar beyond but the mixing no. "Uprtream" s les in an estuary et be taken f enough upstr to be beyond t plant influence. Salt water shall sampled only the receivi ater is utilised for recreations activities.
F
/
A8LE 3.12.1 7(Continued)
T NOTATION (6)A compo e sample is in which the entity (all t) of liquid Apled is p rtional to quantity of f ing liquid d in which t thod of ampling emplo d results in pecimen that representati of the quid flow.
this program osite saapi aliquots shal collected at time int als that are short rela ve to the c
+ ting perio in order assure obtai g a represen ive sample.
I (7)Gro ater samples all be taken n this sourc s tapped for rinking irrigation pu ses in areas re hydrau e gradient o recharge
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(8)The dose 11 be calcu ed o max organ and group, usin the t odology and p ame r the (9) harvest occur mor +
t.r once year, sampli shall be perfo d during each discrete arves.
. f har t occurs con nuously, sampli shall be f
monthly.
ention sha 1 be aid to incl samples of t rous and root food pr cts.
(
i t-4 i s PAGE l to TE:_.N Ti o t4 ALLY B L A14 W HOPE CREEK 3/4 12-8
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7d HOPE CREEK 3/4 12-10 Amendment No i
e
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@G 1 NW N T \\ Ob1 b.LLM BLM N TAS 4.12.1-1 ntinued TABLE TATIONS
/1)This I st does no mean that ly these clides at to be c sidered.
Othe peaks that re identif ble, tog er with ose of e above nuc ides, shall siso be an yzed and ported i the Annu Radiologic E ironmental perating R ort purs nt to Spe ficatio 6.9 l.6.
( Required de ection cap 111 ties f r thermo1 inescent dosimeters u d for environne, al measur nts shal be in acc dance w of Regul oty Guide
.13.
h the recome ndations (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 the*, will ield a ne co t, above s tem back ound tha will be etected wit 95% proba lity w' h only 5% robabili of f 1
conclu ng that a b1 h observa ion epresents "real" s nal. /
/Foraparicular sure h stem, w ch may inclu e radioch ical separat n:
G g
pV
.66 sb LLD =
V V 2.22 Y
exp(-
)
Where:
LD is the ' a prior lower limit f detecti n as define above, as picoeur es per. it mass or v lume, s
is e stand d deviation f the bac round count'ng rate or of tNec nting r te of a blan sample as appropriate as counts er
'1 minu e, E s the unting ef.fi ency, as unts per di ntegratio,
V is t sample siz in units mass or vo 2.2 is the ntabe of disin grations per minute pe picoeurie is the fract nal radi esical yiel, wnen ap icable, A is the ra osctive d ay constant or the p ticular ra enuclide
(,sec 1),
at for nvironnen 1 samples is he elaps time betw en sample colle ion, or e of the s 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.
HOPE CREEK 3/4 12-11
ABLE 4.12.1-1 /tontinued)
TAB TATIONS It shoul e recognized at the LLD ' d ined as a priori (bef e the fa limit repres ting the c bi of a asurement syst and
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not an a posterio (after th fact it r a particular asurement.
A yses shall be erformed i uch a ner hat the stated Ds will be chieved under utine cond ons as nally background luctuations unavoidable 11 sample zes pre nee of interferi
- nuclides, other unco rollable.c umst render these LL unachievabl In such ses, the c tributi g a ors shall be ide fled and de ribed in th nnual Radi ogical Envir mental Operating eport pursua to Spe fication 6
.1.6.
i
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TM \\ s Wm i t4 TEN n Ora Au.y. ~EthJ K e
HOPE CREEK 3/4 12-12
aanlo!micg 'Jrnamne:TAL Mc27-.gus ce Le Te.O 3/4.12.2
-~x-d IMITING CONDITION FOR ERATION
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............... f...
3.12.2 A land census shall conducted and e identify withi a distance of 5 (5 miles) the ocation in each o the 16 meteorel cal sectorg of nearest milk inal,tp) prod nearest esidence and t arest garden greater than 50 (500 ft ng broad leaf v tation.
- ftfff:
At al times.
a.
W a land cens identifying a 1 ation(s) that yi de a alculat or se commitment stor than the va es currently bein at n specification
.11.2.3, identif he new loc 1 the next Radios we 'IffluenY M e e Report,~'
l pure to pecifica..on 6.9
.7.
are b.
With n and use census i-nt.fying a locat n(s) that yiel a
cal ated dose or dos casusitment (via same exposur pathway) 2 greater than at location from w
-h samples are trently ing obtained in ecordance with 5 ification 3.1 i' add the n location (s) to e radiological e ironmental een,oring program within 30 da The sampling ation(s), exc1 ing the conte
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station 1 ton, having the owest calculat dose or dose casusitme (s), via the e exposure pathw, may be dele fron this itoring program fter October 31 f the year in ich this lan,use census was e ducted. purou to specifica on 6.9.1.s i ntify the new I ation(s) in the at Radioactiv Effluent l
1 ease Report a also include i the report a r ised figur s) and table for 00cM reflect the new loca n(s).
c.
The provi one of specific ion 3.0.3 are t applicabl.
SURVE!I.1AN IREMINTS
......n=....=
===.
4.12 The land use nous sna11 he nducted dur the growing ason at le t once per 12 he using that formation t t will provide best eeulte,'eest as a door to-door rvey, viou survey, seria survey, or by consulting loc agriculture au rities.
resulte of the and use census shall be inc in the Annu Radiologic Envitorusental rating Report pursuant t specificatioa 6
.1.4.
- Br d leaf vegetati sampling o t least three fferent kinds o ation may be rformed at SITE 300NDAR in each of two difforent d on sectors th the highest edicted D/Qs in teu of the garden s.
Specif ations for b leaf vegetation ampling in Table 3
.1-1, Part
.c.,
shall be f owed, includ lysis of control los.
J BOFE CRIII 3/4 13"13 A"*"d'*"I "**
i 4
RADIOLOGICAL ENVIR00 MENTAL MONITORING DE.UiE:.7E D 3/4.12,3 5 0 L'a^^^3;;; g ^=:!a===00 =
bLIMITkCONDITIONFM0PERATION
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3.12.3 Anal s shall be p ormed on rad active mater s supplied s part of an Inte ahoratory C rison Program hat has been rowed by Commissi Appl ASILITY: At I times.
ION:
a.
th analyses n being r Fo as requi above, rope the corrective ac ons o revent a r rence to the onnission in the Annu Radio Environment Operating Re rt pursuant to specif atio b.
The visions oF ocification.
3 are not licable.
/f SURVEIL E REQUIRE 5
f 4
.3 The In riaboratory arison Progr shall be ribed in th 00CM.
summary of he results o ined as part the above uired Inte laborato osparison Pr as shall be i luded in the nnual Radio gical Enviro ntal operatin eport pursua to Specifica on 6.9.1.6.
(
O SEP 2 81988 [
Amendment No.
HOPE CREEK 3/4 12-14 v
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