ML20112E363
| ML20112E363 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/22/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0473, RTR-NUREG-473 NUDOCS 8503260522 | |
| Download: ML20112E363 (75) | |
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O PS G Company Pudic Serwce E!ectric and Gas 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation March 22, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Enclosed for your review and incorporation into the HCGS Draft Technical Specifications are five (5) sets of the Radiological Effluent Technical Specifications.
The en-closed HCGS Radiological Ef fluent Technical Specifications comprise Sections 3/4.11 - Radioactive Effluents, and 3/4.12 - Radiological Environmental Monitoring, of the HCGS Draft Technical Specifications.
These pages are submitted as Revision 2 to the HCGS Draf t Technical Specifications previously submitted on January 17, 1985, and as updated on February 7, 1985 (letters from R.
L.
Mittl, PSE&G to A.
Schwencer, NRC).
Also included are copies of the updated HCGS Draf t Technical Specification List of Ef fective Pages (LEP).
The HCGS Radiological Ef fluent Technical Specifications have been developed from NUREG 0473, Rev.
3,
" Radiological Ef fluent Technical Specifications f or BWR's."
The Of f site Dose Calculation Manual (ODCM), containing the methodelogy and parameters to be used in the calculation of of f site doses due to radioactive liquid and gaseous efflu-ents pursuant to attached Specification Section 3.11.1.2, 3.11.2.2, and 3.11.2.3, will be submitted for NRC review by April 15, 1985.
h32&CK050000,4 22 850322
\\
A PDR The Energy People
% 4312 O'.')4 84 w
Director of Nuclear 2
3/22/85 Reactor Regulation The HCGS Process Control Program for the Solid Radioactive Waste Management System as required by Technical Specifica-tion Section 3.11.3, will be submitted for NRC review by May 1, 1985.
Should you have any_ questions in ' this regard, please contact us.
Very truly yours,
(
d ///
Attachment - HCGS Draf t Technical Specification Sections 3/4.11 and 3/4.12 (Five sets with LEP)
C D.
H. Wagner USNRC Licensing Project Manager A.
R.
Blough USNRC Senior Resident Inspector e
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OEFINITIONS SECTION 1.0 DEFINITIONS ME, 1.1 ACTI0N.....................................................
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'.2 AVERAGE PLANAR EXP05URE....................................
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1.3 AVERAGE PLANAR LINEAR NEAT GENERATION RATE.................
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1-1 1.5 CHANNEL CHECK...............:..............................
1-1 1.6 CHANNEL FUNCTIONAL TE5T....................................
1-1 1.7 ' CORE ALTERATION............................................
1-2 1.8 CORE MAXIMUM FRACTION OF LIMITING POWER SENSITY............ 1-2 1.9 CRITICAL POWER RATI0.......................................
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1.(ISCLATIONSYSTEMRESPONSETIME.............................
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- 1. g uMmMG CONTROL 200 PATnRN...............................
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- 1. sg.INEAR HEAT GENERATION RATE................................ 1-3 l 14 LOGIC sYsnM runCn0nAL Test...............................
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INDEX O
b DEFINITIONS i
SECTION DEFINITIONS (Continued)
PAGE z/r 1.y OPERABLE - 0PERABILITY.....................................
1-4
[l
- 2. s 1,24' OPERATIONAL CONDITION - C0NDITION..........................
1-4 Il lo.f 0NA#Tros!AL. MODG -M ODG s
- 9 1 4 PHYSICS TESTS..............................................
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RINARY CONTAIMENT INTEGRITY..............................
sr 1.JKRATEDTHERMALP0WER........................................
1-5 ll sc 1 7 REACTOR PROTECTION SYSTEM RESPONSE TIME....................
1-5 ll
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37 Event-1.)0' REPORTABLE-4G69RRENCE.....................................
1-5 ll
.58 1.)I'R000ENSITY................................................
1-5 ll 1.)( %GMY GAI.G.fstemeAaY do#^*m9 se a n n en. w u.o m
.n% INTEG R I TY............................
1-6 ll
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90 1.)5 SHUTDOWN MARGIN............................................
1-6 ll
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1-6 ll r
1.
THERMAL P0WER..............................................
1-6 ll s.. _.....
._,, R
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1.
TURSINE BYPASS SYSTEM RESPONSE TIME........................
1-7 l
47 1.M UN I DENTI F I ED LEAKAGE.......................................
1-7 l
r'W TABLE 1.1, SURVEILLANCE FREQUENCY NOTATION......................
1-8 I
TABLE 1.2, OPERATIONAL CONDITIONS...............................
1-9 l
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INDEX
/G LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE
,SECTION 3/4.11 RADI0 ACTIVE EFFLUENTS s
/
3/4.11.1 LIQUID EFFLUENTS l
Concentration............................................
3/4 11-1 4
3/4 11-# '
0ose....g.g..............................................
Liquid (WasteTreatment...................................
3/4 11-p*/
Liquid Holdup Tanks......................................
3/411-/g' Ct.;;'::1 Tr.:t;. int ^ : :a 3/4 11 0
.........m..
1 3/4 11.2 GASEOUS EFFLUENTS Dose Rate................................................
3/4 11-9 j Dose-Noble Gases.........................................
3/4 11-13 u4 Dose todJrs.:.M....TH+f:mrti::1:t::
.,_Jie..=dide S M PMienkte Ferm, R.
- nd ":di:ne:lfd: Oth:r th: M: 1: C2:::................
3/4 11-14 Gassous Radwaste Treatment...............................
3/4 11-15 Ventilation Exhaust Treatment............................
3/4 11-16.
l}
Explosive Gas Mixture....................................
3/4 11-17, Main Condenser...........................................
3/4 11-M /F
- Ma r k I o r II Co ntai nment.................................
3/4 11-20'/T A
3/4 11.3 SOLID RADI0 ACTIVE WASTE..................................,,
1/.4.11 -M a8 n
1 1
3/4 11.4 TOTAL D0SE............................................... '3/4li-3r2/
)
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PK0 GRAM......................................
3/4 12-1,
3/4.12.2 LAND USE CENSUS.........................................
3/4 12-15 3/4.12.3 INTERLA80RATORY COMPARIS0N..............................
3/4 12-14 i
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- - - - ~,
-w a,--,
...--,,----_m,,,,,-,----,n-,-,,-v---------,m--w-
- _n_,
,..,v-e-~_.,, - - - - -,,,
fuf L Le4DM ON 8 m e d -
, ugL Lc4DJNG Of f AIA TI O r0 lb Mf bt& he bcCfM-N J eg[i )
_ ), p /l f +.. I ; J.
e tLe cars or h sL-f4 W3 o-f b l with -n c co m.
i l
DEFINITIONS END-OF-CYCLE RECIRCULATION PUNP TRIP SYSTEM RESPONSE TINE O
1.13 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be that time interval to (;nr;;f::th: :" th: n;i n e htien ;
ef = it tr n h r t-f; 0011 *r z d :: t h r rf u r:d p rin ter r r d i t tri; nt; t :t ^2: ch= =1 x n t) Tcomplete suppression of the electric 1
are between the fully open contacts of the ra:irculation pump circuit breaker from initial apvementlof the associated:
{
a.
Turbine stop valves, and b.
Turbine control valves.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured, l
FRACTION OF LIMITING POWER DENSITY 1.14 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given location. divided by the specified'LHGR limit for that bundle type.
y FRACTION OF RATED THERMAL POWER 1.15 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the sensured i
/ THERMAL POWER divided by the RATED THERMAL POWER.
i FREQUENCY NOTATION 1.16 The FREQUENCY NOTATION specified for the performance of Surveillance 0
Requirements shall correspond to the intervals defined in Table 1.1.
l 9
.-o, wwer A LOENTIFIED LEAKAGE
)'
L.Er IDENTIFIED LIAKAGE shall be:
l I
l If a.
Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the opera-i tion of the leakage detection systems or not to be PRESSURE SOUNDARY LEAKAGE.
t ISOLATION SYSTEM RESPONSE TIME l
1.WThe ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when ll l
zo the monitored parameter exceeds its isolation actuation setpoint at the l
' channel sensor until the isolation valves travel to their required positions.
Times shall include diesel generator starting and sequence loading delays where applicable. The response time any be measured by any series of sequential, everlapping or total steps such that the entire response time is measured.
LIMITING CONTROL R00 PATTERN 1.)K A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the l
2J core being on a thermal hydraulic limit, i.e., operating on a lietting value for APLHGR, LHGR, or MCPR.
4 LINEAR HEAT GENERATION RATE 1,2F LINEAR NEAT GENERATION RATE (LNGR) shall be the heat generation per unit l
)
,u length of fuel rod.
It is the integral of the heat flux over the heat j
transfer area associated with the unit length.
I 46475 (-" 1 0 1-3 Aev. 2.
Het c h
Imssa.r A T.
P=j. / -U5 :
GASE US RADWASTE TREATMENT $YSTEM
,,, g a be A GASEOUS RADWASTE TREATMENT SYSTEM
~
s any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the main a system and providing for delay or holdup for the purpose of reducing the1 total radioactivity prior to release to the environment.
Gosd we e mwa + ee@
l O
i 1
0 Rev.x L
OEFINITIONS LOGIC SYSTEM FUNCTIONAL TEST 1.3f A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, ll 2.1 1.e., all relays and contacts, all trip units, solid state logic elements, etc. of a logic circuit, from sensor through and including the actuated device, to verify OPERA 8ILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tasted.
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...,--,s
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- I "" _ ""' E...'..' "I". I_ ".;".". ' '.~_', ". '. I"".,.." ".' ' f., ;. "' '. ' I..'..:"'.,. l '..'.'", _'. ' '.',. _..'"_ ' ' "
7 ll,
4 /NMAT }$
MINIMUM CRITICAL POWER RATIO
.tr. exists in the core.' Sr :::'. :!=: Of f r!).
---p $sent 6 OPERABLE - OPERA 8ILITY 1.pl A system, subsystem, train, component or device shall be OPERABLE or have ll A7 OPERA 8ILITY when it is capable of performing its specified function (s) l
}
and when all necessary attendant instrumentation, controls, electrical s
power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device i
to perfom its function (s) are also capable of performing their related support function (s).
OPERATIONAL CONDITION - CONDITION 1./ An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive ll 2a combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.
- -p INstG c l
DNYSICS TESTS 1.%PHYSICSTESTSshallbethosetestsperformedtomeasurethefundamental ll so nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) othenrise approved by the Commission.
PRESSURE 800NDARY LEAKAGE 1.gPRESSURE80UNDARYLEAKAGEshallbeleakagethroughanon-isolablefault ll in a reactor coolant system component body, pipe wall or vessel wall.
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Insee., A 1 P=>. 1-4 :
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MEMBER (5) 0F THE PUBLIC I.19 l
trP' MEMBER (5) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
P.
I- 'l 2 Tusen.y B t.
S 0FF5ITE 005E CALCULATION MANUAL (00CM) s.u h 4 The OFFSITE 005E CALCULATION MANUAL shall contain the current methodol
> and parameters used in the calculation of offsite doses due to radioactive i
gaseous and liquid effluents, in the calculation of gaseous and ifquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radiological monitoring program.
s Insra.T C tm Pg, I-4 :
OPERATIONAL MODE - MODE
/.29 i
h44 An OPERATIONAL M00E (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1.
i hv..t
DEFINITIONS
- O PRINARY CONTAI MENT INTEGRITY w tr<sesT A 1.pf PRIMARY CONTAIMENT INTEGRITY shall exist when:
ll 31 a.
All primary containment penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an OPERA 8LE primary containment automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, or i
deactivated automatic valve secured in its closed position, except as provided in Table 3.6.3-1 of Specification 3.6.3.
b.
All primary containment equipment hatches are closed and sealed, c.
Each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
The primary containment leakage rates are within the limits of Specification 3.6.1.2.
I e.
The suppression chamber is in compliance with the requirements of Specification 3.6.2.1.
f.
The sealing mechanism associated with each primary containment penetration; e.g., welds, bellows or 0-rings, is OPERABLE.
RATED THERMAL POWER
- 1. GRATED THERMAL POWER shal1 be a total reactor core heat transfer rate to l
~
3f the reactor coolant of $2931mfT.
REACTOR PROTECTION SYSTEN RESPONSE TINE 1.M REACTOR PROTECTION SYSTEM RESPONSE TDE shall be the time interval from '
l 3(, when the monitored parameter exceeds its trip setpoint at the channel 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.
REPORTA8LE 000We#6NGE &vr#T'
- 1. g A REPORTABLE d
! shall be any of those conditions specified in l
37 !;r* **--t tc; ;;. :. :.
2: 5 a.'.". Sec.Oe So.7f f, /o cag At 40.
800 DENSITY 1.[ 200 DENSITY shall be the number of control rod notches inserted as a l y fraction of the total number of control rod notches. All rods fully O
inserted is equivalent to 1005 R00 DENSITY.
C:T; On'4 1-5
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PROCESS CONTROL PROGRAM (PCP) 1, 3%
h41 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20,10 CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.
PURGE - PURGING l.3B L4a PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
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/
O DEFINITIONS s
0:00:0^^" GT"L,.qGewMa ( coerewcur.)
tueras, mos L.-!NTEGRITY REACTOR, BWLDtNC3 1.I-SE69NSMPHIGNT*HMEMT-INTEGRITY shall exist when:
l All':Y" accident conditions are e)ither:
-- n pe trations required to be closed during a.
Capable of being closed by an OPERA 8LE-a:: doc L*di'ig ecc
- n':r; ::nt. r = t 1.
automatic isolation system, or
+k W
automatic ( _!
) (:r) {damperl (,[:: ;;1!::ti:) secured in its Closed by at east one manual valve lind flange, or deactivated 2.
l closed position. - :--t :: pr:;'":d '- T:ti: 3.5.5.2-1 :"
' xifi::ti:n 2.0.0.2.
2sfv/-
All reub, ub3(sec..Jm ced:aw.*)
l
- ' hatches and blowout panels are closed b.
and sealed.
sat <,h, Red <c4b a.4 hNm c.
The :^ :O, p - tr :^--.t system is in compliance with the requirements of Specification 3.6.5.3.
f **
. Mu k.1I.ii' i t
A -';l.
in each rea entry a
,5
}, J a elae M j:::e p er O
.f g.
The sealing mechanism associated with each ^:we &::_y; G AE m.cn nt,R' r ::.._
penetration, e.g., welds, bellows or 0-rings, is OPERA 8LE.
The' pressure within the : emehg:e k'dLys. n/~fO f< :n_ r; ::: _
n is less than or equal oj f.
to the value required by Specification 4.6.5.1.a.
l SHUTDOWN MARGIN 1.M SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is l
40 subcritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e. 68'F; and xenon free.
7INswr B STAGGERED TEST BASIS
- 1. M A STAGGERED. TEST BASIS shall consist of:
l w a.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n l
equal subintervals.
b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL POWER O
1.kTHERMALPOWERshallbethetotalreactorcoreheattransferratetothe l
NOPE CRETot.
- -07 ( = /t) 1-6
.ktV. f
INSERT A TO PG. 1-6:
d.
For double door arrangements, at least one door in each access to the reactor building (secondary containment) is closed.
e.
For single door arrangements, the door in each access to the reactor building (secondary containment) is closed except for routine entry and exit.
O 2 ~> r a +
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SITE SOUNDARY
- t. 4 /
1.ne The SITE B0UNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK A.5OURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
O a~. t
J DEFINITIONS OO M il "CMIG 7." 70" l
1.
The TOTAL PEAKING sha a
o of local LHGR for any ll
~
specific location o v
core average LNGR associ-p?:
tr rue bundles of the same type opera core average
- =
- r. )
ll TUR8INE BYPASS SYSTEM RESPONSE TIME 4G 1.Js The TUR8INE SYPASS SYSTEM RESPONSE TIME 2:P 5: th:t t'= *-*:r;-! < C __, 'I dx th: (= n r
- r r
- '
- r ::=;;; 't: ::te-f:- :t-1-.
- -- -- -- - * " a l:'-, - - I I ' "E "' '
- 27) (trd '.=m_bg en : = t--! 2:
8'
...m, m
y.-, -.... _- _... :.g;;; ::,. ;; tr=;1 *- th- - - g -; 7-- e. --,
- x
- t's R,5==r:dt :j- ::r';; cf = =tf -1, =;-7 "-- --
j Or ^;t:1 -t:; :::t ".-t '2: =t'
- =; "=
a- ---
--c.
UNIDENTIFIED LEAKAGE 1.pfUNIDENTIFIEDLEAKAGEshallbeal'1leakagewhichisnotIDENTIFIEDLEAKAGE.
ll
'M 4 INJGAT A a[Me hm Edka.\\ mme Covdib e ktco c.orw.pe s'.
cn h % b w 4 4e -coAo\\ 4ewh sa p) a m %,a me m u, a e m u 2
6 kLa memea S m & w 4o,sa c A \\ udue uvh\\. 'wG\\i\\ vwevemed E % b6
/ Wscabe..% ve9m.e b w3 be *==e1 bg m3 seau. E seyevh.ia\\., weAaggg bb\\. sh swck %k bok. ewhe. +es.peue. be empw.wh are. vw.e.a.wel.
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P. I' 7 I n3ar A to S
O UNRESTRICTED AREA I
/.fr h4d An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATNENT SYSTEM t, W 4,40 A VENTILATION EXNAUST TREATMENT SYSTEM is any system designed and installed l
1 to reduce gaseous radiciodine or radioactive asterial in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing todines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 160
)
O,,
VENTING is the controlled process of discharging air or gas from a con-h40 finement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not pro-vided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
O ev. A
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3/4.11 RADICACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in ifquid affluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be Ifmited to the concentrations specifici in 10 CFR Part 20, Appendix 8. Table II, Column 2 for radionuclides i
other than dissolved or entrained noble gases.
For dissolved or entrained noble i
gases, the concentration shall be Ifaited t :
10 ' :n. xrS:/2! et?
nt!"'ty.
QS Shown is ra ble
- 3. / / - i APPLICA81LITY: At all times.
ACTION:
With the concentration of radioactive material released in liquid effluents a.
to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above Ifnits.
f b.
The provisions of Specification 6.9.1.9.h are not applicable.
O SURVEILLANCE REQUIREMENTS 1
l 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4. u-1.
4.11.1.1.2 The results of the radioactivity analyses shall be used in l
accordance with the methodology and parameters in the 00CM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
i l
4 l
fle96 CRWk m
Rev.2
-#WR-9 5-t 3/4 u-1 4, Wee-
TA8LE 3.'11el h e-MAXIMUM PERMISSIBLE CONCENTRATION OF F
DIS 5OLVED OR ENTRAINED NOBLE GA5E5 RELEASED FROM THE 5J,TE TO UNRESTRIcrto AREAS IN L QUID WA5TE NUCLIDE MPC (uCI/s1)*
Kr 85 a 2E-4 Kr 85 5E-4 Kr 87 4E-5 Kr 88 9E-5 Ar 41 7E-5 Xe 133 a 5E-4 Xe 133 6E-4 Xe 135s ZE-4 Xe 135 2E-4
]'
C
" Computed from Equation 20 of ICRP P blication 2 (1959), adjusted for infinita u
cloud submersion in water, and R = 0.01 ram / week, p, = 1.0 gn/ca, and P/P
=,1.0.
s g
l Hon ca.en 3/4 11-2 dev.2
--..,.,,_-,---,.,,,,--,,_,,,,------,_,,,,,_,---,_,_,,,,,,,,,.,,,,,-,,,,__,,,,,,_,,,--,-,-,,..--,,--__,,-,.,---,-.n,
4 l
TA8LE 4.11-1 i
RADICACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minious Liquid Release Sampling Analysis Type of Activity of Detect {on Type Frequency Frequency Analysis (pC1/ml)
(LLD)
A. Satch Weste P
P Releage Each Satch Each 8atch
~7 Tanks Principa} Gamma 5x10 Emitters
-6 I-131 1x10 P
M Ofssolved and 1x10-5 One 8atch/M Entrained Gases (Gamma Esitters)
P Q -46 d 53 1x10 Each Batch Composite Gross Alpha 1x10'I P
-8 Q
Sr-89, Sr-90 5x10 d
Each Batch Composite
-6 F.e-55 1x10
- 5. ^.. t r:g:
W
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- 0WR*$YS*T" l ".,aTa fev. L 3/4 ll-g 3
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. m.m.--..
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)
i TA8LE 4.11-1 (Continued)
TA8LE NOTATION i
"The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD =
b E
V 2.22 x 108 Y
exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, h is the standard deviation of the be.ckground counting rate or of s
tne counting rate of a blank sample as appropriate, as counts per i
- minute, j
E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x los is the number of disintegrations per minuta per microcurie, Y is the. fractional radiochemical yield, when applicable, 1
A is the radioactive decay constant for the particular radionuclide, and l
l At for plant effluents is the elapsed time between the midpoint of j
sample collection and time of counting.
Typical values of E V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a orfori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular esasurement.
bA batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
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-. ~ - -. - -... -. -.... -.. -. -,... -, -.. - -. - -.
-..---....,w.,,
4 3
TA8LE 4.11-1 (Continued)
L 2
TA8LE NOTATION i
cThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that
~
j are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report j
pursuant to Specification 6.9.1.12.
dA composite sample is one in which the quantity of liquid saspied is
)
proportional to the quantity of Ifquid wasta discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
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all ;a ple; taken foi O. ; ;;;it; ;haII be 17 T;_7.If ;h;d iG ;.-167
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RADI0 ACTIVE EFFLUENTS nu LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMER OF THE PUBLIC free radio-active materials in ifquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (r,ee Figure 5.1-3) shall be limitee;.
a.
During an-f calendar quarter to less than or equal to 1.5 areas to the total body and to less than or equal to 5 areas to any organ, and b.
During any calendar year to less than or equal to 3 areas to the total body and to less than or equal to 10 areas to any organ.
APPLICA81LITY: At all times.
1 ACTION:
a.
With the calculated dose from the release of radioactive saterials in.1iquid effluents exceeding any of the above limits, in Ifeu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that i
identifies the cause(s) for exceeding the Ifait(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
Tht: ;;;tel Oe,.e.; :t;11 elee ia l.4e '1) tJ,
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b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.11.1.2 C aulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.
i 5 Suar wb y
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I RADI0 ACTIVE EFFLUENTS LIQUID RA0 WASTE TREATMENT SYSTEM LIMITING CON 0! TION FOR OPERATION l
c 3.11.1.3 The liquid radwasta treatment system shall be used to reduce the radioactive materials in ifquid westes prior to their discharge when the projected doses due to the liquid effluent, free each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 arem to the total j
body or 0.2 area to any organ in a 31 day period.
APPLICA8ILITY: At all times.
ACTION:
'l a.
With radioactive liquid waste being discharged without treatment and in excess of the above Ifaits, in Ifou of a Licensee Event Report, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:
I i
1.
Explanation of why liquid radwests was being discie ged without 4
treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appifcable.
SURVEILLANCE REQUIREMENTS
.I i
4.11.1.3 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREA 5 shall be projected at least once per 31 days in accordance with the 4
methodology and parameters in the 00CM.
j
}
k IQ aore dose N
- 1 Rev.1 C.. - -
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.._,n-..--.,_---___....---
--.r-,,
@MR RADI0 ACTIVE EFFLUENTS LIQUID NOLDUP TANKS *
(.*;;gritte Olt:7;;tiJ;; te 17.. TCTI N3 and 3d6Rumm.t "S @ !"E."i".TS 5: 5 ::: 5: !!re;*-' i' t':s ;-- f de - 2:!rd ? ?
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?:::
ee-*rce r:te er;;?y fa-a* """EST*!CTL" ""i". }
LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following excluding tritium and dissolved or entrained noble gases. unprotected 4
c:'
9
- g 0utside temporary tank APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any of the above listed a.
tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appifcable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
m Tanks included in this specification are those outdoor 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.
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t RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEQUS EFFLUENTS 005E RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE SOUNDARY (ses Figure 5.1-3) shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 arems/yr to the total body and less than or equal to 3000 aress/yr to the skin, and
?
b.
For iodine-131Jor tritium, and for all radionuclides in particulate 3
form with half Tives greater than 8 days:
Less than or equal to 1500 erses/yr to any organ.
APPLICA8ILITY: At all times.
ACTION:
l a.
With the dose rate (s) exceeding the above Ifmits, without delay restore l
the release rate to within the above limit (s).
b.
The provisions of Specification 6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 00CM.
l 4.11.2.1.2 The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half lives greater tha,n 8 days in gaseous effluents shall i
be determined to be within the above limits in accordance with the methodology I
and parameters in the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
a l
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RAo10ACTsvE GAsE0uS WASTE SAMPLING AND ANALYSIS PA0GRAN I
E I
T Minimun Lower Limit of Sampling Analysis Type of Detection (LLS)*
Gaseous Release Type Frequency Frequency Activity Analysis (pCl/el) b
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P A X Contalement PGAGE Each PUAGE Each PURGE" Principal Gamma Esitters 1x10 C
b
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y 4.
All Release Types continuoui C W' d I-13t 1x10
-12 O
C as IIsted in A, 8 Cly$ coal *er*
e-ob.e sa. re" i
Continuous #C dd Principal Gamma Emittersb
~U 1x10 Particulate (I-131, others)
Sample l
N Gentinuous
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Sr-89, Sr-90 1x10-U Composite 4pQ Particulate p
Sample
?
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Monitor Gross seta or C -
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[e
TA8tf 4.11-2 (Continued)
TA8LE NOTATION I
The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above system background, that will be detected with 95K probability with only SX probability of falsely concluding that a blank observation represents a "real" signal.
For a particular esasurement system, which may include radiochemical separation:
4.66 s i
b E
V 2.22 x 108 Y
exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s i s the standard deviation of the background counting rate or of h
tne counting rate of a blank sample as appropriate, as counts per
- minute, E is the counting efficiency, as counts per disintegration, i
V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant efflu nts is the elapsed time between the afdpoint of sample collection and time of counting.
Typical values of E, V, Y, and At should be used in the calculation.
It should be recognfred that the LLD is defined as an a priori (before the fact) limit representing the capability of a esasurement systen and not as an 3 posteriori (after the fact) limit for a particular measurement.
5 o
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p TABLE 4.11-2 (Continued)
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TA8LE NOTATION l
b7he principal gassa emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87. Kr-88, Xe-133, K c Sim, 4. '
Xe-133a, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, l
Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulata emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together l
with those of the above nuclides, shall also be analyzed and reported in i
the Seetannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.12.
C.
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l C #The ratio of the sample flow rate to the sampled streas flow rate shall be known for the time period covered by each dose or dose rate calculation i
made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
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. _,....... m 2_._
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J. 4" Filters and cartridges shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from the sampler.
If the iodine or particulate monitoring ch,annel(s) is (are) inoperative, sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days, unless the monitors are restored, fol-lowing each shutdown, startup or THERMAL POWER change ex-ceeding 15 percent of RATED THERMAL POWER.in one hour. Thed O-analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing the samples. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10".
I e
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i RADICACTIVE EFFLUENTS 005E - NOSLE GASES LIMITING CON 0! TION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE SOUNDARY (see Figure 5.1-3) i shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 stads for gaena radiation and less than or equal to 10 stads for beta radiation and, b.
During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 meads for beta radiation.
i APPLICA8ILITY: At all times.
ACTION i
With the calculated air dose from radioactive noble gases in gaseous a.
effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases m
will be in compliance with the above limits.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appitcable.
SURVEILLANCE REQUIREMENTS i
4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the setnodology and parameters in the 00CM at least once per 31 days.
.i
.I l
l J
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RADI0 ACTIVE EFFLUENTS DOSE-100!NE-131.f7RITIUN.ANDRADIONUCLIDESINPARTICULATE LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from fodine-131. tritium, and all radionuclides in particulate fem with half-lives greater,than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE 800NOARY (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 7.5 areas to any organ and, b.
During any calendar year:
Less than or equal to 15 areas to any organ.
APPt.ICA51LITY: At all times.
ACTION:
1 With the calculated dose from the release of iodine-131,, tritium, a.
and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in O
lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above liefts.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
SURVEIt. LANCE REQUIREMENTS l
4.11.2.3 Cumulative dose contributions forj(he current calendar quarter and current calendar year for iodine-131,g(ritius, and radionuclides in particulate fore with half lives greater than 8 days.shall be detemined in accordance with the methodology and parameters in the 00CM at least once per 31 days.
Hopecastk
~
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"9/9/92-
RADI0 ACTIVE EFFLUENTS g
GASEQUS RA0 WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.
APPLICA8ILITY: Whenever the main condenser air ejector (:;;;;;ti: )
system is in operation.
ACTION:
a.
With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 days in lieu of a Licensee Event Report, prepare and submit to tbe Connission within 30 days, pursuant to Specification 6.g.2, a Special Report that includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
j SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of the relevant instruments shall be checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the main condenser air ejector is in use to ensure that the gaseous radweste treatment system is functioning.
l HoM ctEtt.
Rev.2.
4WIM55-t 3/4 11-Z 2/02 O
4
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RADI0 ACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILA-TION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE SOUNDARY (see Figure 5.1.3-1)would exceed 0.3 ares to any organ in a 31 day period.
APPLICA8ILITY: At all times other than when the VENTILATION EXHAUST TREATMENT system is undergiong routine maintenance.
ACTION:
4,
- L. v
+;l.%. mu
- a.
With gaseous waste being discharged without treatment and in excess oftheabovelimits,inlieuofaLIcenseeEventReport,prepareand submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
1.
Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the 00CM, u v
w+,..
t..o.
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RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Sy:t.;; d::f;;;d t:.fth:t ad : hydre;e SN;!ce4cc)
Appropriate alternatives to the ACTIONS below can be accepted if they provide incentive for timely repair of monitors and for compliance with GDC 3 (fice 7.2::tter).
LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen ew in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of hydrogen op-emygen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b...'553!.5."5I5.5$555b'N..'.5$,.!"
E
'l F""
b-e:-
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen o g in the main condenser offgas treatment system shall be determined to be within the above limits by con-tinuously monitoring the waste gases in the main condenser offgas treatment systemaith the hydrogen or oxygen monitors required OPERABLE by Table 3.3.7.12-1 of Specification 3.3.7.12.
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RADI0 ACTIVE EFFLUENTS MAIN CONDENSER t
LIMITING CONDITION FOR OPERATION
- l
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3.11.2.7
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ACTION:
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i 4.11.2.7.1 ' "..... ". '.. - -. '.. ".., -..- -. '..... ' '...,...--
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T e 1*.i r e p[sce
,,g-MSe M S Qge 4.
9___.
a.
__ ___.s 1 2_.ye.
See ne ct-p.
e _2_3_g b.
u.m. ms_
m m_.._
a_, s _.J _._ ____...,.. I m.a. s...
.a k,m.............. _
on.
s......,
A J. _..P E - _ A _ _
-o 9_
__ r...._f....
u a_
1 u__1
_m
__._i-mm'....
w'emt mi
.-.g..
2_._.
_u_____
v
.y r-... w.,
w.
y.u..
q _. _, s..W I es,
. Wh.W. # _ _ _.
- s.._.
vuenu a s anuen
...y w..
.w
.....y. e
..........-..i...i..,...
the nami na_l.
a t amass m_ * = e m8'..='.... y..-
.. '..... - '..v.,
.w'.....
- '---- -- - ^
pi.-.y l
.n e......u. J..-
..,4..e.J.1 1.
e.4..m..
J a.._.m.. _ /. 4 a.._ -...... L..
w
.me_
.e 9.,.n.a
^_
..An.W
.....y
...g f
.i.
g i
t AF MJ, Ma, 4 7e k w.. b 3..Wu b E.JII G I b51-JU WIIIUb53
_ __ a_f t_ imm_.am.e.. u.d. 6 4. m.m.8. --- -.....'i..= g....a
- m. v_ _._
2-
-~^- ad the e i ne d
. m...ws eka
- a.,-g w..- _ _ 21_ _ _. a. u s. s.gu
_.s.
a.
- n.._.
. g.. e. n..,y 5 b { W { l,
__us_
_ _ _ _. na
.u2_
____2
.....m..
v
..w
..w.
p,, e
& w%e n As m.%
c o,.] e,. s. r-
'.4 r-m n,,.
yy o ee<. i o,.
i l}
==
=., =
/4 n,,
.e,sq se,..
s a an a
--n HoPGCAEsk
- 6. 2 l
l
=
e.
.efr--
-.w--
--e--
?w.-.w--w-.
---w r-wv-..w-w'-='-'*-P- - " * " ' - " * - ' ' = * * - " ' " ' - - " ~ - ' " - - - ' - ' " " - "- ^ " - - - - - - - - - '
k sav A&B to PS.
3/y n - /t r 3.11.2.7 The radioactivity release rate of the noble gases Kr-85m, O
Kr-47, Kr W. Xe-133, Xe-135, and Xe-138 measured at the discharge of the recombiner packages shall be Ifmited to less than or equal to 330 milli-curies /second.
APPLICA81LITY:
OPERATIONAL CONDITIONS 1, 2*, AND 3*.
ACTION:
With the gross radioactivity rate of the specified noble gases at the discharge of recombiner package exceeding 330 mil 11 curies /second, restore the gross radioctivity rate to within its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least NOT STAN08Y within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
/ 4.11.2.7.1 The radioactivity rate of noble gases at the discharge of the recombiner package shall be continuously monitored in accordance with Specification in Table 3.3.7.12.
4.11.2.7.2 The gross radioactivity rate of the specified noble gases from the discharge of the recombiner package shall be determined to be O6 within the limits of Specification 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the discharge of the recombiner package:
a.
At least once per 31 days.
b.
Within four hours following an increase, as indicated by the i
Offgas Radioactivity Monitor, of greater than 501, after factoring out increases due to change in THERMAL POWER level or in air in-leakage, in the nominal steady state fission gas release from the primary coolant."
u kev..t O
l
~..
T$.
v -- g i
RADI0 ACTIVE EFFLUENTS l-MARK I or II CONTAINMENT LIMITING CONDITION FOR OPERATION r
3.11.2.8 #ENWiG-w PURGING of the.";;i
- r
- : containment &.211 shall be
+
/
through the St::d4 k; 'n:*---t Sy;t;;. #mm 8.issoiw4 (Ner/wmu en = (eavs) ab de
.e &3 46. c.
w /5.r.,,. c/ w rwa (cres) J 3.
/.
APPLICABILITY: Whenever the drywell is : t:d Or purged.
i ACTION:
With the requirements' of the above specification not satisfied, a.
suspend all MENHNG-end PURGING of the drywell, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
3URVEILLANCE REQUIRMENTS
)
4.11.2.8 The containment drywell shall be determined to be aligned for VENHNG-
,--ee PURGING through the : 4 C M '=:'..r^. Cy;;;; within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at leastMe per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during #ENHNG-w PURGING of the drywell.
(ABV.S aAw clew ssy Ly LAs CFts,1f repaln/
e6 QQ '
Not< CREEK jg Av. A.
M 3/4 11-g 3/12/^^
O g.
m._.,
_..~
_m
.e
{
i RADI0 ACTIVE EFFLUENTS 3/4. u.3 SOLIO RADI0 ACTIVE WASTE LINITING CONDITION FOR OPERATION r
I I
- 3. u. 3 The solid redwaste system shall be used in accordance with a PROCESS j
CONTROL PROGRAM to process wet radioactive wastes to meet shipping and
)
burial ground requirements.
APPLICA8It.ITY: At all times.
ACTION:
With the provisions of the PROCESS CONTROL PROGRAM not satisfied, a.
suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the sita.
1 b.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.9.b are not appitcable.
4 4
SURVEILLANCE REQUIREMENTS Wrifiedron of solidromN.n shall be in acc o rd an c.e..w tk n e.
1
)
p s
T A8 8-
_ao cs s.a.,c,o u..u..,..m.
P.RoGaoM -
,a ammma-m_,,
' w_
_2
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u
. m.w_
a..=
. nww u.ww
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___=w__
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m__
_.,___i nw e.
r nw.. -m euwaa w
wwww ww wws eay ww mew a s a wri s o wn i
_a i.,........s..._
w' u==.u weu wu' w.
...w
. ww
.. sy wb s is eiws u=
sweem
.ww.y 1
- m. a..-.k..m.._
. s. m. e.
7
..a d.... a. d. o.. --.a.. #.,.
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....a.
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m.u. mmm m. m e m,n kne_+mm.ka m4.,. ar d.d g
7
a m 1. n+ 4. m m a, -... anA 4e_ma m u i. d at_a_
a_a_l.ut_4nnai, med f
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m=_ m. _
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.===.m*===n 7-..-..
sea ww wwu aey wwwu a r a bes s awes, wuw.pwa.4 W a r & bn e 4 wn
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.e n e e n, e v e a v v a.u
...w 7-,.-...
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W 6 s a 4.r15 aw T
...___e._
k.
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-...-. -=
-w......w w ass ebt.ws wasubs w 1.H bHW rMWWJJ bWl18 RWI.
.n ame n a na
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..A_______.
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.. _ _ J s. A.._. en e f.n. T e t. p a,v.n.a.a.
ww w..R. f.e T _
ensT
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m a,y,ma.in a mm_
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_______2
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.s.a...... s...
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ww s._ -
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.k-j eneemerem ww u.a w a r a w.m e..ma,a amar e.c.e........ a mn e s A M..
enas, man y..
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==...-...w.
-s j
k.
T. s. -.. a..d. a.d.
1 a.. a. --_J...
ah.
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- m. J. i. _
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a-4 y--
.- = --
l
.ma emesem w
---mesp e-w. ara a,omaa
_P._
a y.w 2.2_ a... gh.
^^
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4
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--.. - -. a....
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9....._....A.m..
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a ma 2----=&..e-
_w..f n f. f ?.P AT. TMM eMA 7-.-.
__.s__2
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.aanma ana _ u _ i. t.
k.m m.a.-
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da e- - - 4. # 4.,- m e_ d. am E_.1 'I, _- ma a n nem CfM T_ M_ T Ef_ f_* AT?nua_ #
+n 7
...k..k m a k.ankAm
.-a.a.
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a Hors caso mm OwO 9
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- - - - - - _.. - - - -...., - - - -. ~.
_e.m_m.w.,,,.me
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-, - - - - ~
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{
RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CON 0! TION FOR OPERATION
, - ster 3.11.4 The annual (:: hn i r i n r) dose or dose commitment to any MDSER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel l
cycle sources shall be limited to less than or equal to 25 areas to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas.
APPLICA8ILITY: At all times.
i ACTION:
1 a.
With the calculated doses from the release of radioactive saterials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b 3.11.2.3.a. or 3.11.2.3.b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have i
been exceeded.
If such is the case in lieu of a Licensee Event t
Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recur-O rence of exceeding the above limits and includes the schedule for i
{
achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) i covered by this report.
It shall also describe levels of radiation i
and concentrations of radioactive saterial involved, and the cause of the exposure levels or concentrations.
If the estimated dose (s) i exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the i
Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Subetttal of the report is considered a timely request, and a variance is granted until staff j
action on the request is complete.
i b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1
4.11.4.1 Cumulative dose contributions from Ifquid and gaseous effluents shall i
be determined in accordancs.with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.
4 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor t
i units and from radweste storage tanks shall be determined in accordance with the methodology and parameters in the 00CM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a.
Arv. 2-
-#WR-6PS-t-3/4 11-g,j 4/3/;2 Moff cREtk l
l 1
3/4.12 RAOI0 LOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 NONITORING PROGRAM __
l LIMITING CONDITION FOR OPERATION
.)
3.12.1 The radiological environmental sonitoring program shall be conducted as specified in Table 3.12-1.
t i
APPLICA8ILITY: At all times.
i i
ACTION:
I With the radiological environmental monitoring program not being a.
conducted as specified in Table 3.12-1, in lieu of a Licensee Event i
Report, prepare and submit to the Commission, in the Annual Radio-logical Environmental Operating Report required by Specification 6.9.1.11, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, t
b.
With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the Ilmit(s) and defines the corrective actions to be taken to reduce radioactive l
effluents so that the potential annual dose" to A MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.
When more than one of the radionuclides in i
Table 3.12-2 are detected in the sampling medium, this report shall i
be submitted if:
concentration (1) concentration (2)
+ ***> 1.0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 3.12-2 are detected and j
are the result of plant effluents, this report shall be submitted if 1
i the potential annual dose
- to A MEMER OF THE PU8LIC is equal to or greater than the calendar year limita of Specifications 3.11.1.2, f
3.11.L 2 and 3.11.2.3.
This report is not required if the seasured i
level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
With milk or fresh leafy vegetable samples unavailable from one or c.
more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add thee to the radio-s logical environmental monitoring program within 30 days. The specific i
"The methodology and parametert used to estimate the potential annual dose to a MEMER OF THE PUBLIC shall be indicated in this report.
3/4 12-1
-0/0/M b* 'l-non cRwc c..
--, -,,,, - - - - - -, - -,.. -. ~. - ~. -... - - -. -... - - -
RADIOLOGICAL ENVIRONMENTAL MONITORING locations from which samples were unavailable may then be deleted from the monitoring program.
In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.12, identify the cause of the unavail-ability of samples and identify the new location (s) for obtaining replacement samples in the nexc 5esiannual Radioactive Effluent Release Report and also tw1ude in the report a revised figure (s) and table for the 00CM reflecting the new location (s).
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
d.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental sonitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.
O e
.. 2 JWESTS-t-3/4 12-2 4rW44-
i j
i*
l g
IABLE 3.12-1 A
RADiet0GICAL ElfWlR00SIEIIIAL MDellTORIllG PAGGRAM*
S m
t sa E
10 umber of Representative Exposure pathway samples and Sampling and Type and Frequency and/or Sample Sample tocations*
Collection Frequency of Analysis 1.
DIRECTRADIAT10d 4dresestinemonitoringstations quarterly Gamma dose quarterly.
l (S".&-8840) either with two or more desleeters -- W 2 - :
a_. _., _ _ _ _ _ _. _ _ _ _,
9^; 3
_^
2U' r.
an i r,lpgg f eorolog1 stations, one in o
cal sector in the w
eac
)
general area of the SITE telfleARV-("' ""15h an outer ring of stations, one in each meteorological sector in j
the 6-to 8-ka range from the j
site (""!? ""22);
t i
the balance of the stations 40833=0R40) to be placed in special interest areas such as population centers, nearby residences, schools, and in,
l
-oe-4 areas to serve as control stations.
- The number, media, frequency, and location of samples may vary free site to site. This table presents an acceptable minimum program for a site at which each entry is appilcable. Local site characteristics
)
l must be examined to determine if pathways not covered by this table may significantly contribute to an j
y individual's dose and should be included in the sampilng program.
s ;
Sr c:f: '-t*-~ '" 7- ""*****. " e-8 j
2"1.
- ti - : :p :" i ft !:; g ar!; :, : :;;;;';; ',, ;;,'; :;::if'cet'er. tiet ;-e L..e;4 te N
li niffy : 57::!**: ? ::t!::: 8: - - 7(:) _ d a 3: != n- ::ya.
.l t
TA8tE 3.12-1 (Continued) 3 gi i i -
3 3 I RADIOLOGICAL ENVIA0000FNTAL MDNITORING P90 GRAM
^
i ilumber of i
g- !
Representative g4 -
Exposure Pathway Samples and sampling and Type and Frequency j
g and/or Sample Sample tocations, Collection Frequency of Analysis 2.
Alte0AIIE Radioledine and Samples from 5 locations (Al-M):
Continuous sampler Radiolodine Canaister:
Particulates operation with sample I-131 analysis weekly.
3 samples (a!-A2) from close collection weekly, or to the 3 SITE teuMBAAF locations, more frequently if in dif forent sectors, of the-required by dust Particulate Sampler:
higheeb calculated annual average loading.
i
]
groundlevel D/q.
Gross beta radioactivity
{
analysis falleging 1 sample 4A4) from the vicinity filter change; 1
}
ef a community having the highest Gamma isotopic analysis"
)
calculated annual average ground-of composite (by level 8/Q.
location) quarterly.
j M
1 sample fAH from a control i
location, as for example 15-30 km l
distant and in the ast preva-4 i
lent wind direction I
3.
WATERSORIIE g
G c5 L ered a.
Surface I sample upstream (We&}
" ; n'".; sample evee-Gamma isotopic analysis
- I sample downstream (Weal-1 month perled" monthly.
. x!S fr-i swede e.r
- 34re.,
tritium analysis quee6ec4y."**b b.
Ground Samples from 1 or 2 sources
^ :rt: &
Gamma isotopic" and tritium affect]ed.), only if likely to be m%4d
( ?.
3 analysis ----*edy, mo4(g 6
c.
Drinking I sample ef r::5 of 1 2 2 '".1
-;: !S : ; h I-131 analysis on each e-j i 4ds4)- of the nearest water
- ur 0-.; t Fr!;4*
composita when the dose i
g supplies 'tzt ;;J 4 0.-
- t- !-!?! --We!:
calculated for the consump-effer'ed b; ' M d!:-t r,..
!s ---f;;--2, monthly i
Lion of the water is g
composite otherwise-than 1 mrom per year. greater Com-I 8 y
1 sample from a control 3
p location Ods4h posite for gross beta ap l
i gamma isotopic analyses I
g monthly. Composite for s I trittun analysis quarterly.
t
- - - ~
ei; i
i l
i TABLE 3.12-1 (Continued)
RADIOLOGICAL ENW19000 ENTAL MONIl0 RING PROGRAM 4.
n5 I
L' i tha=har of
}
M Representative F
Eaposure Pathway Samples and Sampilng and Type and Frequency i
i and/or Sample Sample Locations
- Collection Frequency of Analysis 1
i d.
Sediment I sample from downstream area Sealannually Gamma isotopic analysis' from r
i l er s t * - -- P* --* h !
samlannually.
shoreline
- r r'*---! -e!-- ( * *).
4.
INGESTION L hmele sde ~
up sir
' w le e
em o re.
<:.r. s s s+ <,. m e r,.
a.
Nilk Sampjps free allking animals Seeleonthly when Gamma isotopic
- and I-131 in 471ecations (':1
"; ) within animals are on analysis seminenthly when 5 km distance having 4he highee4 pasture, monthly at antaals are on pasture; dose potential.
!! *',- : er other times monthly at other times.
____--,.m_., _ _.-,....- _-_ -.-.
1:'
='--h 1-e-" :" 3 ::::: (1el
!a?) ' '-::: 5 u ^ 6 eistant-
^t::= 2:::: ::; ::'::::'ri,': b j
J.
enzt : ' ' -- 1
- p. 1 i
i I sample from allking animals j
at a centrol location ("20),
i to W 30 km distant - ' 8: :
i l
? rrt ;-:::!::t r'd d!:::15 ;.
b.
Fish and I sample of emeh-commercially Sample in season, or Gamma isotopic analysis
- l Inverte-and recreatlanally important semiannually if they on edible portions.
j brates species in vicinity of plant are not seasonal
{
discharge area.
('51
'5 _ ).
I sample of same species in areas not influenced by plant dis-L*
charge ('t!S "t_ ).-
l 1
c.
Food I sample of each principal class At. time of harvest Gamma isotopic analyses
- i Products of food products ";
on edible portion.
-t !
'::'^:t:
t, e !d !* ;'d ;!: ' "::'r: 5 ::
y,
6::: d'::t:, 4 (':!
":_).
i 8
J
i j
)
i m
- Ii Ia 2.
a l: b2 TABLE 3.12-1 (Continued)
.$lt l ?.,
RADIOLOGICAL INVIR000 ENTAL MDNITORING PA0 GRAM i
i e
..>=y i
10 umber of 4
I Representative
)
Exposure Pathway Samples and Sampling and Type and Frequency j
and/or Sample Sample locations, Collection Frequency of Analysis l
c.
Food C -?re ef 3 d!!?: ::t h!- t n r.':;"y '_:.
^ - - h:tr;';* ::_r ;-;;;
Products ef 5-rd ?r f :: ;:iei!:: ;;7 -- -
3-.ai.hn.
eno4ysis.
(cont'd)
-- r:
--h
= f *= differ e
-- s a,s a --.
1__
..._.s IE.'s -'; if c jik E.,I:d te c.
I sample of each of the siellar 5 ^l.ij * - -
Gamma isotopic
- and I-131
)
broad leaf vegetation grown e-c!!d?e analysis.
l g
15-30 km distant != ' ' ? :t ow he. cu r si-j
=~-e!r ! 94 dir;;ti;;. i; "ik-
.m
.u..-....-.-..-..
a..- - p l
g g,'hn - B ***
e ws.n g.
i e
1 1
F I
b i
Q i
1 t I
! l 8
I 8 1 l
6 e
O O
O
.i t
N l
TABLE 3.12-1 (Continued)
TABLE II0TATION
- Specific parameters of distance an~d direction sector from the contarline of one reactor, and additlanal description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the 0000.
Refer to IIUREG-0133, " Preparation of Radiological Effluent Technical Specifications for fluclear peuer Plants,'! October 1978, and to Radiological Assessment Branch Technical Posttlen, Bevisten 1. Ilovember 1979.
Deviations are permitted free the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavaliabt11ty, malfunction of automatic sampling squipment and other legitimate reasons.
If specimens are unobtainable due to samp11ag equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next samp11ag perled.
All deviattens free the sampitag schedule shall be documented in the Annual Radiological Environ-mental Operating Report pursuant to Specification 6.9.1.11.
possible er practicable to continue to obtain samples of the media of chelce at the most desired locatten er time.
In these lastances suitable alternative media and locations may be chosen for the particular pathuey in question and appropriate substitutions made within 30 days in the radiological environmental
)
monitoring program.
In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.12, identify replaceeent samples in the next Sealannual Radioactive Effluent Release Report g
report a revised figure (s) and table for the 0001 reflecting the new location (s).
b ene or more lastruments, such as a pressurized los chamber, for seasuring and recording dose rate continuously may be used in place of, or in addition to, integrating desleeters.
For the purposes of this table, a thermoluminescent desteeter (It0) is censidered to be one phosphor; tuo or more phosphors in a packet are considered as tuo or more dosimeters.
direct radiation. The 40 stations is not an absolute namiber. Film badges shall not be used as dosimeters for measuring stations may be reduced according to geographical liettations; e.g., at an ocean site, some sectors wl11 he over water so that the number of desleeters may be reduced accordingly.
The fregency of analysis or readout for it0 systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
'The purpose of this sample is to obtain background information.
If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide l
valid background data may be substituted.
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Ij TABLE 3.12-1 (Centinued) l 2,
I i
9e TASTE IIDTATIOff Airborne particulate sample filters shall be analyzed for gross beta radleactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sasyllag to allow for raden and theren daughter decay.
If gross beta activity in air particulate samples i
is greater than ten times the yearly mean of centrol samples, gamma isetapic analysis shall be performed j
en the individual samples.
' Gamma isotepic analysis means W identificatten and quantificatten of gamma-emitting radienuclides j
that may be attributable to the affluents from the facility.
l l
Ilhe "apstream sample" shall be taken at a distance beyond significant influence of the discharge. The f
" downstream" sample shall be taken in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be l
sampled only when W receiving water is utilized for recreatlanal activities.
4 8A composite sample is one in which the a uantity (aliquet) of liapsid sampled fi" proportional to the quantity s
}
1l*
et flowing 11apeld and in which the mathed of sampilng employed results in a specimen ht is representative l
et the Ifguld flew.
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ter samples shall be taken when this source is tapped for drinking er irrigatten purposes in areas where h hydraulic gradient er recharge properties are suitable for contaminatten.
I The dose shall be calculated for the maximum organ and age groep, using the methodelegy and parameters in the 0004.
I i
lf harvest occurs more than once a year, sampilng shall be performed during each discrete harvest.
If harvest occurs contineseusly, sampilng shall be monthly. Attention shall be paid to including samples of tuberaus and rest feed products, n
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,i TAetE 3.12-2 n
SEPetillIG LEVELS F00 SA010 ACTIVITY CGIICENTSATICIIS III EllWIS010 ENTAL SAIFLES 1
a f
Seporting Levels
~
liater Airborne Particulate Fish Milk Feed Products 1
Analysis (pCf/s) er Gases (pCl/m )
(pCl/kg, wet)
(pCl/a)
(pCl/kg, wet) a
)
N-3 3 p,000*
Ben-54 1,000 30,000 Fe-59 400 10,000 l
j Co-50 1,000 30,000 l
1' Co-60 300 10,000 i
i g
In-65 300 20,000 Jn Zr-10s-95 400 I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Sa-La-140 200 300 1
l'
- For drinkins water samples. This is 40 CFO Part 141 value.
If me drinking water pathway exists, a value of 30,000 pCl/2 may be used.
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OETECTION CAPA81LITIES FOR Envl30000fMIAL SANPLE ANALYSIS
- 1 o
'd LOWE8 LINIT OF DETECT!0N (LLD)"**
I Water Airborne Particulate Fish Nilk food Products Sedleent i
Analysis (pCi/A) or Gas (pCl/m )
(pCl/kg, wet)
(pCl/2)
(pCl/kg, wet)
- (pC1/kg dry) 8 gross beta 4
0.01 5
N-3 3 2900*
^
Mn-54 15 130 i
fs-59 30 260 Co-58,60 15 130 w
D I
Zn-65 30 260 l
5 Zr-IGn-95 15 i
d I-131 I
0.07 1
60 i
j Cs-134 15 0.05 130 15 60 150 l
l Cs-137 18 0.06 150 18 80 180 i
j Sa-La-140 15 15 i
"If no drinking water pathway exists, a value of 3000 pCl/l may be used.
h i
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TA8LE 4.12-1 (Continued) 1 TA8LE NOTATTON "This list does not mean that only these nuclides are to be considered.
4 Other peaks that are identifiable, together with these of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
l U
l Required detection capabilities for therimoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
1 "The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above system background, that will be detected with 95% probability with only 55 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement systes, which may include radiochemical j
separation:
4.64 s 4
LLD =
D
{
E V
2.22 Y
exp(-AAt)
+
Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume,
}
s., is the standard deviation of the background counting rate or of tMe counting rate of a blank sample as appropriate, as counts per minute.
E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, t
2.22 is the number of disintegrations per minute per picoeurie, s
Y is the fractional radiochemical yield, when applicable,
)
A is the radioactive decay constant for the particular radionuclide, and At for envirormental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E V Y, and at should be used in the calculation.
l, EEI N. 2.
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i TA8LE 4.12-1 (Continued)
TA81.E NOTATION It should be recognized that the LLD is defined as an 2 priori (before the fact) limit representing the capability of a seasurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses s~ hall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental operating Report pursuant to Specification 6.9.1.11.
dLLD for drinking water samples.
If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
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i RADIOLOGICAL ENVIRO MENTAL NONITORING.
3/4.12.2 LAND USE CENSUS LINITING CONDITION FOR OpfRATION 3.12.2 t
A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological
~
sectors of the nearest milk antasi, the nearest resfdance and the nearest gardena of greater than 50 ma (500 ft ) producing broad leaf vegetation.
8
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APPLICA8ILITY: At all times.
ACTION:
1 a.
With a land use census identifying a location (s) that yields a calcu-i lated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event Report, identify the new location (s) in the next Sesiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.12.
b.
With a land use census identffying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are cur-rently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental sonitoring progrse within 30 days.
3 The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.
In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.12, identify the new location (s) in the next Sesiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the 00CM 4
reflecting the new location (s).
The provisions of Specifications 3.0.3 and 3.0.4 are not appitcable.
c.
SURVEILLANCE REQUIREMENTS 4
4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will results, such as by a door-to-door survey, aerial survey, provide the best or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
i
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.
Specifications for broad leaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.
..i n 3/4 12-13 i
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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLA80RATORY COMPARISON PROGRAM LIMITING CON 0! TION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.
APPt.ICABILITY: At all times.
ACTION:
a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIRENENTS O
4.12.3 The Interlaboratory Comparison Program shall be described in the 00CM.
A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
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3/4.11 RAOI0 ACTIVE EFFLUENTS SASES 1
3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive asterials released in liquid wasta effluents to UNRESTRICTED AREA 5 will be less than the concentration levels specified in 10 CFR Part 20, Appen-dix 5 Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II. A design objectives of Aspen-dix I,10 CFR Part 50, to a MEp5ER OF THE PUBLIC and (2) the limits of 10 CFR i
Part 20.106(e) to the population. The concentration 11mit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the control-1 ling radioisotope and its WC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICAP) Publication 2.
This speciffcation applies to the release of 1iquid effluents from all I
reactors at the site.
The required detection capabilities for radioactive materials in ifquid weste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection Itaits can be found in NASL Procedures Manual. HA5L-300 (revised annually) Currie, L. A., " Limits for Qualitative Detection and Quantitative Oetermination - App 1tcation to Radiochemistry," Anal. Chem. 40, 588-93 (1968), and Hartwell, J. K., " Detection i
Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARM-SA-215 (June 1975).
3/4.11.1.2 005E This speciffcation is provided to faplement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Listting Condition for Operation fsptements the guides set forth in Section II.A of Appendix I.
The ACTION statements provide the required operating flexibility i
and at the same time taptement the guides set forth in Section IV.A of Appen-dix I to assure that the releases of radfoective asterial in Ifquid effluents to UNRESTRICTED AREA 5 will be kept "as low as is reasonably achievable." Also, 4
for fresh water sites with drinking water supp1fes that can be potentially i
affected by plant operations, there is reasonatie assurance that the operation i
of the facility will not result in radionuclide concentrations in the finished i
drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodologP and parameters in the 00CM faplement the require-ments in Section III.A of Appendix ! that conformance with the guides of
,i Appendix I be shown by calculational procedures based on models and data, such l
that the actual exposure of a MEpSER OF THE PUSLIC through appropriate pathways
- ^
00CM for calculating the doses due to the actual release rates of radtosctive is unlikely to be substantially underestfested. The equations specified in the materials in liquid effluents are consistant with the methodology provided in i
4Nt*99P4-fWPSTPt 8 3/4 11-1 M Rev. 2.
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1
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RA0!0 ACTIVE EFFLUENTS O
OASES F
Regulatory Guide 1.109, " Calculation of Annual Doses to Man free Routine Releases of Reactor Effluenta for the Purpose of Evaluating compliance with "Estinating Aquatic Ofspersion of Effluents free Accid Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid effluents free each reactor at the site.
For units with shared radweste treatment systems, the liquid effluents from the shared system are proportioned among the units that systen.
3/4.11.1.3 LIQUID RADWASTE TREATMENT SY5iui The requirement that the appropriate pertions of this system be used, when specified, provides assurance that the releases of radioactive materials in liq effluents will be kept "as low as is reasonably achievable".
implements the requirements of 10 CFR Part 50.35a, General Oesten Criterion 6 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix ! to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the Ifquid radwesta treatment systas were specified as a suitable fraction of the dose design objectives set forth in Section II. A of Appendix I, 10 CFR Part 50, for liquid effluents.
This specification applies to the release of Ifquid effluents from each reactor at the site.
Itquid effluents from the shared system are proportioned among sharing that systas.
3/4.11.1.4 LIQUID HOLDUP TANKS The tanks Ifsted in this Specification include all those outdoor 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 redweste treatment system.
tanks provides assurance that in the event of an uncont tanks' contenta, the resulting concentrations would be less than the limits of 10 CFR Part 20 Appendix 5. Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 005E RATE This specification is provided to ensure that the dose at any time at and beyond the SITE SOUNCARY free gaseous effluents from all units on the site wi be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTE annual dose liefta are the doses associated with the concentrations O
The Part 20, Appendix 8. Table II, Column 1.
These Itaits provide reasonable
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1 O
RADICACTIVE EFFLUENT 5 SASES assurance that radioactive material discharged in gaseous effluents will not _
i result in the exposure of a MDGER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE SOUNDARY, to annual average concentrations -
i exceeding the limits specified in Appendix 0. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMSERS OF THE PUBLIC who may at times be with i
the $1TE SOUNDARY, the occupancy of that MDGER OF THE PUBLIC will usually b i
sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE SOUNDARY. Examples of calculations for such MDGERS OF THE PUBLIC, with the appropriate occupancy factors, shall be give in the 00CM.
The specified release rate limits restrict, at all times, the 1
corresponding gassa and beta dose rates above background to a MEMBER OF THE l
PUBLIC at or beyond the SITE SOUNDARY to less than or equal to 500 acess/ yea to the total body or to less than or equal to 3000 oress/ year ta the skin.
These release rata limits also restrict, at all times, the corresponding 4
thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 aress/ year.
}
}
This specification appites to the release of gaseous affluents free all reactors at the site.
j The required detection capabilities for radioactive materials in gaseous j
waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in NASL l
Procedures Manual, NASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection ana Quantitative Determination - Appifcation to Radio-cheefstry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Rad' oanalytica' Counting Techniques," Atlantic Richfield Hanford j
Company Report ARN-$A-215 (June 1975).
I i
3/4.11.2.2 005E - NOBLE @ **!
t This specification is provided to implement the requirements of I
Sections II.B. III.A and IV. A of Appendix I,10 CFR Part 50.
Condition for Operation taplements the guides set forth in Section 11.8 ofThe Limiting Appendix I.
The ACTION statements provide the required operating flexibiltty and at the same time faplement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive asterial in gaseous affluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
1 veillance Seguirements taplement the requirements in Section III.A of Appendix I The Sur-l that confermance with the guides of Appendix ! be shown by calculational proco-dures based on models and data such that the actual exposure of a MOWER OF THE PUBLIC through appropriata pathways is unlikely to be substantfally under-1 estimated.
The dose calculation methodology and parameters estab1fshed in the 00CM for calculating the deses due to the actual release rates of radioactive noble gases in gaseous affluents are consistant with the methodology provided a
4 in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with i
10 CFR Part SC, Appendix ! " Revision 1, October 1977 and Aegulatory Guide 1.11
)
" Methods for Estiasting Ataespheric Transport and 0tspersfon of Gaseous Effluents
{
in Routine Releases from Light-Water Coeled Reactors," Revision 1. July 1977.
l
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-u RA0!0 ACTIVE EFFLUENTS l
BASES 1
j The 00CM equations provided for deteretning the air doses at and beyond the SITE SOUNDARY are based upon the historical average steespheric conditions.
This specification app 11es to the release of gaseous effluents free each reactor at the site.
For units with shared redwesta treatment systass, the sharing that systas, gaseous effluents from the shared system are proportioned am i
3/4.11.2.3 005E - 100!NE-131. TRITTUM. ANO RADI0aRELIDES IN PARTI 1
This specification is provided to implement the requirements of i
Sections II.C. III.A and IV. A of Appendix I,10 CFR Part 50.
The Liefting The ACTION statements provide the required operating f same time toplament the guides set forth in Section IV. A of Appendix I to assure AREAS will be kept "as low as is reasonably achievatte."that the i
The 00CM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix ! that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the i
unlikely to be substantially underesttaated. actual exposure of a MEM O
and parameters for calculating the doses due to the actual release rates ofT Guide 1.109, " Calculation of Annual Doses to Men from Rou Appendix I," Revision 1. October 1977 and Regulatory G i
Estfasting Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1. July 1977.
i tions also provide for determining) the actual doses based upon the historicalThese equ average atmospheric conditions.
trittua, and radionuclides in particulate form with half lives greater tha a days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE 30U4ARY.
l development of these calculations were: The pathways that were examined in the
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onts green leafy vegetation with i
l subsequent consumptfon by een, 3) deposition onto grassy areas where silk
)
animals and aset producing animals graze with censumption of the silk and esat by men, and 4) deposition on the ground with subsequent exposure of man.
This speciffcation app 1fes to the release of gaseous affluents from each reactor at the site.
For units with shared radweste treatment systass, the gaseous effluents from the shared systes are proportioned among the units sharing that system.
3/4.11.2.4 AND 3/4.11.2.5 i
l TREATMENT GASEQUS **OuASTE TREATMENT ANO VENTILATION EXHA The OPERASILITY of the GA5E005 RA0 WASTE TREATMENT SYSTEM
{
VENTILATION EX,HAUST TREATMENT SYSTEM ensur,ss that the systems will be r :T I
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RADICACTIVE EFFLUENTS Basts for use whenever gaseous effluents require treatment pr'ior to release to the environment.
The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous affluents will be kept "as low as is reasonably i
achievable".
This specification feplements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.0 of Appendix I to 10 CFR Part 50.
i The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.8 and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.
3/4.11.2.5 EXPLO51VE GAS MIXTURE This specification is provided to ensure that the concentration of potentially emplosive gas mixtures contained in the weste gas heldup system is maintaine<f below the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.
These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration 4
below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of l
radioactive materials will be controlled in conformance with the requirements of Geratal Design Criterion 60 of Appendix A to 10 CFR Part 50, 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 i
implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
3/4.11.2.8 MARE I CONTAINMENT This specification provides reasonable assurance that releases from drywell pruging operations will not exceed the annual dose limits of 10 CFR Part 20 for unrestricted areas.
3/4.11.3 SOLIO RA0!0 ACTIVE WASTt This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, O
but are not limited to weste type, weste pH, westa/ liquid / solidification agent /
catalyst ratios, weste oil content, weste principal chemical constituents, and mixing and curing times.
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1 RAO!0 ACTIVE EFFLUENTS 8ASES 3/4.11.4 TOTAL 00$E This specification is provided to meet the dose liettations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 44 FR 18525.
The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 areas to the total be g or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas.
For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose Ifmits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses free the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMER OF THE PUSLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMER 0F THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions free other nuclear fuel cycle facilities at the same site or within a radius of 4 km must be considered.
If the dose to O
any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and i
10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limita of 40 CFR Part 190, and does not apply in any way to the other requirements for dosa Itaitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1.
An individual is not considered a MEMER OF THE PUSLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle, I
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t 3/4.12 RADIOLOGICAL ENVIRONMENTAL NONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this specification provides representative measurements of radiation and of radio-active materials in those espesure pathways and for these radionuclides that lead to the highest potential radiation exposures of METERS OF THE PUSLIC resulting from the station operation.
This monitoring program implementsSection IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.
Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environ-mental Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational emperience..
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).
The LLDs required by Table 4.12-1 are considered optimum for routine environmental O
measurements in industrial laboratories.
It should be recognized that the LLD is defined as an 3 gejagi (before the fact) limit representing the caga-bility of a measurement system and not as an 3 nosteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection Itaits, can be found in NASL Procedures Manual. NASL-300 (revised annually) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chos. 40, 546-93 (1964), and Hartwell, J.
K., " Detection Limits for Radioana ytica', Counting Techniques," Atlantic Richfield Hanford Company Report ARM-5A-215 (June 1975).
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v 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING SASES -
3/4.12.2 LANO U$f CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE SOUNDARY are identified and that modifications to the radiological environmental monitoring program are ande if required by the 7
results of this census. The best information from the door-to-door survey,
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from aerial survey or free consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.O.3 of Appen-i dix 1 to 10 CFR Part 50. Restricting the census to gardens of greater than 50 ma provides assurance that significant exposure pathways via leafy vege-tables will be identified and monitored since a garden of this size is the l
ainimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were ande:
- 1) 205 of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m,
a 3/4.12/3 INTERLA80RATORY COMPARISON PROGRAM.
i The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accu-racy of the seasurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are valid for the j
purposes of Section IV.8.2 of Appendix ! to 10 CFR Part 50.
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