ML20118A686
| ML20118A686 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/17/1992 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20118A685 | List: |
| References | |
| NUDOCS 9209240439 | |
| Download: ML20118A686 (13) | |
Text
.
ENCLOSUIL_ 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHN'. CAL SPECIFICATIONS
.lMPLEMENTATION OF THE NEW 10 CFR 20 REOUIREMENTS PROPOSED TECHNICAL SPECIFICATION CHANGJiS 9
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9209240439 920917 PDR ADOCK 03000424 P
PDR,
y
____L_____________.__._____.____._________
/
INDEX OEFINITIONS i
SECTION PAGE
- 1. 0 DEFINITIONS 1.1 ACTI0N........................................................
1-1 i
- 1. 2 ACTUATION LOGIC TEST..........................................
1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST...............................
1-1 1.4 AXIAL FLUX DIFFERENCE.........................................
1-1 e
1.5 CHANNEL CALIBRATION...........................................
1-1 1.6 CHANNEL CHECK.................................................
1-1
- 1. 7 CONTAINMENT INTEGRITY.......................
1-2
- 1. 8 CONTROLLED LEAKAGE............................................
1-2 1.9 CORE ALTERATIONS..............................................
1-2 1.10 CORE JPERATING LIMITS REPORT................
1-2 1.11 DOSE EQUIVALENT I-131.............................
1-2 1.12 E-AVERAGE DISINTEGRA1 ION ENERGY..............................
1-2 1.13 ENGINEERED SAFETY FEATURES RESPONSE TIME.....................
1-3 1.14 FREQUENCY N0TATION...........................................
1-3 1.15 GASEOUS WASTE PROCESSING S: STEM..............................
1-3 1.16 IDENTIFIED LEAKAGE....................
1-3 1.17 MASTER RELAY TEST.................
1-3 E THE Pu b...................................
1.18 1-3 1
1.19 0FFS TE DOSE CALCULA ION MANUAL......................
1-4 1.20 O P E RAB L E - O P E RAB I L I TY.......................................
1-4 l
1.21 OPERATIONAL MODE - M00E......................................
1-4 1.22 PHYSICS TESTS................................................
1-4
' 23 P RESSURE BOUNDARY LEAKAGE....................................
1-4 1.24 PROCESS CONTROL PR0 GRAM......................................
1-4 1.25 PURGE - PURGING..............................................
1-4 1.26 QUADRANT POWER TILT RATI0....................................
1-5 1.27 RATED THERMAL P0WER............................
1-5 1.28 REACTOR TRIP SYSTFM RESPONSE TIME............................
1-5
~ 1. 29 REPORTABLE EVENT..........................................
1-5
- 1. 3C SHUTDOWN MARGIN.............................................
1-5 1.31
<~'E 80VNOARY................................................
1-5 V0GTLE UNITS - 1 & 2 I
Amendment No.
32 (Unit 1)
Amendment No.
12 (Unit 2)
l-a rneans o.n indMcAual in a, cedrolked a,ceo.
or UNM:5TMcTED ARrA. However, An incli-WdeI is n6t A MEMBE&oF, THE PuBUd.
. DEFINITIONS
[EMBERb910FTHEPUBLIC during Qng PeelOrA in u) hic.h *the irdtVidudl
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gecivesqq m pft.jonalc,(o3e, i
1.18 MEMBER OF THE PUBLIC hal! 'n:!ud: 21per:er: ~h:
r: net :: u;:-
h ti:n:lly:s::@:ict;d.ithth;pl:nt.
Thi: ::t:;;ry ::: n:t 'n:-led: Or;1:y:::
cf the 'ic:n ee, it: ::ntr::t:r:, Or V:nd:r:.
^1:: :xclud:d ' m thi: ::t:;: y sr per:::: wh: ^-t:r th: Ofte t: ::rv-ice :;uipr: t er t: :kt d:!'verie.
Thi: ::te;;ry d::: includ; p;r om wh ;;
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OFFSITE DOSE CALCULATION MANUAL resulhnt C0fA I
1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses-d;; i:
radioactive gaseous and liquid effluents, in the calculation of gaseous-and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. T OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
l i
i and when all necessary attendant instrumentation, controls, electrical-power, cooling or seal water, lubrication or other auxiliary equipment that are i
required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
I OPERATIONAL MODE-- MODE i
1.21 An OPERATIONAL MODE (i.e., M'.0E) shall correspond to any one inclusive combinaticn of core reactivity condition. powei level, and average reactor l
j coolant temperature specified in Table 1.2.-
i.
j.
PHYSICS TESTS 1.22 PHYSICS TESTS shall bo those tests performed to measure the fundamental
-l iL nuclear characteristics of the reactor _ core an(related-instrumentation:
i (1) described in Chapter 14.0 of the FSAR,_ (2) authorized under che provisions of 10 CFR 50.59, or (3) othemise approved by the Commission.
1.23_ PRESSURE BOUNDARY L m ~t shall be leakage Texcept steata generator tube l
leakat e) through a nonisolable fault.in a Reactor Coolent System component 4
body, p Se wa;1, or vessel wall.
- '. 24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, l
1 _
sampling, analyses, te'.,ts, and determinations to be made to. ensure that process-
'ng 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 jl to assure compliance.with 10 CFP. Parts 20, 61, (qd 71 pad Rd=1 =d State
-V0GTLE UNITS - 1 & 2 1-4
'Amendrnent No. _32 (Unit _1)
Amendment No, 12 (Unit 2):
0
+
..u ac, _.
n -... _.. _,
DEFINfT20NS SOLIDIFICATION Deleted.
1.33 A SOLICITICATION :h ll b: th: ::=:r:i r of wet :::te - Mt: a 70- th L l
w 't: :M ppi ; :nd 5;M :1 gr:.und requiremee w.
SOURCE CHECK 1.34 A SOURCE CHECK snail be the qualitative assessment of channel response l
when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS 1.35 A STAGGERED TEST BASIS shall consist of:
I A test schedule for n systems, subsystems, trains, or other a.
designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train, or other tiecignated component at the beginning of each subinterval.
THERMAL POWER 1.36 THERMAL POWER shall be the total reactor core heat transfer rate to the l
TRIP ACTUATING DEVICE OPERATIONAL TEST 1.37 A TRIP ACTUATING DEVICE OPERA'TIONAL TEST shall consist of operating the l
Trip Actuating Devico and verifying OPERABILITY of alarm, interlock and/or trip functions.
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.38 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE l
or CONTROLLED LEAKAGE.
UNRESTPICTED AR Nr 1.39 An-UNRESTRICTEb AREA : hall bc ny cr:c at er b yend th: SITE SOUNDARY l
[ 4ae:: to "ieb i not centre!!ed by the ':cen::: f:.r perpece: c' prete: tier of 4edhidu l: fr:. ex;,0:ur: 10 radict-4:r :nd radi ::tiv materici:, Or alc 07 withi-the-S W -BOUND ^RV u:ed for re'.i. dent?al-quar 4e.r: er for indus* M
/c isercial, irtstitution:1, Ond/or recreational purposes.
utJPESTRitTED AAEA means an em gccess to which is /
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()ci.thqr bry\\iierd Aor ( onYrollt.d kx3 the hcen see.
V0GTLE UNITS - 1 & 2 1-6 Amendment No. 32 (Unit 1)
Amendment No.
12 (Unit 2)
TABLE 3.3-3 (Continued)
TABLE NOTATIONS
- Time constants utilized in the lead-lag controller for Steam Line Pressure-Low are ty > 50 seconds and t 1 5 seconds.
CHANNEL. CALIBRATION shall 3
ensure that these time constants are adjusted to these values.
- The time constant utilized in the rate-lag controller or Steam Line Pressure-Negative Rate-High is greater than or equal to 50 secom's.
CHANNEL CALIBRATION shall ensure that this time constant is adjusted to tnis value.
- Feedwater isols. tion only.
Turbine trip occurs on reactor trip, aDuring refurling operations.
During power operation.
This is an initial setpoint only.
The trip setpoint will be set at 50 times background level.
Background ' evel should be deter-mined at or near the end of the first fuel cycle.
cSetpoints will not exceed the limits of Specification 0.11.2.-1.
-bR. If_ E
- 6. 7."(f. f. 7
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<0GTLE UNITS - 1 & 2 3/4 3-35
I RADIDACTlVE EFFLUENTS BASES DOSE (Continu Reactor Ef uents for the Pu se of Evaluating C pliance with 10 CF art 50, Appendi
" Revision 1, Oc ber 1977 and Regul ory Guide 1.113, "J timating Aquat' Dispersion of Ef ents from Acciden and Routine Reactof Releases for he Purpose of Imp menting Appendix I April 1977.
gggb f
This specific ion applies to the 'elease of radioacti materials in liquid '
effluents from e.h unit at the site When shared Radwas Treatment Systems a used by more r one unit on a s
, the wastes from units are mixed for shared trea ent; by such mixin, the effluent relea s cannot accurately ascribed a specific unit.
n estimate should b made of the contribu ons from ejc unit based on in t conditions, e.g.,
ow rates and radioa vity con trations, or, if practicable, the tr ted effluent releas may be a ocated eqcally to h of the radioactiv aste producing uni sharing the adwaste Treau4ent tem.
For determini conformarce to LCO, these alloca-tions from share adwaste Treatment Sy ems are to ta added o the releases specifically a ributed to each unit,.t'o obtain the total r eases per unit.
3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM N ot us ed. "^ """" '
' ^ ' " ^ ' ' "
" *-^^' *~ '^- ^^'" ~ +"'+ *" 4 syste ill be available for se whenever liquid luents require trea nt pri to release to the e ronment.
The requi
.nt that the appropr' te portions o
tnis system be used - - n specified provide assurance that the r eases of adioactive materials n liquid effluents 1 be kept "as low as s reasonably achievable." This ecification impleme s the requirements of 0 CFR 50.36a, General Design Cr' erion 60 of Appendi A to 10 CFR Part 50 the design i
objective give in Section II.D of endix I to 10 CFR Pa 50.
The ripecified limits gover ng the use of apprope ate portions of the quid Radwaste Treatmen t
System wer specified as a suitM le fraction of the do design objectives se forth i ection II.A of App dix I, 10 CFR Part 50 or liquid efflu g g g his specification a lies to the release o radioactive materials in 1,i id effluents from-ch unit at the site.
en shared Radwaste Tre
.ent Eystems are used by re than one unit on a te, che wastes from al units j
are mixed for shar treatment; by such m' ing, the effluent relea t
accurately be a ribed to a specific un'.
An estimate should b made of the s cannot contributions rom each unit based on nput conditions, e.g.,
ow rates and radioactivi concentrations, or, i not practicable, the tr ted effluent
/
releases.ay be allocated equall o each of tha radioacti waste producin units aring the Radwaste Tre. ment System. 'For determ ing conformance o l
LCOs these allocations from hered Radwaste Treatment ystems are to be added t-he releases specifical attributed to each unit o obtain the tot,a' l
eleases per unit.
/
3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all these outdcor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains i
j connected to the Liquid Radwaste Treatment System.
Restricting the @antity of radioactive snaterial contained in the specified tanks provides assurance that in the event of an
- ncontrolled release of the tank's contents, the resulting concentrations wouid be less than the limits of 10 CFR Pat 20, Apptr.db S, Tdh II, Cel=r 2, at the nearest potable water supply and the nearest surface water supply inRan UNRESTRICTED AREA.
\\,f '
V0GTLE UNITS - 1 & 2 8 3/4 11-2 20.13 02. (9 GN
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ACMiNISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 1)
Identification of a sampling schedule for the critical variabits
.nnd control points for these variables, 4
2)
Identification of the procedures used to measure the values of the critical vaciables, 3)
Identification of process sampling points, 4)
Precedures for the recording and management of data, 5)
Procedures defining corrective actions for all off-control point chemistry conditions, and 6)
A procedure identifying:
(a) the authority responsible for the interpretation of the data.and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
post-Accident Samolino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and contJinment atmosphere samples under accident conditions.
The program shall include the following:
4 1)
Training of personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance c' sampling and analysis equipment, A program which will enstre the capability to monitor piant v&riables e.
and systems operating status during and following an accident.
This program shall include those instrusaents provided to indicate system operating status and furnish information regarding the release of i
radicactive materiels (Category 2 and 3 instrumentation as defined in Regulatory Guide 1.97 Revision 2) and provide the following:
1) preventive maintenance and periodic surveillance of instrumentation.
2) pre planned operating procedures and back-up instrumentation to be used if one or more monitoring instruments become inoperable.
3) administrative procedures for returning inoperable instruments to OPERABLE status as.soon as practicable.
l TS I._J\\ sed 2.
b V0GTLE UNITS - 1 & 2 6-16
INSERT 2 f.
Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFP, 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievaH e.
The program-(l) shall be contained dr. the CDCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exccaded.
The program shall includa the following elements:
1)
Limitations on the operability of radioactive liouid and gaseous monitoring instrumentation including surwillance tests and setpoint determination in accordance with the methodology in,the_0DCH, s r 77 all Wnes
^
- 2) diMtationMon the concer.trations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming N
to 10 CFP, Pet 20 /4per. dix 0, Table :!, Cclumn 2, ten times %e n IO(.FR2.0, AffendM 8(to PMatro bs 20.1001-)
NE8oT,$bfeY't oDQ'hT' a n a l viivd fan d i n a r + 1"e'1149 konitorina,samn r
3) a 1d and gaseous effluents in accordance with 10 CFR 907146-and with the methodology and parameters in the ODCM, N
- {
4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLI". frnm radioactive meterials in liquid efflue..ts rehased from each unit to i
UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 3)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatsent systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for tha annual dose or dose comitment conforming to Appendix I
),nes N' Q
g n3 4 7)
Limitations 4on the doet rate rc:ultin;; from4 radioactive material released in gaseous effluents to areas beyond the SITE E2!f'9ARY conforming to ee-dese: ;;;cciated with 10 C-FR Put 20, r4peneix e, T ue ::, Colum, :, ten wes the conceniccrtions stoked in 16UR Part 20, AppendtX B
[
(t c) poco sco(>hs 20. I3o1 - 2o.2'+ o D, TMc a, column 1., << Nc GDN6 Fonds to a dose rate of 500 rnrem /gegr total eHective dose equivale.nt,
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ADMINISTRATIVE LC.iTROLS 6.8 REPORTING REQUIREMENTS ROUlINE REPORTS 6.8.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Adniinistrater of the Regional Office of the NRC unless otherwise noted.
STARTUP REPORT 6.8.1.1 A summary report of plant startup and power escalation testing shall be submitted following:
(1) receipt of aa Operating License, (2) amendment to the license involving a planned increase in power level, (3) inttallation of fuel that has a different design or has been manufactured by a different fuel stpplier, and (43 modifications that may has a s ignificantly altered the nuclear, thermal, or hydraulic parformance of either unit.
The initial Startup Report shall address each of the startup tests iden-tified in the Final Safety Analysis Report and shall include a descriptien of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satis-factory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
Subsequent Startup Reports shall address startup tests that are necessary to demonstrate the acceptability of changes and/or modifications.
Startup Reports shall be submitted within:
(1) 90 days following comple-tion of the Startup Test Program, (2) 90 days following resumption er commence-ment of commercial power Lperation, or (3) 9 months following initial criticality, whichever is earliest, If the Startup Report does act cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commcrcial operation), supplementary reports shall be submitted at least every 3 months until all three eU.nts have been completed.
ANNUAL REPORTS **
6.8.1.2 Annual Reports covering the activities of the plant as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
Reports required on &n annual basis shall include:
A tabulatirn on an annual basis of the number of plant, utility, a.
an otho' personnel (including cont ractors) receiving exposures 9 eater than 100 mrem /yr and their associated man-rem. exposure according to work and job functions" (e.g., reactor operations and "This tabulation supplements the requirements of 520.;C7 of 10 CFR Part 20.
- A single submittal may be made for Units 1 and 2.
The submittal should combine those sections that are common to both un ts at the plant.
,e 3%
parqre p h 20 220 b' V0GTLE UNITS - 1 & 2 6-17 j
i I
A0HINISTRATI"E CONTROLS l
RECORD RETENTION (Continued) h.
Records of inservice inspections performed pursuant to these Technical Specifications; i.
Records of quality assurance activities required by the Final Safety
]
Analysis Report; j.
Records of reviews performed for-changes made to procedures or
]
equipment or reviews-of tests and experiments pursuant to -10 CFR 50.59; i
k.
Records of meetings of the'PRB and the SRB; 1.
Records of the service _ lives of all hydraulic.and mechanical
[
snubbers required by Specification 3.7.8 including the date et which the service life commence and at.ociated installation and 4
}
mainten n:e records;-
Records of secondary water sampling and water quality; and m.
n.
Records of analyses requitad by the Radiologic.) Environmental 1
Monitoring Program that would permit evaluation of the accuracy of.
the analysis at a later date.
This should include procedures
[
effective at specified times and QA records' showing that these i
oroceduras were followed.
l 0.
lInsect 6]
6.10 RADIATION-PROTECTION-PROGRAN 6.10.1 Procedures for personne1~ radiation protection shall be prepared consistent
[
with the requirements of 10 CFR Part 20 and shall be-approved, maintained, and adhe.ed to for all cperations involving personnel radiation exposure, f 20.S oy
( [201 3 e.11 HIGH RADIATION AREA
" control device or " alarm signal" required by paragraph 20.200sPursu 1
6.11.1 c,each high radiation area, as defined in 10 CFR Part 20,.in which-the intensity of radi n 1:
tion is' greater than 100 mrem /hr but less than 1000 mR/h at ?! ci(IS "., 30cm0&l fram the radiation source or from any surface which the radiation penetrate Q'
shali be barricaded and conspicuously posted as -a high radiation _ area and i
t.r.:rance thereto shall be controlled. by requiring; issuance of 'a Radiation Work Dermit (RWP).
Individuals qualified in radiation protection procedures..(e.g. -
Health Physics Technician) or personnel continuously escorted by such individ -1s~
aay be exempt from the RWP issuance requirement during the performance of-their assign a duties in high radiation areas with-exposure-rates greater t' j-
'100 mrem /hr uut-less than 1000 mR/h, provided they are otherwise following' plant radiation protection procedures for ently into such high radiation areas.
Any individual or group of individuals-permitted to enter-such areas shall be
,9cvided with or accompanied cy one or more of?the following:
l a.
A radiation monitoring device which continuously indicates the radiation dose rate 1in the area; cr 5
VCGTLE UNITS _- 1 & 2 16-23 L
m
i l
4i-ADMINISTRATIVE /.)NTROLS 1
6.11 HIGH RADIATION AREA (Continued) g.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset -integrated 4
i dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have oeen established and personnel have been made knowledgeable of them; or An individual qualified in radiation protection-procedures with a c.
i radiation dose rate monitoring device, who is responsible for providing i
positive control over the activities within the area and sMll-perform perlooic radiation surveillance at the frequency soecified by the F
Health Physics Superintendent in.the RWP.
a
, 30cm 02lnb u
6.11.2 In additic, to the requirements of Spec!fication 6.11,1,/ areas accassible to personnel with radiation levels greater than-1000 mR/h at 5,c (IS % )
from the radiation source-or from any surface which +be radiation penetrates shall be provided with lo:ked doors to prevent unauthorized entry, and the keys shall be maintained.under the administrative control of the shift Foreman on i_
duty and/or health physics supervision.
Doors shall remain lo;ked except during j
periods. of 1 ass by personnel under an approved _ RWP_ which shall specify the dose rate levels in the immediate work areas and the maximum l allowable stay time for individuals in that area.
In-lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous i
surveillance may_ be made by personnel-qualified in radiation protection procedures to provide positive exposure control over the activities t, ing j
performed within the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 10C0 mR/h that are located within large areas,_ s' ch as u
PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that 4
individual area shall be barricacied, conspicuously posted,_ and a flashing light shall be activated as a warning device.
!j:
6.12 PROCESSCONTROLPROGRAM(PCR i
6.12.1 The' PCP shall be approved by the Commission prior to' implementation.
6.12.2 Licensee-initiated changes to the PCP:
a.
Shall be submitted to the Commission in the Semiannual Radioactive i;
Effluent Release Repcrt for the period in which.the change (s) was
.made.
This submittal shall contain:
u 1)
Sufficiently detailed infoer.ation to totally-' support the rationale for thet change. without' benefit of additional or j
-supplemental information;<
'2)
A determination that 4he-change did not reduce the overall-conformance of the solidified waste product to existing criteria for solid wastes; and l
4 V0GTLE UNITS - 1 & 2 6-24 1
ADMINISTRATIVE CONTROLS 6.12 PROCESS CONTROL PROGRAM (PCP) (Continued) 3)
Dccurcatetica af the feet-that th; chang: h;; bc:n r:.icacc and Stanc acceptable by the-fRB.
a Mer review and, ace.eFtanc.t h +he PR B and the b.
Shall become effectiveppen-approval Whe General Manager-Nuclear Plant.
of 6.33 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.13.1 The ODCM shall be approved by the Commission prior to implenentation.
6.13.2 Licensee-initiated changes to the ODCM:
L5d 7 r/
a.
S 11 be submitte to the Commission
~ the Semianual fpfdioactive I
ffluent Releas Report for the per' d in which the c nge(s) was mada effectiv.
This subn.ittal s 11 contain:
1)
Suff' iently detailed in rmation to totall support the ra anale for the chan without benefit additional or pplemental informa on.
Information mitted should co ist of a package of th e pages of the OD to be changed wi each page numbered, d ed and containing e revision number together with appropria analyses or evalugtions justifying t change (s);
2)
A determi ation tnat the cha e will not reduce
.0 accuracy er /
reliabi ity of dose calcul ions or Setpoint d erminations;
/
and
/
3) 0, umentation of the 4ct that t'le change as been reviewed nd A ound acceptable by he PRB.
b.
1 jecome effer.tig icoon approval by ty General Manager uclear 6.14 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEM Uot u s e d.
6.14.1 Licensee-initi ed major changes to he Radwaste Trea nt Systems (iiquid, gaseous, an solic):
a.
Shall 4 ieported to the Co ssion in the Semi nual Radioactive Effl nt Release Report for the perico in whi the evaluation was rev'ewed by the PRB.
The discussion of each hange shall contai.
)
A summary of the valuation that led o the determinatic that the change coul De made in accord ce with 10'CTR 50.
2)
Sufficient d ailed information totally support t e reason for the ch ge without benefit f additional or su lemental informati.;
DELETED
^ Licensees may cnco e to submit the info mation called for this Specification is part of the ar> ual FSAR upoate.
V0GT_i UN:~S - 2 & 2 6-25
INSERT 7 a.
Shall be documented ant. records of reviews performed shall be etained as recuired by Specification 6,9.30.
This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the {'__s
- s h((./ 3021 change (s) and
-g j
- 2) A determination that the change will maintain theplevel of radioactive effluent control required by 10 CFR 20.106, 40 l
CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or'setpoint calculations.
]
b.
Shall become effective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.
C.
Shall b? submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semihnnual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date-(e.g., month / year) the change was implemented.
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