ML20125C713

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Proposed Tech Specs to Incorporate Requirements for Annual Radioactive Effluent Rept in Lieu of Current Semiannual Rept
ML20125C713
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 12/07/1992
From:
GEORGIA POWER CO.
To:
Shared Package
ML20125C710 List:
References
NUDOCS 9212140044
Download: ML20125C713 (8)
v • d • e


Text

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ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS .

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT PROPOSED TFLHNICAL SPECIFICATION CHANGES p_. PDR Ils

d INDEX ADMINISTRATIVE CONTROLS SECTION

'6.4.2 SAFETY ~ REVIEW BOARD (SRB) ,

Function.. .. . .......... . .. . ..... . . ............. 6-9 Composition.... .............. ........................... 6-10 Alternates........... ............................... ... 6 Consultants........ .. . . . . . . ................ ........... 6-10 Meeting frequency. . ... . . . . .. ......................... 6-10 Quorum............ ............... .......... ............ 10 Review.... ...... ...... . . . . . ............................ 6-11 Audits.... .. .............. .. ....................... 6 Records................... ............................... 6 6.5 REPORTABLE EVENT ACTI0N..................................... 6-13 6.6 SAFETY LIMIT VIOLATION...................................... 6-13

6. 7 PROCEDURES AND PR0 GRAMS..................................... 6-13 6.8 REPORTING REQUIREMENTS 6.8.1 ROUTINE REPORTS. ..... .................... .. .. ... , 6-17 Startup Report... ............................. ........ . 6-17 Annual Reports................. ............... .......... 6-17 g Qual Radiological Environmental Surveillance Report.....

6-18 Scri;rnu' Radioactive Effluent Release Report............ 6-19 q '-/(n31stct l 7 .J

' w ,thly Mon Operating Reports'.. .............................. 6-21 Core Operating Limits Report ............................. 6 6.8.2 SPECIAL REP 0RTS........................................... 6-21a-6.9 . RECORD RETENTION........................................... 6 .

V0GTLE UNITS - 1 & 2 XXIII- Amendment No. ~ 44' (Unit 1)

Amendment No. 24 (Unit 2)

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DEFINITIONS-

-MEMBER (S):0F THE'PUBLIC-1.1B MEMBER (S) 0F THE PtlBLIC shall include-all persons who are not'occupa- 9 tional_ly associated _with the plant._ This category does not include employees of the licensee,_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 recre-ational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL gg d g b rn 1.19 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall conta'in the methodology and parameters used in the calculation of offsite_ doses d;; t. 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 INSER,T 1 OPERABLE - OPERABILITY 1.20 A system, subsystem,: train, component or device shall be OPERABLE or.  :

have OPERABILITY when it is capable of performing its specii ted function (s),

and when all- necessary attendant -instrumentation, ' controls, electrical power, cooling or- seal water, lubrication- or other auxiliary equipment that' are required for the system,_ subsystem,-train, component, or device to perform its

~

function (s)'are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond:to any one_ inclusive- j-combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental .l!

nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the. provisions of.10 CFR 50.59, or (3) otherwise approved by the . Commission.

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube .l-leakage).through a nonisolable fault in a Reactor Coolant-System' component-body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM 1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current _ formulas, l sampling,- . analyses, tests, 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-

-to assure compliance with 10 CFR Parts 20, 61, and 71 g d R d d =d State

, V0GTLE-UNITS - 1 & 2 1-4 Amendment No.-32 (Unit 1)

-Amendment No. 12 (Unit 2)-

m .2. _ _; _ _ _ - . - _ _ _ _ _ . _ . ._ _ _ _ _ _ . _ _ _ . . . _ , . ~ . . _ , . -

INSERT 1 The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.7.4 and (2) descriptions of the information that should beyyded in the Annual Radiological Environmental Surveillance apC,;r.=:.\ Radioactive Effluent Release Reports required by Specifications .8.1.3 and 6.8.1.4, Annual u -

r m g gp - bd The Seriana=l Radioactive Effluent Release Report ering the operation of-the unit during the previous S -^ nth: ef ep r: tie.. shall- be submitted [

~/

1 within 50 d:y: :ft:r 2:ne:ry.1 :nd July 1 of.each year. The report shall N acaudtr-e-summary i the auantities ot radioactive 1iquid-and oa wous:

effluents and solid waste released from tne unit. . ine material provided shall be-(1) consistent with-the objectives outlined.in the ODCM and PCP -

and (2)- in conformance with 10 CFR 50.36a and Section _IV.B.1 of' Appendix. I to 10 CFR Part 50.

        • A single submittal may be made for Units 1 and 2. .The submittal.

should combine those sections that are common to both units'at the plant; however, the submittal shall specify the releases- of gaseous and liquid radioactive material from-each unit _ and of solid _

radioactive material from the site.

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ADMINISTRATIVE CONTROLS

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ANNUAL RADIQk6GICAL ENVIRONMENTAL #fRVEILLANCE REPORTontinued)

T Annual Radiological nvironmental Survei ance Report shall .clude the esults of analysis o all radiological en ronmental samples of all ironmental radiatio easurements taken ing the period pur ant to the locations specified the table and fig s in the Offsite 0 e Calculation Manual, as well summarized and tabu ted results of the analyses and measurements i the format of the t e in the Radiologi 1 Assessment ~ Branch Technical P ition, Revision 1, ember 1979. The r iological level of radionuc es which are natur y occurring not in ded in the plant effl nts need . be reported. In't event that some in- vidual results are not vail-abi for inclusion with e report, the repor shall be submitted not' g and p plaining the reason or the missing res s. The missing data s 11 be submitted as soon practicable in a su ementary report. .DE LETE D The repo shall also include e following: a summar description of the Radiolo cal Environmental M itoring Program; at lea two legible maps coverin dl sampling locatio keyed to a table givin istances and direc ons from oint midway betwee he two reactors; the re ts of licensee par ci-pa n in the Interlabor ory Comparison Program a the corrective act' n J4 en if the specifie rogram is not being perf ed as required by Specification 3.12. , reasons for not conduct g the Radiological vironmental

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Monitoring Progr as required by specific on 3.12.1, and disc sion of all deviations fr - the sampling schedule of able 3.12-1; discuss n of environ-mental samp measurements that exceed he reporting levels Table 3.12-2 but are t the result of plant eff ents, pursuant to ACT N b. of Specifica-tion 7 2.1; and discussion of al analyses in which th LD required by

- a . {-1 was not achieved.

Uf' RADIOACTIVE EFFLUENT RELEASE REPORT HT*

' <se rt 4- l

.1.4 A acuta ne ricanual ?cdicact:<c Ef'Nent 9:lene 9epert; ecuer'ng the operation of the u 't during the previous months of oper ion shall be submitted within 0 days after January and July 1 of e year. Tne per od of the first r ort shall begin with e date of initi criticality.

The miannual Radioactive luent Release R orts shall inclu a summary of the uantities of radioacti liquid and gase s effluents and s id waste reie ed from the unit as ou ined in Regulator Guide 1.21. "Hea ring, Evalu -

t , and Reporting Radioa ivity in Solid W es and Releases Radioactiv

.aterials in Liquid and seous Ef fluents f om Light-Water-Coo ed Nuclear P er Plants," Revision 1, ne 1974, with dat summarized on a qu terly basis ol-iv ing the format o Appendix B thereof For solid wastes the format f Table 3 in Append B shall be supple.ented with three ad-itional cate ries:

ciass of sol'c stes (as defined b 10 CFR Part 61), t e of contain s .g., LSA, T e A, Type B, large ,uantity) and SOLIO ICATION agent or absor-cent (e.g. :cment, urea formal enyde). gg Lg7g g I Semiannual Radica ive Effluent Release eport to be s mitted witnin

,0 s af ter January 1 e each year shall inc1 ae an annual mary of hourly V0GTLE UNITS - 1 & 2 6-19 i

o ADMINISTRATIVE CONTROLS 6.12 PROCESS CONTROL PROGRAM (PCP) (Continued)

3) Occumentation if tht f;;t th;t tF: d;ng; hn b :n rc. i = nd found acceptab'.e by the NO.

amer review anel gcc.eptec.e b +he PR B anc( the.

b. Shall become ef fectiveAgen-approval Whe General Manager-Nuclear Plant, of 6.13 0FFSITE DOSE CALCULATION MANUAL (00CM)_

6.13.1 The ODCM shall be approved by the Commission prior to implementation..

6.13.2 Licensee-initiated changes to the 00CM: I^5d 7 n/

a. 5 11 be submitte to the Commission the Semiannual dioactive ffluent Releas . Report for the per' d in which the c nge(s) was made effectiv . This submittal s 11 contain:
1) Suffjliently detailed in rmation to total'1 support the ta fonale for the chan without benefit additional.or pplemental informa on. Information mitted should co eist 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 evalu ions justifying t change (s); -
2) A determi ation tnat the cha e will not reduce e accuracy or reliabi ity of dose calcul ions or Setpoint d erminations; and
3) 0 umentation of the ct that the change as-been reviewed nd ound acceptable by he PRB, D. 1all become-effectiv, upon approval by tt 3e General Manager- uclear

. Plant. / /

6.14 MAJOR CHANGE 5 TO LIQUID. GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEM u o t used.

6.14.1 Licensee-initi ed major changes to he Radwaste Treat nt-Systems; (iicuid, gaseous, an solid):

a. Shall reported to the Com ssion in'the Semi nual Ra'dioactive.

Effl nt Release Report for the period in whic the evaluation-was  !

, rev'ewed by the PRB. The discussion of each hange shall contai l

) A summary of.the valuation that lert o the determinatio that

, the change coul De made in accord ce with 10 CFR 50.  ;

2) Sufficient d ailed information totally support t e' reason-for the ch e without benefit f additional or su lemental informati  ;

DELETE.D

^ Licensees may cnco to submit the info mation called for this Specification is part of the'a ual FSAR upoate.

v0G7 i WGS 1&2 6-25

INSERT 7

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.3.o. This documentation shall contain:
1) Sufficient information to supoort the change together with the appropriate analyses or evaluations justifying the change (s) and
2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint. calculations.
b. Shall become effective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.

C. Shall be submitted to the Commission in the form of a complete, Megof the entire ODCM as a part of or concurrent with th Radioactive Effluent Release Report for the

[/\ntgAqk R;;,i;....,

per piod f Ah J[ report in which any change to the ODCM was made.

Qv ETeh change shall be identified by markings in the mr.rgin 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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