ML20115C954

Proposed Tech Specs Implementing New Requirements of 10CFR20 Including,Revising Definition of Members of the Public & Unrestricted Area & Deleting Reference to ETS Footnote Re Radiation Monitoring Instrumentation

ML20115C954
Person / Time
Site:	Hatch
Issue date:	10/14/1992
From:	GEORGIA POWER CO.
To:
Shared Package
ML20115C939	List: HL-2409, Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-01 ML20115C954
References
NUDOCS 9210200154
Download: ML20115C954 (39)

Text

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ENCLOSURE 3

' PLANT 11ATC11- UNITS 1 AND 2 NRC DOCKETF $0 321,50-366 ,

OPERATING LICENSES DPR 57, NPF-5 REQUEST TO REVISE TECilNICAL SPECIFICATIONS IMPLEMENTATION OF Tile NEW 10 CFR 20 REOUIREh.iEtiTS PAGE C114tiGE INSTRUCTIONS' j

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a ENCLOSURE 3 PLANT llATCil- UNITS 1 AND 2 i l

NRC DOCKETS 50-321,50166 OPERATING LICENGES DPR 57, NPF-5 REQUEST TO REVISE TECilt41 CAL SPECIFICATIONS '

JMPLEMENTATION OF Tile NEW 10 CFR 20 REOUIREMEN))i j I

PAGE CliANGE INSTRUCTIONS

, The proposed changes to the Plant liatch Unit I and Unit 2 Technical Specifications will -

l be incorporated as fo"ows:

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! 1.0-9 1.0-9  :

3.2 18 3.2 18

• 3 3.15-8 3.15 8  :

., 3.15-22 3.15 22' 6-15 6-15*  ;

6 20 6 20*

! '6 23 6-23*

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3/4 3-44 3/4 3-44 3/4 11-8 3/4 11-8.

B 3/4 11-2 B 3/411-2*

6-14 6-14*

6-18 6 18*

6 22 6 22*

6-22a 6 22a*

Supersedes proposed changed Technical Specification page submitted by Georgia Power Company letter dated September 21,1992.

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1.0 DEFlf{lTIONS (Continued' ZZ. MEMBER OF THE PUBLIC l MEMBER OF THE PUBLIC means an individual in a controlled area or t.'NRESTRICTED AREA. However, an-individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.

AAA 11].E BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, based, or otherwise controlled by Georgia Power Company, as shown in figure 3.15-1.

BBB W RESTRICTED AREA UNRESTRICTED AREA means an area, access to which is neither limited nor contrclled by the licensee.

CCC. EE.0L- PURGING PURGE or PURGlhG 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 confine.'..nt..

DDD. VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such : manner that replacement air or gas *.s not provided or required during VENTING. The term " vent" used in system names, does not imply a VENTING process.

HATCH - UNIT 1 1.0-9 ~ _techsp\h\92-16U1. pro /170

.y-Tetde 3.2-8 4

$ RADtATION MONITORING SYSTEMS WHCH LIMIT R ADICACTIVITY RELEASE I

Ref. Instr.; ment Trip Required Trip Cetting Action to be taken if Remarke E

No. Cerv 5 tion Oyeble there are not two operstde or t-W trip eystems (a) Nomencia- Chermele ture pos Trip

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Systam (b)

1. Off ges Upecate/ 1 At a value not (c) id) 2 upscales, or 1 Post Treatment Downscele to exceed the downecole eruf 1 Radiation equivaient of upecafe. or 2 h Monitore the eteck re- scales wig iociate lease Imt the SJAE oftp I indicated in Specificetmn 6.18(7) l

2. Refueling Floor Upecele 2 $20 mrlbr Ceese refueling opere- 2 upacete unil l

Exhaust Vent trone. if in progrees isolete the seccadery Radiation footste the secondary containment and Monitore coe ' ent and start initiate the eterufby the sta.=fby see treet- ges treatment everem

. ment system.

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3. Reactor Endg. Upecele 2 $20 mr/hr ledete the seconc8ery 2 upaceae enilisolete Exhaust Vent cor teinment. etert store the seaondary con-E detfor- by goe treetment eyotem, teinment and initiate Monitore close prirnery contain- the etendby goe ment and went welves. treatment eyetem.

4 Control Room Downeeste 1 10.015 mr/hr Refer to Specificata 1 upscale or 2 deem-

c.  : Intake 3.12.C. end 3.12.D. ecelee wEl estuste Radiation Hi $1.0 mr/hr the MCRECS in the y Monitore control room pree-surization mode.

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i RADI0 ACTIVE EFFLUENTS l

LIOUID HOLOUP TANKS

! LIMITING CONDITION FOR OPERAT'0:1 i

j 3.15.1.4") The contents within any outside temporary tank l shall be limited to $10 curies, excluding tritium and i dissolved or entrained noble gases. .

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APPLICABILITY i' At all times. This specification does not apply to disposable liners used for shipment of radioactive waste.

! ACTION ,

i a. With the contents within any outside temporary tank ,

1 exceeding the above limit, immediately suspend all.

. additions of radioactive material to the tank and within  ;

i 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents within the limit and

provide notification to the Commission pursuant to j Specification 6.9.1.8. '

i f SURVEILLANCE RE0VIREMENTS-

! 4.15.1.4 The quantity of radioactive material contained in any outside temporary tank- shall be determined to be within the ,

! -above limit by anal rzing a sample of each. batch of radioactive

, material prior to its addition to the tank.

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a. -An outside timporary tank is.not surrounded by liners, ,

dikes, or. walls that arc capable of holding.the tank 1 contents and not having tank overflows and drains connected to:the. liquid radwaste-treatment system.

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d RADI0 ACTIVE EFFLUENTS BASES .

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3/4.15.1.3 L10VID WASTE TREATHENT This specification transferred to the ODCM per NRC Generic letter 89-01.

3/4.15.1.4 LIOUID HOLDUP TANKS

, Restricting the quantity of radioactive material contained in

the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting t

concentrations would be less than the limits of 10 CFR Part 20.1302(b)(2)(1) at the nearest surface water supply

, in an UNRESTRICTED AREA.

3/4.15.2 GASEOUS EFFLUENTS 3/4.15.2.1 DOSE RATE l This specification transferred to the ODCH per NRC Generic Letter 89-01.

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@RINISTRATIVE TANTRgts l

[M!iUAL pEPORTS (Continued 6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on sn annual basis of t5e number of station, utility and other personnel, including contractors, receiving exposures greaterthan100 mrem /yrandtheirags,ociatedmanremexposure t.ccording to work and job functions, e.g., reactor operations i and surveillance, inservice inspection, routine saintenance, special maintenance (describe maintenance), waste processing, and refuelina. The dose assignment to various duty functions may be estimates based on pocket dosimeter TLD, or film badge measurements. Smallexposurestotallinglessthan20%ofthe individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. Documentation of all ct.allenges to safety / relief valves,

c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specificatica 3.6.F.1. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiotodine cerformed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiolodine activity was reduced to less than limit. Each result shuuld include dtte and time of sampling and the radioiodine concentrations; (3) Cleanup system flow history starting 48 heurs 1 prior to the first ', ample in which the limit was exceeded; (4) Oraph of the I-101 concentration and one other radiotodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state levelt anc (5) The time duration when the specific activity of the priinary coolant exceeded the radiciodino limit.

d. Any other unit unique reports required on an annual bisis.

ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVfillANCE REPq@H 6.9.1.6 The Annual Radiological Environmental Surveillance r art covering the radiological environmental surveillance activities related to the plant during the previous calendar year shall be submitted before May 1 of cach year. The report shall include summaries, interpretations, and analyses nf trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The matarla) provided shall be consistent with the objectives outlined in the 00CM and Sections IV.tl.2. IV.B.3, and IV.C of i Appendix ! to 10 CFR Part 50.

a. A single submittal may be made for a multip'e-unit station. The submittal should combine those sections comon to all units at the station,

'This tabulation supplements the requirements of 20.2206 of 10 CFR Part 20. l 4

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LOMINISTRailV W RlR0tS PEQRJ PETINTION (Cnntingef1

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of tran,1cnt or operational cycles for those unit components identified in Table L.O.G-1.

f. Picords of reactor tests and experiments.

g. Records of training and qualification for current memrers of the unit .

staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

1 Records of Quality Assurance activities required by the QA Manual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PRB and the $RB.

1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.15.

m. Records of analyses required by the Raf'.tological Environmental Monitoring Program.

n. Records of tha urvice lives of all safety-related hydraulic and mechanical s a m rs including the date at which the service life commences anc aociatrd installation and maintenance records,

o. Records of reviews performed for changes made to the Off5ITE DOSE CALCULATION MANUAL and the PROCEST TONTROL PROGRAM.

6.11 RADIATION PRO ECTION PROGRAM Procedures for personnel radiatic prott.ction shall be prepaied consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiaticn exposure.

6.12 HIGH RADIATION AREA 6.12.1. In lieu of the ' control device" or " alarm signal" required by paragraph -

20.160)(a) of 10 CFR 20, each high radiation area in which the intensity of I radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation 9ork Permit *.

Any individual or group of individuals permitted Walth hysics personnel, or personnel escorted by Health Physics personnel in accordante with approved emergency procedures, shall be exempt from the RWP issuance requirement-tJring the performance of their assigned radiation p*otection daties, provided they comply with approted radiation protection proceduces for entry into high radiation areas.

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egi]1QIEATIVE CONTROLS 6316 POST-ACCIDENT SAMPLING AND ANALYS11 A program shall be established, implerented. and maintained to ensure the capability to obtain and analyre samples of reactor coolant, radioactive 4 ledines and partic'lates in plant gaseous effluents, and c'ntainment atmosphere under accident conditions.

The program shtl1 include the following:

(1) Training of personnel, (2) Procedures for samp19g and analysis, and

. (3) Provisions for maintenance of sampling and analysis equipment.

t 6.17 OffSITE DQSE CALCULATION MANUAL 6.lL1 Licensee-initiated changes to the ODCM shall: l

a. Be documented and racords of reviews performed shall be retained as l required by Tecanical Specification 6.10.2.c. This documentation l shall contain: j

1) Sufficient information to support the chango together with the appropriate antlyses or evaluations jt.stifying the charge (s),

and

2) A determination that the change will maintain the level of radioactive effluent centr 91 required by 10 CFR 20.1302 - 40 CFR

' Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of. effluent, dose, or setpoint calculations.

b. Become ef fective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.

c. Be submitted to the Commission in the form of a complete, legible copy of the entire ODCH as a part of, or ccMurrent with, the Semiannual 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, cicarly indicating thi area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

6.18 RAD 10AW'1E EFFtVENTS CONTROL PROGRAM A progra:a shall be established, implemented..and maintained conforming with 10 CFR 50.35a for the control of radioactive e'fluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effit.cnts as low as reasonably achievable. The program (1) shall be conttined in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elemet.ts:

1) Limitctions on-the OPERABILITY of radioactive liquid and gaseous monitoring-instrumentation including surveillance tests and setpoint -

determination in accordance with the methodology it. the ODCM,

2) Limitations at all times on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentrations stated in 10 CFR Part 20, An andix B (to paragrapt.s 20.1001 - 20.2401), Table 2. Colt,mn 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous-effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, i

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[')MINISTRATIVE CONTROLS _.

I RAD 10ACYlVE Ef f LUINTS CONTPOL PROCRAM (Continuedi

4) Limitations nn the annual N quarterly doses or due co imitmet.t to a MEMBER Of lHE PUBLIC from radioactive mater:als in liquid effluents released frcm each unit to UNRESTRICTED AREAS conforming to

j. Appendix ! to 10 CFR Part 50,

$) Determination of cumulative and projected dose contributions fro-

radioactive effluents for the currer'. calendar quarter and curren6 calendar yeai in accordance with the inethodology and parameters in th6 00CM at least every 31 days,

6) Limitations on the OPERABILITY and use of the liquid and gaseous effluent treatment systems to 9nsure that ihm appropriate portions j of these systems are used t: reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for t annual DOSC or dose commitment conforming to '

Appendix ! to 1( t Part 50,

7) Limitations at .

ies on the c5ncentretions of radioactive material release. 4 gasetus effluents to areas beyond the SITE

. BOUNDARY :onforming to 10 times the concentrations stated in j 10 CFR Pait 20, Appendix B (*o paragraphs 20.1001 - 20.2401),

4 Table 2, Column 1, which corresponds to a dose rate of 500

? mrem / year total effective dose equivalent,

8) Limitations on the annual and quarterly air Joses resulting from l noble gases released in gaseous effluents from each unit to areas beyond the $1TE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50, 4

9) Limitations on the annual and quarterly doses to a MEMBER Of lHE j PUBLIC from lodine-131,-lodine-133, tritium, and all radionuclides

! in particulate form with half-lives greater than 8 days in gaseous ,

! efflunts released from each unit to areas beyond the SITE BOUNDARY '

conforming _ to Appendix 1.to 10 CFR Part 50, and

! 10) Limitations on the annual dese'cr dose commitment to any MEMBER Of THE PUBLIC due to relcases of radioactivity and to radiation from uranium fusi cycle sources conforming to 40 CFR Part 190.

6.19 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i A program shall oe established, implemented, ar.d maintained to monitor i

the radiation and radionuclides in the environs of.the plant. The program shall provide (1) represent &tive measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained-in -

the ODCM, (2) conform to the guidance of Appendix 1 to 10 CFR Part 50,.

, ar.d (3) include the following:

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t) Monitoring, sampling, analysis, and reporting of-radiation and radionuclides in the environment in accordance with the methodology j and parameters in the ODCM, l . ,

.. 2) A land Use Census to ensure that changes in.the use of areas at and!

beyond the SITE BOUNDARY are identified and that modifications to the monitoring program.are made if required by the results of this.

census _. and

, 3) Participation in an Interl.avratory rparison drogram to ensure that indeperdent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample -

l matrices-are performed as part of the quality assurance program for ew ironmental monitoring.

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i 10 DEFINITIONS (Continued)_ _

MEMBER OF.THE PUBLIC l MEMBER OF THE PUBLIC means an individual in a controlled area or UNRESTRICTED AREA. However, an individual is r.ot a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.

SITE B001(DAB 1 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by Georgia Power Company, as shown in-figure 3.11-1.

11NPLSfRICTED AREA UNRE5131CTED AREA means an area, access to which is neither limited nor controlled by the licensee.

DOSE E0tilYAlHT IODINE The DOSE EQUINTNT I-131 shall be that concentration of I-131 (microcurie / gram), which alone would produce the same' thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-!33,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in table III of TID-14844 or those in NRC Regulatory Guide 1.109, Revision 1, October 1977.

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, cencentraticn, or other operating condition in such a manner that replacement air or gas .is required to purify the confinement.

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--s TABLE 3.3.6.1-;

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.c R ADf ATION MON *TORING INSTR'JVENTATI'W 8 ,

C z APPUCABLE Q MINIMUM CHANNELS OPERATIONAL ALAR 4' TRIP MEASUREMENT INSTRUMrNTATION OPERABLE CO*JDITIONS SETPO'NT RANGE ACTION

1. Off-Gas Post-Treatment Morutors 2 1. 2 (a) 10' to l'f cps 50 (2D11-K615 A, B)

2. Control Room Intake Monitors 2 1,2.3,4.5 1 rnr/hr 0.07 to 100 mr/hr 51 (1Z41-R615 A. B) w N

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• Value riot to exceed the equivalent cf tM eM release linut indicated in '

Specifestion 6.1E(7).

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RAD 10ACTlyLEFFLUENTS LLOUID HOLDUP TANK 3 LW111NG CONDITION FOR OPERATION 3.11.1.4N The contents within any outside temporary tank l shall be limited to s 10 curies, excluding tritium and dissolved or entrained nobio gases.

APPLICA8ILITY At all times. This specification does not apply to disposable liners ssed for shipment of radioactive waste.

ACTION

a. With the contents within any outsido temporary tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and 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 within the limit and provide notification to the Commission pursuant to Specification 6.9.1.8.

SURVEILLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in any outside temporary tank shall be determined to be within the above limit by analyzing a sample of each batch of radioactive material prior to its addition to the tank.

a. An outside tempor'ary tar? is not surrounded by liners, j dikes, or walls that are capable of holding the tank contents i and not having tank overflows and drains connected to the liquid radwaste treatment system.

l HATCH - UNIT 2 3/4 11-8 techsp\h\92-16UEJ. pro /48 L - .. . _

RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 L10010 WASTE TREATMENT This specification transferred to the ODCH per NRC Generic letter 89-01.

3/4.11.1.4 ' L10010 HOLDUP TANKS-Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting-concentrations would be less than the limits of 10 CFR Part 20.1302(b)(?)(1), at the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE This specification transferred to the ODCM per NRC Generic l.etter 89-01.

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MMINISTRATIVE CONTROLS ANNUAL REPORTS (Contiqqqdl 6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an Annual basis of the number of station, utility and other personnel, including contractors receiving exposures greaterthan100 mrem /yrandtheirassocialedmanremexposure according to work and job functics,(2) e.g., reactor operations l and surveillance inservice inspection, routine maintenance maintenance (describe maintenance), waste processing, and , special refueling. The dose assignment to variour duty functions may be estimates ta.ed en pocket dosimeter TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose no'd not be accounted for. In the aggregate, at least 80% of the totai whole body dose received from external sources shall be assigned to specific major work functions.

b. Documentation of all challenges to safety / relief valves.

c. The results of specific activity analysis in which the primary coolant exceeded the limits of S ecification 3.4.5. The following information shall be included: 1 Reactor power history starting e 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first samp e)in which the limit was exceeded; (2? Results of the last isoto prnor to exceeding the limit,pic analysis results for radiciodine of analysis performed while limit was exceeded and results of one analysis after the radiolodine was reduced to less than the limit. Each result should include date and time of sampling and th radioiodine cor.centrations; (3) Cleanup system flow histor starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> )rior to the first sample in which the limit w."s exceeded; (4) Grap1 of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5? The time duration when the specific activity of the primary coo ant exceeded the radioiodine limit,

d. Any other unit unique reports required on an annual o' asis.

ANNUAL RADIOLOGICAL ENVIRONMENTAL SVRVEllLANCE REPORT"3 6.9.1.6 The Annual Radiological Environmental Surveillance Report covering the radiological environmental surveillance-activities related to the plant during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries interpretations, and analyses of trends of the results of the Radiological, Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the ODCH and Sections IV.B.2, IV.B.3, a i IV.C of Appendix I to 10 CFR Part 50.

a. A single submittal may be made for a multiple-unit station. The submittal should combine those sections common to all units at the station.

2 This tabulation supplements the requirements of 20.2206 of 10 CFR Pa t 20. l HATCH - UNIT 2 6-14 techsp\h\92-16U20. pro /86

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ADMINISTRATlYE CONTROLS l i

RECORD RETEli(ION (Continued) i

c. lecords of radiation exposure for all individuals entering radiation control areas. l

d. Records of gaseous and liquid radioactive material released to the environs,

e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.

f. Records of reactor tests and experiments. '

g. Records of training and qualification far current members of the unit staff.

h. Records of in-service ins Technical Specifications,pections performed pursuant to these

i. Records of Quality Assurance activities required by the QA Manual.

1. J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PRB and the SRB.

4

' 1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.15.

m. Records of analyses required by the Radiological Environmental Monitoring Program,

n. Records of the service lives of all safety-related hydraulic and mechanical snubbers including the date at which the service life e

commences and assoclated installation and maintenance records,

o. Records of revtews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION DROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with m

4 the requirements of 10 CFR Part 20 and shall be approvedadhered exposure. to for all opera 6.12 (1[GB RADIATION AREA 6.12.1 In lieu of the "contrel device" or " alarm signal" required by paragraph of 10 CFR 20 20.1601(a)is rtdiation greater tha,n 100 mrem /hr but less than 1000 mremeach high radiation l barricaded and conspicuously posted as a high radiation areaand /hr entrance shall be

• thereto shall be controlled by requiring issuance of a Radiation Work Permit *,

Any individual or group of individuals permitted

• Health Physics personnel, or personnel escorted by Health Physics personnel in accordance with approved emergency procedures shall be exempt from the RWP issuancerequirementduringtheperformanceoftheirassignedradiation provided they comply with ap protectionduties{ryintohighradiationareas.provedradiationprotection procedures for en HATCH - UNIT 2 6-18 techsp\h\92-16020. pro /51

i ADMINISTRATIVE CONTROLS 6.16 POST-ACCIDENT SAMPLING AND ANALYSIS A program shall be established, irplemented, and maintained to ensure the capability to obtain and analyze samples of reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere under accident conditions.

4 The program shall include the .ollowing:

(1) Training of personnel, (2) Procedures for sampling and analysis, and (3) Provisions for maintenance of sampling and analysis equipment.

6.17 0FFSITE DOSE CALCULATION MANUAL 6.17.1 Licensee-initiated changes to the ODCH shall:

a. Be documented and records of reviews performed shall be retained

. as required by Technical Specification 6.10.2.o. This documentation shall contain:

1) Sufficient information to support the change together with the appro change (s)priate and analyses or evaluations justifying the

2) A determination that the change will maintain the level of radioactive effluent cout rol required by 10 CFR 20.1302 10CFR50.36a,andAppendix!to10CFlt 40 PartCFR Partnot 50 and 190, a dversely impact the accuracy er reliability of effluent, dose, or .tetpoint calculations.

b. Become effective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant

c. Be submitted to the Commission in the form of a cornplete, legible copy of the entire ODCM as a part of, or concurrent with, the Semiannual Radioactive Effluent Release Report for the period ef.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, hall clearly indicateindicating the date (the e.g.,area of the month page

/ year) the that changewaswas changed, implemented. and s

, 6.18 RADI0 ACTIVE EFFLVENTS CONTROL PROGRAM A program shall be established, . implemented, and maintained conforming with 10 CFR 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 achievable. The program (1 shall be.

contained and (3) shall- include in thereme ODCM, (2) dial actions to be taken wienever limits are exceeded. The program shall include the following elements:

1) Limitations on the.0PERABILITY of radioactive liquid and gaseous monitoring-instrumentation including surveillance tests and setpoint--

determination in accordance with the methodology in the ODCM, HATCH - UNIT 2 6-22' techsp\h\92-16U2D. pro /48

--~- .=ym,... ..,.p -*t---* * -

p *-7e"

i W

! 6.18 RADI0 ACTIVE EFFLUENTS CONTROLS PROGRAM (Continued) l 1

2) Limitations at all times on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS 3 conforming to 10 times the concentrations stated in 10 CFR Part 20 Table 2, Column, 2, Appendix B (to paragraphs 20.1001 - 20.2401), )

! 3) sampling, and anal i MonitoringInaccordancewithIbsisofradioactiveliquidandgaseousand effluents CFR 20.1302 with the met j and parameters in the ODCM,

4) Limitations on the-annual and quarterly doses or dose commitment to

+

a MEMBER OF THE PUBLIC from radioactive materials in liquid l effluents. released from tach unit to UNRESTRICTED AREAS conforming j to Appendix I to 10 CFR Part 50, q I 5) Determination of cumulative and projected dose contributions from .

radioactive effluents- for the current calendar quarter and current i calendar year in accordance with the methodology and parameters in 1 the ODCH at least every 31 days, l

! 6) Limitations on the 0PERABILITY and use of the liquid and gaseous.

i ffluent treatment systems to ensure that the appr riate artions-

of these systems are used to reduce releases of ra oactiv ty when >

the pro ected doses in a 31-day period would exceed 2. percent of

~

l l the gut elines for the annual dose or dose commitment conforming to -

3 Appendix I to 10 CFR Part 50,

-

i 4

7) Limitations at all times on the concentratior 4 of radioactive i material released in gaseou; effluents to-areas beyond:the SI1E

BOUNDARY conforming to 10 times the concentrations stated in

! '10 CFR Part 20, ppendix B (to paragraphs 20.1001 - 20.2401),

! Table 2, Column which corresponds to a dose. rate of 500-mrem /yeartotaleffectivedoseequivalent,

8) Limitations on' the annual and quarterly air doses resulting from ,

noble gases released-in gaseous effluents from each unit to areas-beyond the SITE BOUNDARY conforming to Appendix;I:to-10 CFR Part 50, I 9) Limitations on the annual.and quarterly doses'to a MEMBER OF THE Iodine-133, tritium,. and all radionuclides PUBLIC from form Iodine-131,h. half-live greater than 8 days in gaseous

in particulate wit effluents released from each unit to areas beyond the SITE BOUNDARY i contorming to Appendix.I to 10-CFR Part 50, and<

10) Limitations on the annual dose or dose commitment-to any MEMBER OF

THE.PUBLIC due:to releases of radioactivity.and to radiation from j uranium fuel cycle sources conforming to A0 CFR Part 190.

' 6.19 RADIOLOGICAL- ENVIRONMENTAL MONITORING PROGRAM - ,

E A

the program radiation shall andberadionuclides citablished, in the environs of theimplemented, lant. Theand maintained to-monito  ;

1 representative measurements o L program in;the: highest shall providepotentia(l)exaosure pathways, and (2 verification ofradioactivity-l the accurac of.the effluent monitoring program an modeling of environment 1 exposure pathwa s. The program.shall be contained j 'in the ODCM, conform to:t e uidance of Appendix ( )to 10 CFR Part-50, and include the foi owing: .

HATCH. UNITT2- 6-22a techsp\h\92-16U20.48 ,

( _ _ _

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Marked Pages t 4

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1.0 DEFINITIONS (Continued) Y M

___ _ r/ .

means An mdividual i 1 e. (.orttrolkd Area of ESTRICTED AMA, Howev% on indivMual is ZZ. MEMBERlM OF THE PUBLIC y nct a MEiMBER OF THE PuBLlC durig ag peritd

( m uAic.h the MEMBER (57 0F THE PUBLIC"shell he'ue: 011 per:On: u". 0 ar-e

/ not ::::p:t hn:11y :::: ht:d with the p unt.  % individual recciVCsj

t:g:ry d :: n:t 'n:hd :mphy :: Of th; utility, it; an oc_cu pationql c+ntrac-ter'er-er 't 't^nder . "he .  ::hd:d f rom thh- dose, eate9ery ::: per: n %+-ent:r th: 't: t0 ::F;4ee.

qu pr:nt er t: m:he detW rbt.

i " h ::teg0ry dOO inc hde per:On: 't0 200-pert 40n: Of th: tit: f0r r;;rcathn:1, :::;p:thn:1, er :th:r purp ::: nt assee4eted-with the-p h nt.

J' #

L a L AAA. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, based, or otherwise controlled by Georgia Power Company, as shown in figure 3.15-1.

- e -- < ,

"" "# " '8 BBB. ONRESTRICTED AREA Iimitec/ nor co$ "d bg %e beensee.

ntrolle 1

-Aft-UNRESTRICTED AREA : hell be 0;;y Orc st-er- beyond-the SIT SO'JM0'"Y t: whh 5 :::::: f+r purp0:e: Of p Ote:the ef i d*"dde:M n 'rer expe:tr: t: radhth: :nd-r:44+as444e materbh % eat-sentrr:1hd by the M: ente:. 9h

[ 4fre4udet-eftj- c re w*th h tA -S!TE B0"MD.^"Y u 0d for

+ee44ent r h1 qu:rt0r: cr4+r- Sng-term-4ndustr-iah.

<0 :rc hl, in:t tet hn:1, 2nd/ar recreat hnet purp :st.

i 2 w jw J%

CCC. PURGE - PURGING 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.

000. VENTING VENTING is the controlled process of discharging air or gas fror.a confinement to maintain.t'emperature, pressure, humidity, concentration, or'other operating condition in such a manner that replacement air o gas is not provided or required during YENTING. The ters " vent" used in sysum names, does not imply a VENTING process.

HATCH - UNIT 1 1.0-9 Amendment No.110 1

1

.sh._

Table 3.2-8 1 RADIAftON MONITORING SYSTEMS witCit limit RA0lOACTIVlTVRemarks RELEASE M .~ trip Setting Action to be taken if o Trip Required there are not two operable Z Ref. - -Instrument '

Condition. Operable or tripped trip systems e No. Nomencia - Channets e2-

- '(a) ture per T rip System tb_1 i

l ML - 2 upscales, or 1 j

At a value not. (c) (d)' downscale and 1 l Orr-gas- t>pscale/ 1

to exceed the "pscale, or 2 down- i 1'  :

fust Treatment Downscale equivalent or scales wilt isolate  ;

Radiation the stack re.

Monitors

8. ce d n^

" C TkChorg hC)

~ '

J 2 Upscale wllt j Cease reruellng opera-2 ^t - --* -t isolate the secondary J Rertel8ng Floor' Upscale - tions, it' in pregress.

2~  ;; ' 2 '^r contairwe,t and Exhaust vent ^e isolate the secondary initiate the standby j

p. '

• 2 ^^ t - containment and start 9as treatment systesa Radiation Monitors.

Y: ;:--;;- t- the standby gas treat-ment system.

{'*:,

Q isolate the secondary 2 upscate wit: Isolate Upscate 2 500 mr/hr containment, start stand. the secondary con-

3. ' Reactor Bldg.

by gas treatment system, tainment and initlete

'." Exhatsst Vent .cfose primary contain-the standby gas N ' Radiation treatment systesa.

Monitors, ment and vent valves.

g' - Refer to specifications 19pscale or 2 down-Downscale' 1 20.013 er/hr 3.12.C. and 3.12.D. seales wiiI actu?te 4 Control Room the MCRECS in the

' Inta ke ..

Hi-51.0 ar/hr control room pres-G~ Radiation surization mode.

' Monitors t

3>

R CL O

a:

1 620 mr/hr o ,. , .

~

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RADI0 ACTIVE EFFLUENTS LIQUID HOLOUP TANKS LIMITING CONDITION FOR OPERATION P

3.5.1. 4 '*

• The contents within any outside temporary tank shall be limited to $10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY At all times. This specification does not apply to disposable liners used for shipment of radioactive waste.

ACTION a< With the contents within any outside temporary tank exceeding the abo limit, immediately suspend all additions of radioactive material to the tank and within 48 hoors reduce the tank contents within the limit and provide notification to the Commission pursuant to Specification 6.9.1.8. ,. -

u n_ ___a.. .. m.,. .e m. 4. , 4. , s . 4. m_ .. c__o__3_33_r,u_, mm.

r _ _ .

SURVEILLANCE REQUIREMENTS 4.15.1.4 The quantity of radioactive material contained in any outside temporary tank shall be determined to be within the above limit by analyzing a sample of each batch of radioactive material prior to its addition to the tank.

(

a. An outside temporary tank is not surrounded by liners, dikes, or walls that are capable of hWing the tank contents and not having tank overflows and dra." connected to the liquid radwaste treatment system.

i HATCH'-UNIT 1 3.15-8 Amendment No. 130

~..:.. . ...._J '

RADIDACJ 4E EFFLUENTS LL 1

/

, fIs s t s; stems y tment systems, the it did effluents from the .D L : E T E D tt units sharing thet s en . _

.g g 1 2 J eo., portioned among t

~ ' .y f

'.i LIOUID CE TREATMENT 2

TMr rpeci  % hh cSem[k k. Oppf per - .yfC dewie LetVugq.pl 4 I (' 'tN 1 quio racwaste eatment s/ stem ensures yj

>S

.e k ..., . ist will be available fo* se whenever liquid /

e tre treatment prior tt, elease to UNRESTRICTE g eff w -

d, rf requirements that the propriate portions of is

", i ARCA

'y-w us4: sed when specified pr ides assurance that th-11 be re . a- vf radioactive matert is in liquid effluents

.c

,p ke s.R$ c.rt . t. !O.36(a), Gener i nDesign This.specificati implements the requi ments of DELETED i i Appendix A E 10 CFR Part 50; and de gri objettive Criterion 60 .0 of Appendix t Section

$9 specifiec limits gov ning the use of js A to 10 CFR Part 50. T the liquid radwaste

/ appropriate portions uttable fraction of th eatment system guide set forth in *

/

were spec Mied as a .

Section II.A of Appendix I,10 CFR oart 5 , n.r liquid ef fluents 3/4.15.1.4 LIQUID HOLOUP TANKS 1 Restricthg the quantity of radioactive mb.teriai cor.',i'Wa in an the specified ts + ,a'ivides assurance that in

" the tanks' contents, the resu' ting the en [ g g

uncontrolled .* . be less than the limits of 10 CFR Part te,4-- 20.I30MbM(0 /

cone w rations u

• ,, Tch :: (ech.r & at the nearest surface water j j r,.

-Atmesa supp)y in an UNCESTRICTED AREA.

j i

3/4.15.2 GASEOUS EFFLUEms 114.15.2.1 DOSE RtTE 4

Yhil50tti{icab% nS{em$bNe GNM W,eNf((stitM / sher 99-01 1

, This specific . ton' is provice o en re Rat at ai! sees dose rate a the exclusion area bo dary from gaseous eff1sents of from all site units will be wt in the annual dose 11. limits m.

10 CFR P rt 20 for UNRESTRICTED REAS. The annual CFR dos Part

• v ne t doses associated with he concentrations of pendix B, Table II. T se limits provide rea nable DELE TED

~f'[#

20, as rance that radioactiv material discharged i gaseous fluents will not resul. in the exposure of a e exclusion individual in an A area UHRESTRICTED AREA, ei e: with h or outside ceeding the limits boundary, to annual verage :cncentrations Part 20 (10 CFR Dart

% i specifi(d it Appe ix B. Table II of 10 C /,

l 20.106(b)). For ndividuals who me/ atof imesthe be individual within the will e / '

j 1xclusion area oundary, the occupanc y increase in the suf ficiently ow to crmpensate for atmospberi diffusion Tactor abov that for the exclusic rea k 3.15-22 gendment No. &

CH-UNIT 1 s

g 3 MISTRAT1YE CONTR0l$ _

ANNUAL REPORTS (Continued 1 6.9.1.5. Reports required on an annual basis shall includes

a. A tabulation on en annual basis of the number of station, utility and other personnel, including contractors, receiving exposures greater than 100 arem/yr and their associated man rem exposure according to work and job functionsfe)e.g., reactor c:erations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based oh pocket dostmeter. TLD, or film badge measurements. Small exposces totalling less than 205 of the individual total dose need not be accounted for. In'the aggregate, at legst 80% of tne tots) whole body dose received from external sources shall be assigned to specific major work functions.

b. Documentation of all cha11 sages to safety / relief valves.

c. The results of specific activity analysis in which the primary u olant exceeded the limits of Specification 3.6.F.1,. The following information shall be included: (1) Reactor power

% history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first vample in which ae {

limit was exceeded; (2) Results of the last isotopic analysis for t.

y, radiciodine performed prior to excee6ing the. lir.it, r(sults of V analysis while limit was exceeded and results of one analysis af ter

' the radiotodine activity was reduced to Icss than li::it. Each result should include date and time of sampling and the radiciodine concentrations; (3) Cleanup systetu flow histo *y starting 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Sraph of the 1-131 concer.tration and one other radiciodine isotope, concentration in microcuries per gram as a function of time for the duration of the' specific activity above the steady-state level; ano

($) The time dura *. ton when the spe:ific activity of the primary coolant exceeded the radiciodine limit.

d. Any other unit unique reports required on an annual basis. _ l AFNUAL RADIOLOGICAL ENVIRONMENTAL $URVElllANCE REPORT hser b 6.9. 6 Routine ra fological enviro ntal surveills'nce reports covp' ring th radiological vironmental sur 111ance activi its related to t,Me plan

• ring the prev us calendar year shall be submi ed prior to May , of ea:h year. A sing report may fulf 1 this requir nt for both uni s.

6. 9 .1.1 e Annual Radiol cal Environment Surveillance R ort shall include ries, interp ations, and sty (istical evalr?t n of the resul of the radiologi; 1 environmental surveillance av ities for the repo ingperiod,inc1ging(asappropr te) a compariso ith the pr perationalstudips",operationaltotrols, previous vironmental J rveillance repartr, and an assess of any observe tapacts of the l operation op'the environment. The reports sha also include t

/f ant

.i

, / __

a. A single ubmitta) may'be mad > for a multiple-suit statier. The submittal should combine those sections coarmon to all units at the station.

8This tabulation supplemente the requirements of 40 of 10 CFR Paryt HATCH - UNIT 1 6-M knendment No. H.JpJ.JJB,49-

- - _ l

4 ggsTEATivt CONTROLS RttoRD RETENT'ON (Continued)

c. Records of radiatin exposure ff.r all individuals entering radiation 4

control areas.

4. Records of gaseous and 114uid radic, active material released to the environs.

e. Records of transient or ope .tional cycles for those unit componnas l

identified in Table 5.0.G-).

l f. Secords of reactor tests and experiments.

g. Reccrds of trainths and qualification for curm t members of the unit staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

1. Records of Quality Annance 1.ctivities required by the QA Manuel.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.5g.

k. Records of meetings of the PRB and the SRB.

1. Records for Environmental ')ualification which are covered under the provisions of paragraph 6.15.

a. Records of analyses required by the Radiological Environmental Monitoring Program.

n. Recerts tf the service lives of all safety-W1sted hydrad e and mechanical snuders inclu11ng the date at which the service life i

cocances and associated installation and maintenance records.

6.11. RA31 AT10N MOTECTION fRQGRAM AS S.f b Procedures for personnet radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure, b .12 . H16M RADIATION AREA 020.lb01(cn 6.12.1. In lieu of the

• control device

• or ' alarm signal' required by paragraph l

20.000(c)(4t of 10 CFR 20, each high rad'.ation ares in which the intensity of radiation is greater than 100 arem/hr but less thati 1000 mren/hr shall be barricaded and conspicuously posted as a high radiation area and entrance' thereto shall be centro 11ed by requiring issuanca t.f a Radiation Work Permit *.

" Any individual or group of individuals permitted

• Health Pnysics personnel, or personnel escorted by Health Physics personnel in ac:.ordance with approved emergency procedures, shall be exeset free the RWP l

issuance requiremer.t during the performance of their assigned radiation L

protection duties, provided they coaly witii approved radiation protection procedures for entry into high radiation orsas.

l 6-20 Amendment 4to.' $$ Seder et1f"

MATCH - UNIT 1 iCit;;;;, Tyy, TYJ',-HO~ j

-J y

1

. ADMIWisTRaTIVE CONTROLS' 6 '.16 . POST-ACCIDENT SAMPLING AND ANALYS11

-l

t. program shall be established, implemented, and maintained to ensure tne l

' capability to obtain and analyze samples of reactor coolant, radioactive i

. iodines ar J particulates in plant gaseous ef fluents. and containment atmosphere under accident conditions.-

! t

[

ft e program shall include the following:

4 (1)-Training of persocel.

• (2) Procedures for sampling and analysis, and-(3) Provisions for maintenance'of sampling and analysis equipment.

p 6.17. OFFSITE- DOSE CALCULATION MANUAL -_

= '

6.17.1. Licensee-initiated changes to the 00CM 5 [MS d T'I ._ ;

dI. St-submitte 'to the-Conni ion ichin thethe serai-annual change a) was n.adeeffluent effectre' e. a ir report fo the period i 4

This su ittal shall:c tain;_

the' 1.- ufficiently d ailed informatio to totally suppo rationale f the--charge witho bsnefit of addit na) or

' supplement information. 1 ornation submitted should 00CM pa*ges to be . hanged, with consist- _a package of tho ided with an app al and date box, each p e numbered and p i

toge er with appropria analyses or_evalu tons justifyir.g i

th change (s);

2. determination th the change will n' reduce the accur cy or reliability 9f dose calculations setpoint determinations; nd- .

found

3. 'Documentati that the-change h been reviewed a acceptabl y the PRB.

i Become'eff tive'upon review a acceptance by the RB,.

/ b.

Insert 7 i

l' ..

I v43 _ Amendment No. Tid, ,4M- -

HATCH - UNil i 4

4 a

.l

-t t , w , - , - e 5 e-e .- * =4 ~,=-+-,s

-e+r - - ., ev4--+.e

Insert 6

a. Be documented and records of reviews performed shall be retained as required by Technical Specification 6.10.2.o. This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and r

2) A determination that the change will maintain the level h 2) u ofradioact 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFP. Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,

b. Become effective after review and acceptance by the PRB aN the approval of the General Manager-Nuclear Plant,

c. Be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to tt e ODCH 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 t.as implemented.

Insert _l 6.18 f@lD&CT!vE EFFtVENTS CONTROLS, PROGRAM A program shall be established, implemented, and maintained conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE FUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remcdial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive _ liquid and gaseous monitoring instrumentation inchding surveillance tests and setpoint determinati3a..jgordance with the methodology in the 00CM,

2) Limitat t concentrations of radioactive material released in liquid effluents rnemm ,, - . . , _to_UNREyR4CTED

-,Thi<wes %t concentgtlons@^ AVAS gnfgngW^ddtd in

({cFR Net aogepteA 38 (to parag raphs 20.(o0!- LO.a30th TdM t iC ol p n L j

3) Honttoring, sampling, ano anaTysis of radioactive liquid ano gaseous effluents in accordance with 10 CFR 40406- and with the methodology and parameters in the ODCH, Ng

4) Limitations on the annual and quarterly doses cr dose commitment to '

a MEMER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and pro,iected dose contributions-from -

radioactive effluents for ti'e current calendar quarter and current calendar year in accordance with the pethodology and parameters in the ODCM ut least every 31 days,

6) Limitatiens on the operability and use of the liquid and gaseous effluent treatment systems tc ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses ir. a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commNent conforming to Appendix rAFcttt c 1 to h g @FR rart 50, ,c.- e < smoncenhtiondo s

7) LimitatT6'ns%nThedo;;r:t: re:uM(QW#Yadilfactise material released in gaseous effluents to areas beyond the SITE B0UNDARY conforming to %e-dees-esacci;ted with 10 CF9 P:et 20, Appendix B, 4eM II, Cohan I N C.m-me m

/,O time s he concen%h o n s rtded M 10 cv Ps fbt ?_O; Append.k 8 (to PNgraphs 201001 - 20.?Aod, Table 2, Column 1 3 y u,With cocce spond.s to a dose este 09

• rncern/gme total diecgg gose equival ent Ld ' #

E

= - _ _ _ _ _ _

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a Unit 2 .

Marked Pages i

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1.0 DEFINITIONS (Centinued) _ . _ - - . _

- r Y h v x means an ino6vidual in A' < ontrobrea of MEMBER 0ld 0F THE PUBLIC MN REST %.\C.TED AREA.- However, an indw(dual) is Act 4 N l M EMBER OF THE PusLtd chriq 'gnD pcWoc(

MEMBF@iQ OF THE PUBLIC shall includ; al' p:n::: t:_ :n :t

up;tien:lly :::::t:ted "t' th: pl:nt. t : :t:;;ry d:::

~

(n ujhich the n:t iac1ud: =pley::: -e ? t5: uti'ity, it; : ntn:t:n , ;r it:- '"dlVIdual receives ee nd:n , ^1;: :::1ud:d ~ = tht: ::t:;:ry cr: p:n:n: -;h: :nt;r u occ.upetionql -

th: :it: t: :: ret:: a ufp ::.t ;r :: ::h: d:lic:ri::. Thi; I

Mc;;ry d::: 'n:1;de p w:: :' -5: ;;; p:rtt::: :f th:' :tt: ~7:r dost* -

ree+ect!:n:1, :: up:tten:1, Or Oth r purp:::: Ut':::::ict:d I

_m . , _ .

C {" w s' SITE BOUNDARY-The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by Georgia Power-Company, as shown in ffgure 3.11-1.

7

gUNRESTRICTEDAREA. - [means an geeq,i Access to wh,ch. ,isntdht limited not controlled bgthe Ucensee. '

hr UNRESTRICTED AREA shell b; :ny ac : at ;r b y:nd tS: SITE COUNDA!"f t: ,45ich ::ee:: f r purpe:::- cf prettetten of ' .

i nd i . iiuc.1 : fn; cap::; n t: ndt:tter 2nd :d!:::tfV: m:t rt:10 -  !

i; net : nt =11:d by th '!:en:::. .: 'n:1ud:: :ny :rce.

within th; SITC SOUM0""' u :d f:r r :ident!:1 ;_:rt:n Or f -

long t:r

• ndu;trt:1, cern:r:f:1, 'nttitution:1, 2nd/cr-recrc tional purpo:::. _j

( _e >

?

O_0SE EQUIVALENT IODINE The DOSE EQUIVALENT I-131 shall be~that concentration-of I-131 (microcurie / gram)', -which alone _would- produce the same thyroid -

dose as the cuantity and isotopic mixture'of I-131, 1-132, 1-133, I-134, and I-135 actually present,- The-thyroid dose-conversion factors used for.this calculation shall be those listed in table III of TID-14844 or those-in NRC Regulatory-o juidn 1.109, Revision 1, October 1977. j PURGE - PURGING

- PURGE or PURGING is' the controlled procers of discharging airor gas from a confinement to mair)tain temp'e rature, pressure, hum.dity, concentration, or other operating condition-in such a manner that replacement air or gas is required to purify the confinement.

HA1CH - UNIT 2 1-8 Amendment.No. 48 1

. _ _ _ . , . _, . _ .. _ _ _ . - . , - . . . _ _ . . . _ . . . . - . ,.m. . . . _ . . _ , . . . . _ _ . . _ . . _ . . . . . _ . _ . _ . . . - . _ _ _ _ . . . _ . ..._

.3 TABLE 3.3.6.1-1 RA3IATION MDNITORING INSTRtJHENTATION

.i en .:

'x APPLICABLE .l

.e- ..;HINIMUM CHANNELS OPERATIONAL ALARM / TRIP MEASUREMENT Q SETPOINT RANGE AC110N n CONDITIONS OPERABLE - .

.lE'

-.m

- INSTRLMNTATION :l

\ --

• ' 1. .'Off-Gas 1 N, Post-Tre.tment 1, 2 - (a) 10-' tc,10' cps 50 j.~

Monitors . -- 2 (2011-K615 A.' B)'

- 2. Control Room 1.2.3.4,5 ' O.01 to'1'00 mr/h'r. . 51 -

' Intake Monitors.T 2' 1.mr/hr (1241-R6'.5 A; B) 4 Q

4 4

.w

.g. f  ;\

l TA "3. Value not to exceed.the equivalent of the stack release limit inoicated in

. C ,w . _ .- _1 ;' R h ::;l I; 2 :;t = 0.

5 PedifieAtton or .ts M 4 j .

1 L

9 $

~

.. y.  ;

4 13

.g'.

• 3 .

..I a- ... a . 4 n .:= .

co --

y

i. 2

.O

.)

i ~ w-

O: 'i

.@ 6

.j i

i' JE__---_.__u_m __A_.h_m_ _-_a ~ _ _ _ . .,_

n (1 g" .' 'd'I *l' 'M 'l4 IW .' 55i 7 "

s'4 6- -f gg % 6 ,Qp

RADIOACTIVE EFFLUENTS MQUIDHOLDUP_, TANKS LIMITING CONDITION FOR-OPERATION ,

[ 3.11.1.4b The contents within any outside temporary tank shall be limited to s10 curies, excluding tritium-and dissolved or entrained noble gases.

APPLICABILITY L At all times. This specification does not apply to disposable liners used for shipment of radioactive waste.

ACTION i a. With the contents within any outside temporary tank excaeding the above limit, immediately r.uspend all additions of rsdioactive material to the tank and 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 within the limit and provide notification to the Commission-pursuant to Specification 6.9.1.8.

gm. v u 3 C,,-... c. y-e 2, . C. . . . . . e. . n. 4.1. , . , _, _. _ SD. _ _

j

%_v =* - e _s e URVETLLANCE REQUIREMENTS 4.1~. 1.4 The quantity of radioactive material contained in any outside tempo:ary tank shall be determined tn be within the above limit by analyzing a sampia of each 5atch of radioactive material prior to its addition to the tank.

O

a. An outs Fe umporary tank is not surrounded by liners, r'ikes, or walls that are capable of hoking the tank contents a and not having tank overflows and drains connected to the liquid radwaste treatment system.

HATCH - UNIT 2 3/4 11-8 Amendment No. 48

l RADIOACTIVE SFFLUENTS BASES reatment systems, the quid ef fluents from t shared systems  !

are proportioned among the units sharing that system. DELETED 3/4.11.1.3 LIQUID WASTE TREATMENT Spe'ci/, u;Nes_1'gsntfiXed -b.8e DI)(M w Nf?_fxneric is$es M o l

' _h is T[he0PERABILIT

~

cf the 1fquid raowasta' trestrent sysfem ensu /

that this sy em will be available 6r use whenever liquid effluents quire trestFent prior o ielease to UNRESTRIC 0 e requirements that t appropriate portions this AREAS. e system e used when specified rovides assurance that rele es of radioactive mat ials in liquid effluentrement, will beof.

ke ALARA. This specific ion implements the re . DE LE'TE D CFR Part 50.36(i), Ge ral Design Criterion 6 of Appendix A to 10 CFR Part 50; and esign objective Sectio 11.0 of Appendix I to 10 CFR Part 50. he specified limits g erning the use of appropriate portio of the liquid radwas treatment system

' were specifitd a a suitable fraction of e guide. set forth in Section IE A of dopendix 1. 10 CFR par O_ for liovid effluent /

3/4.11.1.4 LIQUID HOLOUP TANKS Restricting the quantity of cadioc tive material contained in CO

- the specified tanks provides assurance that in the event of an uncont.olled release of the tanks' contents, the resulting 20 13D2.(O@MO concentrations would be less than the limits of 10 CFR Part-eof y Appe-dix ? , Tel; !! ':d =- 2) at the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE Th it SDecik hr,4% hhr[ened -b -Ne 0/){M n4 /JK hMute bh84-0i <

This spec 4f cation is p'rovided to ensure that at all times the dose rat at the exclusion area oundary from gastous ef uents from al onsite units will b6 trin the annual dose 1 its of 10 CF Part 20 for UNRESTRIC WS . The annual d o limit s are he doses associated uit tne concentrations o 10 CFR ? art 2 , Appendix B, Table 11. These limits provide r astnable ssurance that radioact e material discharged n gaseous. . DELETED .

effluents will not rey it in the exposure of n individual in an / l UNRESTRICTED AREA, (ther within or outsid he exclusion area /

/

boundary, to annu average concentration ' exceeding the limits /

specified in Ap ndix B, Tablo II of 10 FR Part 20 (10 CFR Par 20.106(b)). F r individuals who may times be'within the fi exclusion a a boundary, the occupa y of the individual wi be sufficien low to compensate fo .any increase in the atmosphey c diffusion f, actor ab e that for the exclusipff area 8 3/4 11-2 Amandment No. HATCH - UNIT 2

ADMEN 1STRATIVR CONTR0t.S ANNUAL REPORTS (Continued) 6.9.1.5 Repmts required on an annual basis shall includs:

a. A tabulation on an annual basis of the number of station, utility and other personnel, including contractort, receiving exposures greater than 100 mrem /yr and their issociated man rem exposure ac:ording to work and job functions /8) e.g., reactor operations and surveillance inservice, inspection, routine maintenance, special maintenance (describe maintenance), waste processing, an:l refueling. The dose :.ssignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total Jose need not be accounted for. In the aggregate, et least 80% of tn total whole body dose received from external sources shall be assigned to specific major work functions.

b. Documentation of all chaunges to safety / relief valves.

1

c. The results of specific activity analysis in which theThe primary followirg J coolant exceeded the limits of Specifica*'on 3.4.5. '

information shall be included: (1) Reac ar power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiotodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis ther the radiaiodine was reduced to itss than the-limit. Each ref. ult should include date and time ov' sampling and the radiciodine concentrations; (3) Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in whir.h the limit was exceeded; (4) Graph of the'I-131 concentration and one other radiciodir.e isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state hvel; and (5) The time curation when the specific activity of the primary coolant exceeded the radiciodine  ;

limit.

Any other unit unique reports required on an annual basis. l d.

d ANNUAL RADIOLOGICAL ENVIRONMENTAL _SURVElluNCE REP g3 6.9.1.6 Routine rauip: onmental surveillancogical activities environmental related to he planturveillance reports c (e the radiological eti submitted prior to M 1 of each during the previot calendar year shall year. A single port may fulfill this requirtment for both its.

6.9.1.7 The nnual Radiological Eny ronmental Surveillanc Report shall tion of the includesur. aries,interpretattery,andstatisticT1 eval n

E A single submittal may be made for a multiple-unit station. The Sum ttal !,hould combine those sections common to all units at the station.

8Td > tabulation supplements the requirements of -fk40? mf 10 CFR Part 20.

6-14 Amendment No. 3B, ($, HATCH - UNIT 2 m

4 eo.nos O

ADMINXSTRATIVE CONTROLS- .-

RECORD RETENTION (Continued)

c. Records of radiation exposure for all individuals entering radiation contrel areas,

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those unit components identified in Tabir 5./.1-1.

f. Records of reactor tests and exper iments,

g. Records of training and qualification for current members of the unit staff.

h. Records of in-service inspections performed pursuant to these

. Technical Specifications, i.

Records of Quality Assurance activities required by the QA Manual.

j. Records of rev1ews performed for changes made to procedures or equipment or reviews of tests and expceiments pursuant to 10 CFR 50.59.

k. .

Records of meetings of the PRB and the srb.

1. Records for Environmental Qualification which are cuvered under the provisions of paragraph 6.15.

m.

Records of analyses required by-the Radiological Env'ronmental Monitoring Program.

n. Re: ords of the service lives of all safety-relatea hydraulic and mechanical snubbers, including the date at which the service life commences and associated installation and maintenance records.

1

0. <  ; [ f),5 g y f' [__

6.11 RADIAi10N_PPOTECT10N PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR P3 t' ?O and shall be appre-ed, maintained and adhered to for all operations involving personnel radiation exposure.

' 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20 each high radiation area1000 in which the intensity of mrem /hr shall be 4 ,, -.,h,,, radiation is greater than 100 mrem /hr but' iess than g ) barricaded and conspicuously posted as a high radiation area and er. trance v thereto shall be controlied by requiring issuance of a Radiation Work Permit *.

Any individual or group of individuals permitted

• Health Physics personnel, or personnel escorted by-Health Physics personnel in accorriance with approved emergency peccedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation. protection proceduret for entry into high radiation areas.

6-18' .0cerr' Atc. -10/G/50.

HATCH - UNIT 2 Amendment No. /8.44-i

m 4 n.m .e4de4=S- p n a,e oa a 4

.w 4 MW --a.,.41o.a.2.' y 4 g 4 , y.e h

4 ADMINISTRATIVE CONTROLS-i 6.16 POST-ACCIDENT SAMPLING AND ANALYSIS .

I I A program.shall be established, irplemented, and maintained to ensure the capability to obtain-and analyze samples-of reactor coolent,. radioactive

< iodines and particulates in' plant gaseous effluents, and containment

, atmosphere under accident conditions.

l The program sha11 include the following:

(1) ' Training of personnel, s

t (2) Procedures for sampling and analysis, and (3). Pr'ovisions fo'r raintenance of .samp_ ling and analysis equipment.

6.17 0FFSITE 'OCSE CALCULATION MANUAL 5.17.1 Licer te-initiatcd changes.to the 00CM shallp _nSer'N b l

i a. e subeitted to the.C ~ ission in-the semi-a ual effluent release report for 1.he perio in_which the change ( was made effective.

This submittal sha) contain

Sufficienti detailed tnformation o totally suport' th

~

1. r rationale or the_ charge withou enefit of additional l-supplem tal information. 'm d consi of a package of thos0CM 4rmation pages to submitted be cha ed,sho with -

eac page. numbered and pro ded with an approval d date box, /-

-Justifying / - -

to ther with appropriat analyses or evaluatio e change (s);

l 2 A determination tha the change will not-r ucelthC accuracy or reliability of ose calculations or s point F determinatior.n d-j' 3. Documentatio hat the change _has b n reviewed and found -

the PRB.  :

acceptt.ble 1

b. Become effe tve upon review and a eptance by the PRB. /

i 3

hsut7 }

l 6-22 Amendment No. #$,.40-HATCH - UNIT 2 e

1 5 I

. . . . . . . . . . _ . . ~.,- ..-. .. . _ , . _ , ,

Insert 6

a. Be documented and records of reviews performed shall be retained _as required by Technical Specification 6.10.2.o. This documentation shall contain:

L

• 1)

Sufficient information to support the change together_ with the

- appropriate analyses or evaluations justifying the change (s) and m

A determination that the change-will maintain the -level of [20.130ili 2) radioactive effluent control required by 10 CFR10.100,' '-\s - d 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part- 50 and not adverstlyLimpact the accuracy-or reliability of effluent, dose, or setpoint calculations. _>

b. Become effective after review and acceptance-by the PRB and the approval

! of the General Manager-Nuclear Plant.

c. -Be submitted to the Commission in the form of a complete, legible copy of the entire 0DCM as. a part_ of or concurrent with the Semiannual Radioactive Effluent Release Report for the period _of-the-report'in which any change:tc i

the 00tM 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 i

implemented.

l i

k i

Insert 7 6.18 BAD 10 ACTIVE EFFLUENTS CONTROLS PROGRAM A program shall be established, innlemented, and maintained conforming with 10 CFR 50.3ba for the control of radioactive effluents and for maintaining the doses to HEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the OOCH, (2) shall be implemented by operating procedures, and (3) shall: include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1)

Limitations on the operability of rcdioactive liquid and gaseous monitoring instr':santation including surveillance tests and setpoint determinatiMyordance with the methodology in the 00CM, 6E a time _s,,,

2) Limitations %5n'ine concentrations of radioactive material releasedL geonforming g 0 3

MN,ID. 5h.. gIRIQEDy/d

/ myr.m . . -

' tocmoi n epbodix e (to eorosroehs ec. eu -

. i mes theTable ao6> concentcqtions a colmn a statec(j(n

3) ldinit'oring, Tamp 1Tng-'~a'nTTiaTyITs of' 431oittT~veWd,Wg us s

effluents in accordance with 10 CFR &M6 and with the methodology (

and parameters in the 00CH, MQ@J Gv Limitations on the annua'. anc quarterly doses or dote commitment to 4) a HEMBER OF THE PUBLIC from r.dioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix ! to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quitter 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 tr9atment systems to ensure that the appropriate portions '

of these systems are used to reduce relesses of radioactivity when

/ the projected doses in a 31-dsy period would exceed 2 percent of the guidelines for the annual dose or dose commitmor.t conforming .to c

emm ccoue.ntrations g;~(p Appendix 1 to @10 CFR Part 50, re:alting br'i3Toa'cT6e@

7) Limitations'Koii 1 e de:: r:t:

released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the dests-estccieted dth 10 CFR Part 20 Apperdir S, Tet,12 I I , C ol umr. ' , eg

/0 hs %e concentra%ns st@4 M i

IO C.FR Fcyt 20, AppendiK BC porgtophs

20. loo t - 20 2400), Mk 2, Colmn i. ,

ushich c orcesponds t o q don cate ort 500 mcun/ gear totai ewegm e

{epalent, j uvv 1

.- _ _ _ _ _