ML20044D080

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Proposed TS Re Administrative Controls,Reflecting New 10CFR50.36a,incorporating Requirements for Annual Radioactive Effluent Release Rept in Lieu of Current Semiannual Rept
ML20044D080
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/03/1993
From:
GEORGIA POWER CO.
To:
Shared Package
ML20044D078 List:
References
NUDOCS 9305170199
Download: ML20044D080 (31)
v • d • e


Text

. . .

Enclosure 3  !

i Edwin I. Hatch Nuclear Plant Request to Revise Technical Specification 7

Semiannual Radioactive EfIluent Release Report Page Change Instructions  !

Unit 1 4 Remove Page Insen Page  !

l 1.0-8*

3.15-8 3.15-8 * *  ;

3.15-18 3.15-18**

6-15a*

6-23*

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Supersedes proposed changed technical specification page submitted by Georgia l Power Company letter dated September 21,1992.

  • New proposed changed technical specification page.

9305170199 930503 [

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1.0 DEFINITIONS UU. SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

VV. PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM (PCP) shall be implemented by procedures which contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

WW. SOLIDIFICATION This definition transferred to the PCP per NRC Generic Letter 89-01.

XX. OFFSITE DOSE CALCULATION MANUAL The 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the radioactive effluent controls required by Technical Specification 6.18 and Radiological Environmental Monitoring Program required by Technical Specification 6.19 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance Report required by Technical Specification 6.9.1.6 and the Annual Radioactive Effluent Release Report required by Technical Specification 6.9.1.8.

YY. GASE0US RADWASTE TREATMENT SYSTEM This definition transferred to the ODCM per NRC Generic Letter 89-01.

HATCH - UNIT 1 1.0-8 techsp\h\1-0U1062. pro \l10

RADIOACTIVE EFFLUENTS j LIOUID HOLOUP TANKS l LIMITING CONDITION FOR OPERATION l i

3.15.1.4(*) The contents within any outside temporary tank l !

shall be limited to 510 curies, excluding tritium and i dissolved or entrained noble gases.  ;

APPLICABItITY j 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 above limit, immediately suspend all j 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 l Specification 6.9.1.8.  ;

i SURVEILLANCE REQUIREMENTS t

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. l t

l

a. An outside temporary tank is not surrounded by liners, j dikes, or walls that-are capable of holding the tank contents ,

and not having tank overflows and drains connected to the liquid ,

radwaste treatment system.  ;

i HATCH - UNIT 1 3.15-8 techsp\h\3-15089. pro \110 l

RADI0 ACTIVE EFFLUENTS .

EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.15.2.6 The concentration of hydrogen downstream of the  :

recombiners in the main condenser offgas treatment system shall  ;

be limited to s 4 percent by volume.

i APPLICABILITY At all times.  ;

ACTION  !

a. With the concentration of hydrogen downstream of the i recombiners in the main condenser offgas treatment system exceeding the limit, restore the concentration -

within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. ,

I

b. When the ACTION statement or other requirements of this l LC0 cannot be met, steps need not be taken to change the Operational Mode of the Unit. Entry into an Operati:nal 1' Mode or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are i satisfied.  ;

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SURVEILLANCE REQUIREMENTS _

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- 4.15.2.6 The concentration of hydrogen downstream of the l

, recombiners in the main condenser offgas treatment system shall i be determined to be within the above limits by monitoring the l waste gases in the main condenser offgas treatment system with .,

the (hydrogen) monitors required OPERABLE by table 3.14.2-1, 1 Specification 3.14.2.

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i HATCH - UNIT 1 3.15-18 techsp\h\3-15089. pro \110

. t ADMINISTRATIVE CONTROLS  ;

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ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities .

of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

i i

i

a. A single submittal may be made for a multiple-unit station. The .

submittal should combine those sections that are common to all units at the station; however, the submittal shall specify the releases of radioactive material from each unit.

-t HATCH - UNIT 1 6-15a techp\h\6-001062. pro \110 i

l ADMINISTRATIVE CONTROLS  ;

6.16 POST ACCIDENT SAMPLING AND ANALYSIS A program shall be established, implemented, and maintained to ensure the  !

capaDility to obtain and analyze samples of reactor coolant, radioactive  !

iodines and particulates in plant gaseous effluents, and containment atmosphere under accident conditions. -

t The program shall include the following: f

.h (1) Training of personnel, ,

(2) Procedures for sampling and analysis, and t

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

6.17 0FFSITE 00SE CALCULATION MANUAL 6.17.1 Licensee-initiated changes to the ODCM shall: l 3

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 l

1) Sufficient information to support 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 1 to 10 CFR Part 50 and-
  • not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b. Eecome effective af ter 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 concurrent with, the Annual Radioactive Effluent Release Report for the period of the .

I 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.

6.18 RAD 10 ACTIVE EFFtVENTS CONTROL PROGRAM j 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 j contained in the ODCri, (2) shall be implemented by operating procedures,  ;

and (3) shall include remedial actions to be taken whenever the program i limits are exceeded. The program shall include the following elements:

1) Limitations on the OPERABILITY of radioactive liquid and gaseous  ;

monitoring instrumentation including surveillance-tests and setpoint determination in accordance with the methodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in '

liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B Table 11. Column 2 ,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous  !

effluents in accordance with 10 CFR 20.106 and with the methodology i

  • and parameters in the ODCM, l t

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s INDEX ADMINISTRATIVE CONTROLS  ;

SECTION P_A AGE SAFETY REVIEW BOARD (Continued) 1 Audits 6-10 Authority 6-11  ;

Records 6-11 6.6 REPORTABLE EVENT ACTION 6-11 6.7 SAFETY LIMIT VIOLATION 6-11 6.8 PROCEDURES 6-12 6.9 REPORTING REOUIREMENTS  :

ROUTINE REPORTS 6-13 STARTUP REPORT 6-13

  • ANNUAL REPORTS 6-13 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 6-14 ,

ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT 6-14a l MONTHLY OPERATING REPORT 6-14d CORE OPERATING LIMITS REPORT 6-14d j

SPECIAL REPORTS 6-17 6.10 RECORD RETENTION 6-17 6.11 RADIATION PROTECTION PROGRAM 6-18 6.12 HIGH RADIATION AREA 6-18  !

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-j HATCH - UNIT 2 XVI techsp\h\lNDTOC62. pro \l06 l

1.0 DEFINITIONS (Continued)

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

PROCESS CONTROL PROGRAM i The PROCESS CONTROL PROGRAM (PCP) shall be implemented by procedures which contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

50llDIFICAT10N This definition transferred to the PCP per NRC Generic letter 89-01.

OFFSITE DOSE CALCULATION MANUAL The 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the radioactive effluent controls required by Technical Specification 6.18 and Radiological Environmental Monitoring Program required by Technical Specification 6.19 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance Report required by Technical Specification 6.9.1.6 and the Innual Radioactive Effluent Release Report required by Technical Specification 6.9.1.8.

GASEOUS RADWASTE TREATMENT SYSTEM This definition transferred to the ODCM per NRC Generic Letter 89-01. l 1

q HATCH - UNIT 2 1-7 techsp\h\1-0U2062. pro \001

RADI0 ACTIVE EFFLUENTS L10VID HOLDUP TANKS l LIMITING CONDITION FOR OPERATION ,

3.11.1. 4 ") The contents within any outside temporary tank l )

shall be limited to s 10 curies, excluding tritium and dissolved or entrained noble gases.

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

ACTION

a. With the contents within any outside temporary tank i 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 i limit and provide notification to the Commission pursuant to Specification 6.9.1.8.

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t SURVEILLANCE RE0VIREMENTS l 4.11.1.4 The quantity of radioactive material contained I 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. 1 l

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a. An outside temporary tank is not surrounded by liners, 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 t

HATCH - UNIT 2 3/4 11-8 techsp\h\3_4-1189. pro \48

f RADI0 ACTIVE EFFLUENTS ,

EXPLOSIVE GAS MIXTURE  ;

LIMITING CONDITION FOR OPERATION l i

3.11.2.6 The concentration of hydrogen downstream of the i recombiners in the main condenser offgas treatment system shall 1 be limited to s 4 percent by volume.  !

APPLICABILITY -i At all times. ,

ACTION l

a. With the concentration of hydrogen downstream of the  !

recombiners in the main condenser offgas treatment  :

system exceeding the limit, restore the concentration within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. The provisions of Specifications 3.0.3 and 3.0.4 '

3 are not applicable.

SURVEILLANCE RE0VIREMENTS  !

4.11.2.6 The concentration of hydrogen downstream of the .

recombiners in the main condenser offgas treatment system shall be determined to be within the above limits by monitoring the waste gases in the main condenser offgas treatment system with .

the (hydrogen) monitors required OPERABLE by table 3.3.6.10-1, l Specification 3.3.6.10. 1 t

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ADMINISTRATIVE CONTROLS i l

i ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (*)

6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents  ;

and solid weste released from the unit. The material provided shall '

be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of ,

Appendix I to 10 CFR Part 50.

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a. A single submittal may be made for a multiple-unit station. The submittal should combine those sections that are common to all units at the i station; however, the submittal shall specify the. releases of radioactive material from each unit. ,

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HATCH -_ UNIT 2 6-14a - techsp\h\6-002062. pro \B6- l 1

ADMINISTRATIVE CONTROLS 6.16 POST-ACCIDENT SAMPLING AND ANALYSIS A program shall be established, implemented, 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.

The program shall include the following:

(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 ODCM 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 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 CFP 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. 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 ODCM as a part of, or concurrent with, the ,

Annual 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.

6.18 RADI0 ACTIVE EFFLUENTS 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 1HE PUBLIC from radioactive ,

effluents as low as reasonably achievable. The )rogram (1) shall be contained in the ODCH, (2) shall be implemented )y olerating procedures,  :

and (3) shall include remedial actions to be taken wienever the program '

limits are exceeded. The program shall include the following elements:

1) Limitations on the OPERABILITY 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\6-002062. pro \48

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Enclosure 4  !

f Edwin I. Hatch Nuclear Plant l Request to Revise Technical Specifications  ;

Semiannual Radioactive Effluent Release Report  !

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1.0 DEFINITIONS UU. SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

W. FROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM (PCP) shall be implemented by procedures which contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

W. SOLIDIFICATION This definition transferred to the PCP per NRC Generic Letter 89-01. ,

XX. OFFSITE DOSE CALCULATION MANUAL 4

The OFFSITE DOSE CALCULATION KANUAL (ODCM) shall contain i the methodology and parameters used in the calculation of effsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the radioactive effluent controls required by Technical Specification 6.18 and Radiological Environmental Monitoring Program required by Technical Specification 6.19 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance Report required by Technical Specification 6.9.1.6 and the Seaier, m i-Radioactive Effluent Release Report required by Technical-Specification 6.9.1.8.

Annual YY. GASEOUS RADWASTE TREATMENT SYSTEM This definition transferred to the ODCM per NRC Generic Letter 89-01.

RATCH - UNIT 1 1.0-8 techsp\h\92-11U1A.II0

RADI0 ACTIVE EFFLUENTS q LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION A

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3.15I. f he contents within any outside temporary tank shall be .ited to s10 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 wsste.

ACTION  :

a. With the contents within any outside temporary tank l exceeding the above limit, immediately suspend all >

additions o *adioactive 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 pirsuant to Specification 6.9.1.8 u -t_ ___.,_,___ _, e___,,,_. ,__ e n , 43rus . _ _ . __.

ppl'::bl .

SURVEILLANCI REOUIREMENTS 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 i material prior to its addition to the tank.

l

a. An outside temporary tank is not surrounded by liners, dikes, or walls that are capable of holding the tank contents and not having tank overflows and drains connected to the liquid radwaste _ satment system.

HATCH-UNIT ' 3.15-8 Amendment No. 110

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l RADI0 ACTIVE EFFLUENTS r EXPLOSIVE GAS MIXTURE  !

LIMITING CONDITION FOR OPERATION L i

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3.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to 5 4 percent by volume. t I

APPLICABILITY  :

At all times.

t ACTION

a. With the concentretion of Sydrogen downstream of the ,

recombiners in the main condenser offgas treatment system exceeding the limit, restore the concentration -

within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.  !

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b. The pr;;i; ions ;f Spc;ifi;; tion-0.0.1.12(b) ;re 7;; ,

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,{ When the ACTION statement or other requirements of this LCD cannot be met, steps need not be taken to change the Operational Mode of the Unit. Entry into an Operational Mode or other specified condition may be made if, as e minimum, the requirements of the ACTION statement are {

satisfied.

SURVEILLANCE REOUIREMENTS 4.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall '

be determined to be within the above limits by monitoring the waste gases in the main condenser offgas treatment system with 3.14.2-1, .

tt + ('aydrogen) moniters required OPERABLE sv '

Spyct fication 3.14.2.

l.

h 3.15-18 Amendment No. 110 f HATCH-UNIT 1

ADMINISTRATIVE CONTROLS ,

Annua \

I ANNARL S IA""JAL RADIOACTIVE _/ EFFLUENT codendar year RELEASE REP l

6.9.1.8 The Semienmrlei-Radioactive Effluent Release Reporticovering the operation of the unit during the previous 0 months cf speration-shall be submitted within 00 d&ys efter January 1 and July A1 of each year. The report shall include a sumary of the quantities of radio tive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in he ODCM and PCP and (2) in confomance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

before May1

4. A single submittal may be made for a multiple-unit station. The submittal should combine those sections that are common to all units at the station; however, the submittal shall specify the releases of radioactive material from each unit.

HATCH - UNIT 1 6-1:ia 14: ;sp\h\92-IIUIE.110

ADMINISTRATIVE CONTROLS 6.16 POST-ACCIDENT SAMPLING AND AMALYSIS A progras shall be estabitshed, implemented, and maintained to ensure the capability to obtain and analyze samples of reactor coolant, radioactive iodines and particulates in plant gaseous affluents, and containment atmosphere under accident conditions.

The program shall include the following:

(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 ODCM 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 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 ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of affluent, dose, or setpoint calculations.
b. Secome effective af ter review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.
c. Be subattted to the Commission in the form of a complate, legible A ) copy

%;ir. ofn1the entire 00CM Radioactive asRelease Effluent a part of, or concurrent Report for the periodwith, the of the nunuG.1I report in which any change to the ODCM was sede. 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.

6.18 RAD 10 ACTIVE EFFtUENTS CONTROL pP00PJUt A program shall be estabitshed, implemented, and saintained conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radicactive effluents as low as reasonably achievable. The program (1) shall be contair.ed in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the OPERABILITY of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B. Table II, Column 2,
3) Monitoring, sampling, and analysis of radio:ctive liquid and gaseous ef fluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, HATCH - UNIT 1 6-23 techsp\h\S2-11UIE.110

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'INDEX i ADMINISTRATIVE CONTROLS SECTION PAGE 1

f

-SAFETY REVIEW BOARD'(Continued) j i

Audits 6-10 ,

Authority 6 l Records 6-11 l 6.6 REPORTABLE EVENT ACTION 6-11 ~!

6.7 SAFETY LIMIT VIOLATION 6-11 1 6.8 PROCEDURES 6-12 6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6-13 .

r STARTUP REPORT 6-13 i ANNUAL REPORTS 6-13 .j l

ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 6-14 ,

i AANN

';CL 4AL m.L 'L'AL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6-14a i MONTHLY OPERATING REPORT 6-14d .

CORE OPERATING LIMITS REPORT 6-14d .r I

i

-i SPECIAL REPORTS i 6-17  :

i' 6.10 RECORD RETENTION 6-17 j 6.11 RADIATION PROTECTION PROGRAM 6-18  ;

i 6.12- HIGH RADIATION AREA 6-18' c

f t

HATCH-UNIT'2 XVI Amendment No. ell', 86,106 [

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

e; *;...

I i

l 1.0 DEFINITIONS (Continued)

I l

SOURCE CHECK I 1;

A SOURCE CHECK shall be the qualitative assessment of channel 1

response when the channel sensor is exposed to a source of  !

increased radioactivity. a l

PROCESS CONTROL PJfDE&M j The PROCESS CONTROL PROGRAM (PCP)'shall be implemented by procedures which contain the current formulas, sampling, analyses, tests, and I i

deteminations to be made to ensure that processing and packaging  !

of solid radioactive wastes based on demonstrated processing of-actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61,-and 71, 4 State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste, j g

i SOLIDIFICATION This definition transferred to the PCP per NRC Generic Letter 8g-01. j i

0FFSITE DOSE CALCULATION MANUAL The DFFSITE DOSE CALCULATION MANUAL-(00CM) shall contain the methodology I t

and parameters used in the calculation of offsite doses resulting from.  :

radioactive gascous and liquid effluents, in the calculation of gasecas j and liquid effluent monitoring alars/ trip setpoints, and in the conduct of the Radiological Environmental flonitoring Program. The 00CN shall also  !

i contain (1) the radioactive affluent controls required by Technical-Specification 6.18 and Radiological Environmental Monitoring Program required by Technical Specification 6.lg and (t) descriptions of the

-information that should be included in the Annual Radiological Environmental Annual-+S:i==1 Surveillance RadioactiveReport required Effluent Release by required Report Technical Specification 6.g.I by lechnical Specification 6.9.1.8. ,

CASE 005 RADWASTE TREATMENT SYSTEM This definition transferred'to the ODCM per.NRC Generic Letter 8g-01. lL q

a i

e i 1-7 'techsp\h\gt-11U1A.001: l HATCet - uni? 2.

1

RADI0 ACTIVE EFFLUENTS .

LIQUID HOLDUP TANKS ,

-a .

LIMITING CONDITION FOR OPERATION t M ,

o he contents within any outside temporary tank  ;

3.II.1 4'45 mited to s10 curies, excluding tritium and shall dissolved or entrained noble gases.

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

ACTION

a. With the contents within any outside 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 l limit and provide notification to the Commission pursuant to Specification 6.9.1.8. __

b.

((,5,,gr;yigicasofSpecification0.0.1.13(b)areact SURVEILLANCE REQUIREMENTS 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.

I ;

a. An outside temporary tank is not surrounded by liners, i dikes, or walls that are capable of holding the tank contents '

and not having tank overflows and drains connected to the '

liquid radwaste treatment system.  !

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

e

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION i

i The concentration of hydrogen downstream of the 3_.1.1. 2. 6 recombiners in the main condenser offgas treatment system shall

~

be limited to s 4 percent by volume. ,

APPLICABILITY At all times.

ACTION

a. With the concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system exceeding the limit, restore the concentration l within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. ~~~ ,,,

ha nrovisions of Specifications 3

b. .3/3.0.4f+

C. .1Mb not applicable. f SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be determined to be within the ab've o limits by monitoring the  ;

waste gases'in the main condenser offgas treatment _ system with  ;

the (hydrogen) monitors required OPERABLE by table 3.3.6.10-1, Specification 3.3.6.10.

3/4 11-18 Amendment No. 48 HATCH - UNIT 2 ,

__._.____.________._________._._._.__.__._____.____..____.__.__m._

l l

ADMINISTRATIVE CONTROLS l 1

l l

Annual ANHilAL /

fi""*"JAL RADIOACTIVE / EFFLUENT RELEASE REPORTN calendar year i l 6.9.1.8 The Ser.iannual Radioactive Effluent Release Report covering '

the operation of the unit during the previous C s,cnths of p:r: tion shall The year. be submitted)within 00a days report / hall include sumaryafter Jamtery of the 1 indofJuly i- of each quantities radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives out1 ned in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a d Section IV.B.1 of Appendix I to 10 CFR Part 50.

/

before May 1

a. A single submittal may be made for a multiple-unit station. The submittal should combine those sections that are common to all units at the station; however, the submittal shall specify the releases of radioactive material from each unit.

HATCH - UNIT 2 6-14a techsp\h\92-11U2F.86

,.r. j ADMINISTRATIVE CONTROLS i

1

.I 6.16 POST-ACCIDENT SAMPLING AND ??2 LYSIS A program shall be established, implemented, and maintained to ensure the capabilit to obtain and ana iodines a particulates in ze radioactive  !

ant samples of~ reactor gaseous effluents, andcoolant,tainment con atmosphere under accident conditions. j The program shall include the following:

(1) Training of personnel, f

(2) Procedures for sampling and analysis, and I (3) Provisions for maintenance of sampling and analysis equipment. -l 6.17 0FFSITE DDSE CALCULATION MANUAL 6.17.1 Licensee-initiated changes to the ODCM shall: j

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

r

2) A determination that the change will maintain the level of  ;

radioactive affluent control re 40 CFR Part 190, 10 CFR 50.36a, quired by 10 CFR 20.106andAppendil!

Part 50 and not adversel spect the accurac of effluent, dose, or se p int calculations.y or reliability  :

b. Become effective after review and acceptance ~by the PRS and the  :

approval of the General Manager-Nuclear Plant.

i

c. Be submitted to the Commission in the form of a complete ible  !

copy of the entire ODCM as a part ef,;or concurrent with., e Annu.d ) '

-.===1 Radioactive Effluent Release Report for the eriod of the report in which any change to the ODCM was made. Each hange shall' i be identified by markings in the margin of the affected pages. -!

clearly indica 4eindicating (themonth the date e.g., area /ofyear) thethe page thatwas change was impchange emented., and shall  !

(

6.18 RADIDACTIVE EFFLUENTS CONTROL PROGpa.M '  !

A program shall be established i 1

with 10 CFR 50.36a for the confrol of radioactive affluents and forimplemented, and !

maintaining the doses to MEMBERS OF THE PUBLIC from radioactive i effluents as low as reasonably achievable. The regram C ) shall be  :

shall be implemented and 3 contained in the CDCM, (2) dial actions tooperat ng erocedures be taken whenever the progi  !

limi s)are exceeded.shall include The program shallreme include the following elements:  ;

1) Limitations on the OPERABILITY of radioactive liquid and gaseous monitorin instrumentation including surveillance tests and setpoint determina ion in accordance with the methodology in the ODCM, HATCH - UNIT 2 6-22. techsp\h\g2-IlU2F.48 J'

. -,

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