Text

Amends 190 & 129 to Licenses DPR-57 & NPF-5,respectively, Relocating Procedural Details Contained in Radiological Effluent Ts,Incorporating New Part 20 & Revising Frequency of Reporting Radiological Effluent Releases
	ML20059E683
Person / Time
Site:	Hatch
Issue date:	10/21/1993
From:	Hermann R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20059E675	List: ML20059E672; ML20059E683; ML20059E696;
References
	NUDOCS 9311030301
	Download: ML20059E683 (116)
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/s. A 0 ) ( E UN!TED STATES 5

- i NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 k . . . . . ,/

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET N0. 50-321 .

EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No. DPR-57

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The applications for amendments to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated September 21, 1992; October 14, 1992, as supplemented January 15, March 26, and July 30, i 1993; and May 3, 1993, as supplemented October 5, 1993, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set i forth in 10 CER Chapter I- !

B. The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by j this amendment can be conducted without endangering the health and I safety of the public, and (ii) that such activities will be '

conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l E. The issuance of this amendment is in accordance with 10 CFR Part 51 l of the Commission's regulations and all applicable requirements have been satisfied.

9311030301 931021 5-PDR ADOCK 05000321 P PDR

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2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license +

amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 190 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance to be implemented by January 1, 1994.

FOR THE NUCLEAR REGULATORY COMMISSION W

oertA.k. Hermann, Acting Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

Attachment:

Technical Specification Changes Date of Issuance: October 21, 1993 J

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pn nauq h 'g UNITED STATES NUCLEAR REGULATORY COMMISSION

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION ,

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. NPF-5

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The applications for amendments to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated September 21, 1992; October 14, 1992, as supplemented January 15, March 26, and July 30, 1993; and May 3, 1993, as supplemented October 5, 1993, comply with the standards and reouirements of the Atomic Energy Act of 1954, as '

amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth l in 10 CFR Chapter I; 1

D. The issuance of this amendment will not be inimical to the common l defense and security or to the health and safety of'the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have j been satisfied. l l

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2. Accordingly, the license is hereby amended by page changes to the !

Technical Specifications as indicated in the attachment to this license .i amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 .

is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 129 , are hereby incorporated in the .

license. The licensee shall operate the facility in accordance with i the Technical Specifications. l

3. This license amendment is effective as of its date of issuance to be implemented by January 1, 1994.

FOR THE NUCLEAR REGULATORY COMMISSION W

Robert A. Hermann, Acting Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation ,

Attachment:

Technical Specification -

Changes

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Date of Issuance: October 21, 1993 l

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4 ATTACHMENT TO LICENSE AMENDMENT NO.190 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 AtfD TO LICENSE AMENDMENT N0.i?9 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with i the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Paoes Insert Paaes Unit 1 vi vi ix ix 1.0-8 1.0-8 1.0-9 1.0-9 3.2-18 3.2-18 3.14-1 3.14-1 3.14 3.14-5 3.14 3.14-5 3.14-6 3.14-6 3.14-7 3.14-7 3.14-8 3.14-8 3.14-9 3.14-9 3.14-10 3.14-10 3.14-11 3.14-11 3.14-12 3.14-12 3.14-13 3.14-13 3.14-14 3.14-14 3.15-1 3.15-1 3.15 3.15-3 3.15 3.15-3 ;

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1 HATCH UNIT 1 a TECH SPEC !

AMENDMENT 190 i t

s Section Section P_422 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.14 INSTRUMENTATION 4.14 INSTRUMENTATION l I 3.15 RADI0 ACTIVE EFFLUENTS 4.15 RADIOACTIVE EFFLUENTS l CONCENTRATION AND DOSE CONCENTRATION AND DOSE 3.16 ENVIRONMENTAL 4.16 ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM 5.0 MAJOR DESIGN FEATURES 5.0-1 A. Site 5.0-1 B. Reactor Core 5.0-1 C. Reactor Vessel 5.0-1 D. Containment 5.0-1 E. Fuel Storage 5.0-1 F. Seismic Design 5.0-2 6.0 ADMINISTRATIVE CONTROLS 6-1 I 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Unit Staff Qualifications 6-6 6.4 Training 6-6 6.5 Review and Audit 6-6 6.6 Reportable Event Action 6-12 6.7 Safety Limit Violation 6-12 6.8 Procedures 6-13 6.9 Reporting Requirements 6-14 I 6.10 Record Retention 6-18 6.11 Radiation Protection Program 6-20 6.12 High Radiation Area 6-20 6.13 Integrity of Systems Outside Containment 6-21 6.14 Iodine Monitoring 6-21 6.15 Environmental Qualification 6-22 6.15 Post-Accident Sampling and Analysis 6-23 6.17 Offsite Dose Calculation Manual 6-23 6.18 Radioactive Effluents Control Program 6-23 6.19 Radiological Environmental Monitoring Program 6-23a 6.20 Process Control Program (PCP) 6-23b HATCH - UNIT 1 vi Amendment No. 190

LIST OF TABLES (Concluded)

Table Title Pigg 4.6-1 Snubber Visual Inspection Interval 3.6-10e 3.7-1 Primary Containment Isolation Valves Which 3.7-16 Receive a Primary Containment Isolation Signal 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary Containment Testable Isolation Valves 3.7-23 3.13-1 (Deleted) 3.13-2 (Deleted) 3.14.1-1 (Deleted) 3.14.2-1 Explosive Gas Monitoring Instrumentation 3.14-7 4.14.1-1 (Deleted) 4.14.2-1 Explosive Gas Monitoring Instrumentation 3.14-11 Surveillance Requirements 4.15.1-1 (Deleted) 4.15.2-1 (Deleted) 3.16.1-1 (Deleted) 3.16.1-2 (Deleted) 4.16.1-1 (Deleted) 6.2.2-1 Minimum Shift Crew Composition 6-4 6.9.1.7-1 (Deleted) l 6.9.2-1 Special Reporting Requirements 6-19 HATCH - UNIT 1 ix Amendment No. 190

s 1.0 DEFINITIONS UU. SOUR.CE 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 governirsg 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 OFFSliE 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 i 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. A D_ASE005 RADWASTE TREATMENT SYSTEM This definition transferred to the ODCM per NRC Generic Letter 89-01.

HATCH - UNIT 1 1.0-8 Amendment No. 190

1.0 DEFINITIONS (Continued)-

ZZ. MEMBER OF THE PUBLIC l

NEMBER OF THE PUBLIC means an individual in a controlled area or UNRESTRICTED AREA. However, an individual is not a HEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose. This category may include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

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.

BBB. UNRESTRICTED AREA UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

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.

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 a manner that replacement air or gas is 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 Amendment No. 190

--4 Table 3.2-8 S RADIATION MONITORING SYSTEMS WHtCH UMIT RADIOACTIVITY RELEASE t

Ref. Instrument Trip Repred Trip Setting Action to be taken if Romerke

a No. Condition Operable there are not two operable (e) Namencle- Channele or tnpped trip systems

-Q ture per Trip Systoni M

1. Off-ges Uoecele/ 1 At a value not (c) (d) 2 upecafee or 1

- Poet Treatment Downecele to exceed the downscele and 1 Radiation equivelent of upacela, or 2 doww i Monitore the eteck re- scalee wit isoiste lease Emit the SJAE off-ges indicated in

Specification 6.18(7) l

2. R.fuesine neer uneesie 2 52o mraw C.es. refuesina op.re- 2 up.cel. wis l i Exhaust Vent tions, if in progrees. lealete the secondary Redeelon toolete the secondary contamment and Mordters containment and start initiate the standby the etendby ese treet- gee treatment evetern g

. mont system.

N a

3. Roeotor Oldg. Upecele 2 $20 mr/hr leoiste the secondary 2 upecede we isolete 1 Exhaust Vent containment. etort stand- the :n -i son-Redetion by gee treetment eyotem, teinment and ledelete g Monitore close primary contelr* the standry pas e

g rnent end vont veiwee. tresement system.

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4. Control Room Downscele 1 10.015 mr/hr Refer to Specifications 1 staaA or 2 down-r+ intake 3.12.C. and 3.12.D. eesles we eseusse 6 z Medlesion Hi S t.O mr/hr- the MCRECS in the

,0 Mordtere contrei room pese-ouriresion mode.

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s 3/4.14 INSTRUMENTATION l RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION This specification transferred to the ODCM per NRC Generic Letter 89-01.

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t HATCH-UNIT 1 3.14-2 through Amendment No. 190 3.14-5 f

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INSTRUMENTATION

' EXPLOSIVE GAS MONITORING INSTRUMENTATION l LIMITING CONDITION'FOR OPERATION 3.14.2 The explosive gas monitoring instrumentation channels l l shown in table 3.14.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.2.6 are not exceeded.

APPLICABILITY As shown in table 3.14.2-1.

ACTION t

a. With an explosive gas monitoring instrumentation l channel'alars/ trip setpoint less conservative .

than a value that will ensure that-the limits of l 3.15.2.6 are met, without delay restore the l setpoint to a value that will ensure that the limits ,

of Specifiestion 3.15.2.6 are met or declare the !

channel inoperable and take the ACTION shown in table 3.14.2-1.

b. With the number of channels OPERABLE less than the minimum channels required by table 3.14.2-1, take the ACTION shown in table 3.14.2-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Consnission pursuant to Specification 6.9.2 to explain !

why this inoperability was not corrected in a timely manner.

c. When the ACTION statement or other requirements of this LCO 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 a minimum, the requirements of the ACTION statement are satisfied.

SURVEILLANCE REOUIREMENTS ,

1 4.14.2 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.14.2-1.

s HATCH-Unit 1 3.14-6 Amendment No. 190

TABLE 3.14.21 (SHEET 1 OF 23

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9 EXPLOstVE G AS MONITORING INSTRUMENTATION g e

MNmum Z inetrument Chennels OPERABLE Aeoliceb4ity Parameter ACTION

1. Mein Condenser Offgas Treatment System Explosive Gee Monitoring System

- % Hydrogen 108 Hydrogen Modter (1) t,a M

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l HATCH - UNIT 1 3.14-8 ' Amendment No.190

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TABLE 3.14.2-1 (SHEET 2 0F 2) l EXPLOSIVE GAS MONITORING INSTRUMENTATION l Table Notations

- During main condenser offgas treatment system operation.

ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided:

(a) Gas samples are collected once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the ensuing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or (b) Using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

One instrument channel may be inoperable for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to perform required surveillances prior to entering other applicable actions.

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HATCH-UNIT 1 3,14-10 Amendment No.190

% TABLE 4.14.2-1 (SHELT 1 OF 21

-4 l 9 EXPLOSIVE G AS MOND SRING l

, INSTRUMENTATION SURVEILLANCE REOtflREMENTS C

Z

$ CHANNEL SOURCE CHANNEL CHANNEL FUNCTIONAL instrument CHECK CHECK CALIBRATION TEST

1. Mein Condenser Offges Treatnwnt System Explosive Gas Mordtoring System Hydrogen Monitor D" NA O(2) M 4.

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1 HATCH - UNIT 1 3.14-12 Amendment No.190

TABLE 4.14.2-1 (SHEET 2 0F 2) l EXPLOSIVE GAS MONITORING l INSTRUMENTATION SURVEILLANCE REOUIREMENTS Table Notations

- During main condenser offgas treatment system operation.

(1) Deleted (2) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a. One volume-percent hydrogen, balance nitrogen.

b. Four volume-percent hydrogen, balance nitrogen.

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HATCH-UNIT 1 3.14-13 Amendment No. 190

INSTRUMENTATION BASES 3/4.14.1 RADI0 ACTIVE LIOVID EFFLUENT INSTRUMENTATION This specification transferred to the ODCM per NRC Generic Letter 89-01. l 3/4.14.2 EXPLOSIVE GAS MONITORING INSTRUMENTATION l The monitoring instrumentation includes provisions for monitoring l (and controlling) the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criterion 63 of Appendix A to 10 CFR Part 50.

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HATCH-UNIT 1 3.14-14 Amendment No. 190 l l

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3/4.15 RADI0 ACTIVE EFFLUENTS 3/4.15.1 LIOUID EFFLUENTS CONCENTRATION This specification transferred to the ODCM per NRC Generic Letter 89-01.

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HATCH - UNIT 1 3.15-2 through 3.15-3 Amendment No. 190 j

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RADIDACTIVE EFFLUENTS D91E This specificat' ion transferred to the ODCM per NRC Generic Letter 89-01.

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i HATCH - UNIT 1 3.15-5 Amendment No. 190 {

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RADI0 ACTIVE EFFLUENTS LIOUID WASTE TREATMENT This specification transferred to the ODCM per NRC Generic Letter 89-01.

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h HATCH - UNIT 1 3.15-7 Amendment No. 190

RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.15.1.4N The contents within any outside temporary tank l 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 above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents within the limit and provide notification to the Commission pursuant to Specification 6.9.1.8.

SURVEILLANCE RE0VIREMENTS 4.15.1.4 The quantity of radioactive mater!al 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 holding the tank contents and not having tank overflows and drains connected to the liquid radwaste treatment system.

HATCH - UNIT 1 3.15-8 Amendment NO. 190

RADIOACTIVE EFFLUENTS 3/4.15.2 GASE0US EFFLUENTS DOSE RATE This specification trerferred to the ODCM per NRC Generic Letter 89-01.

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HATCH - UNIT 1 3.15-12 Amendment No. 190 l

RADI0 ACTIVE EFFLUENTS DOSE. NQfLLE GASES This specification transferred to the ODCM per NRC Generic Letter 89-01.

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i HATCH - UNIT 1 3.15-13 Amendment No. 190

RADI0 ACTIVE EFFLUENTS DOSE. RADIOI0 DINES. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM. AND RADIONVCLIDES OTHER THAN NOBLE GASES This specification transferred to the ODCM per NRC Generic Letter 89-01.

liATCH - UNIT 1 3.15-14 Amendment No. 190

B@I0 ACTIVE EFFLUENTS GASE0US RADWASTE TREATMENT This specification transferred to the ODCH per NRC Generic Letter 89-01.

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HATCH - UNIT 1 3.15-15 Amendment No. 190 i

RADIOACTIVE EFFLUENTS TOTAL DOSE This specification transferred to the ODCH per NRC Generic Letter 89-01.

HATCH - UNIT 1 3.15-16 Amendment No. 190

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HATCH - UNIT 1 3.15-17 Amendment No. 190 t

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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.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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b. When the ACTION statement or other requirements of this l LCO 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 a !

minimum, the requirements of the ACTION statement are satisfied. ;

i SURVEILLANCE RE0VIREMENTS 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 '

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

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RADI0 ACTIVE EFFLUENTS MAIN CONDENSER -

LIMITING CONDITION FOR OPERATION 3.15.2.7 The gross gamma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation system pretreatment monitor station shall be limited to s 240,000 pCi/second.

APPLICABILITY At all times.

ACTION With the gross gamma radioactivity rate of the aforementioned six noble gases at the pretreatment monitor exceeding 240,000 pCi/second, restore the gross radioactivity rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least the Hot Standby Mode within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE0VIREMENTS 4.15.2.7.1 The radioactivity rate of the aforementioned six noble gases near the outlet of the main condenser air ejector shall be continuously monitored in accordance with the ODCH. l 4.15.2.7.2 The gross radioactivity (beta and/or gamma) rate of the aforementioned six noble gases from the main condenser air ejector shall be determined to be within the above limit at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the pretreatment monitoring station:

a. Monthly when plant is operating.

b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an evacuation system pretreatment increase of greater than 50 percent, as indicated by the condenser monitor, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the primary coolant.

HATCH - UNIT 1 3.15-19 Amendment No. 190

RADI0 ACTIVE EFFLUENTS 3/4.15.3 SOLID RADI0 ACTIVE WASTE This specification transferred to the PCP per NRC Generic Letter 89-01.

HATCH - UNIT 1 3.15-20 Amendment No. 190

RADI0 ACTIVE EFFLUENTS BASES 3/4.15.1 LIOUID EFFLUENTS 3/4.15.1.1 CONCENTRATION This specification transferred to the ODCM per NRC Generic Letter 89-01. l 3/4.15.1.2 DRSE This specification transferred to the ODCM per NRC Generic Letter 89-01. -,

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HATCH - UNIT 1 3.15-21 Amendment No. 190

RADI0 ACTIVE EFFLUENTS BASES l

1 3/4.15.1.3 L10VID WASTE TREATMENT 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 concentrations would be less than the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2 (Column 2),

at the nearest surface water supply in an UNRESTRICTED AREA.

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

l HATCH - UNIT 1 3.15-22 Amendment No. 190

1 RADI0 ACTIVE EFFLUENTS i BASES l

3/4.15.2.2 DOSE. NOBLE GASES This specification transferred to the ODCM per NRC Generic Letter 89-01.

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t HATCH - UNIT 1 3.15-23 Amendment No. 190 >

RADI0 ACTIVE EFFLUENTS BASES 3/4.15.2.3 DOSE. RADIOI0 DINES. RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER

_TjiAN NOBLE GASES This specification transferred to the ODCM per NRC Generic Letter 89-01.

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HATCH - UNIT 1 3.15-24 Amendment No. 190

~ RADIOACTIVE' EFFLUENTS BASES s

3/4.15.2.4' GASEOUS WASTE TREATMENT This specification transferred to the ODCM per NRC Generic Letter 89-01.'

3/4.15.2.5 DD1E This specification transferred to the ODCM per NRC Generic Letter 89-01.

3/4.15.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability-limit of hydrogen. (Automatic control features are-included in'the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control- features include isolation of the source of hydrogen, automatic diversion to recombiners or injection of dilutants to reduce the concentration below the flammability limit.) Maintaining.the concentration of hydrogen beiow its flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to-10 CFR Part 50.

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.3/4.15.2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total-body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in HATCH - UNIT 1 3.15-25 Amendment No. 190

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

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-RADI0 ACTIVE EFFLUENTS BASES-l the event this effluent is inadvertently discharged without

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treatment directly to the environment. This specification

. implements-the requirements of General Design ~ Criteria 60 and 64 -

of Appendix A to 10 CFR Part 50.-

3/4.15.3 SOLID RADIOACTIVE WASTE This specification transferred to the PCP per NRC Generic Letter 89-01. ;

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I HATCH - UNIT 1 3;15-26 Amendment No. 190

4 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.16'.1 MONITORING PROGRAM This specification transferred to the ODCH per NRC Generic Letter 89-01.

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HATCH-UNIT 1 3.16-1 Amendment No. 190

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HATCH-UNIT I 3.16-2 through 3.16-10 Amendment No. 190

r RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.16.2 LAND USE SURVEY This specification transferred to the ODCM per NRC Generic Letter 89-01. .

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HATCH-UNIT 1 3.16-11 Amendment No. 190 i

I RADIOLOGICAL-ENVIRONMENTAL MONITORING

.16,3 INTERLABORATORY COMPARISON PROGRAM This spec 1fication transferred to the ODCM per NRC Generic Letter 89 03',

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I HATCH-UNIT 1 3.16-12 Amendment No. 190

3/4;16 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.16.1 MONITORING PROGRAM This specification transferred to the ODCM per NRC Generic Letter 89-01.

3/4.16.2 LAND USE SURVEY l This specification transferred to the ODCM per NRC Generic Letter 89-01.

3/4.16.3 INTERLABORATORY COMPARIS0N PROGRAM This specification transferred to the ODCM per NRC Generic Letter 89-01.

HATCH-UNIT 1 3.16-13 Amendment No. 190

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.0 The General Manager-Nuclear Plant shall provide direct executive oversight over all aspects of Plant Hatch.

6.1.1 The Assistant General Manager-Plant Operations (AGM-PO) shall be responsible for overall unit operation, except for the Radiological Environmental Monitoring Program as described below and for delegation in writing of the succession of this responsibility during his absence. Certain plant support functions shall be the responsibility of the Assistant General Manager-Plant Support. (AGM-PS) .

6.1.2 The General Manager-Nuclear Plant or his designee shall be responsible for the Radiological Environmental Monitoring Program as described in Specification 6.19 and for the writing of the Annual Radiological l Environmental Surveillance Report.

6.1.3 Each of the above-mentioned individuals is responsible for the accuracy of the procedures needed to implement his responsibilities.

6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear.

power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Plant Hatch Unit 2 updated FSAR.

b. The AGM-PO shall be r(sponsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President-Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety.

HATCH - UNIT 1 6-1 Amendment No. 190

ADMINISTRATIVE CONTROLS ANNUAL pEPORTS (Continued) 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 greater than 100 mrem /yr and their ass,ociated man rem exposure according to work and job functions,' e.g., reactor operations I 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 on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the 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 challenges to safety / relief valves.

c. The results of specific activity analysis in which the primary coolant 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Cleanup system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration 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; and (5) The time duration when the specific activity of the primary coolant exceeded the radiolodine limit.

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

ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT

6.9.1.6 The Annual Radiological Environmental Surveillance Report covnring 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 ODCM and Sections IV.B.2, IV.B.3, and 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.

2This tabulation supplements the requirements of 20.2200 of 10 CFR Part 20. l l

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l HATCH - UNIT 1 6-15 Amendment No. 109 l

ADMINISTRATIVE CONTROLS l

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 ODCH and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

a. 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 6-15a Amendment No.190

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l HATCH - UNIT I 6-15b Amendment No. 190

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HATCH - UNIT 1 6-15c Amendment No. 190 i i

ADMINISTRATIVE CONTROLS I

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a co)y to the Regional Office of Inspection and Enforcement no later tlan the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.11.a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

(1) Operation with a Limiting. Control Rod Pattern (for Rod Withdrawal Error, RWE) for S; ecification 3.3.F, (2) The Average Planar Linear Heat Generation Rate (APLHGR) for Specification 3.11.A, (3) The Linear Heat Generation Rate (LHGR) for Specification 3.11.B, and (4) The Minimum Critical Power Ratio (MCPR) for Specifications 3.3.F and 3.11.C and Surveillance Requirement 4.11.C.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the following documents.

(1) NEDE-2401'-P-A, " General Electric Standard Application for Reactor Sel," (applicable amendment specified in the CORE OPERATINu LIMITS REPORT).

(2) " Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment No. 157 to facility Operating License DPR-57," dated September 12, 1988.

c. The core operating limits shall be determined so that all a)plicable limits (e.g., fuel thermal-mechanical limits, core tiermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

HATCH - UNIT 1 6-15d Amendment No. 190

d o ADMINISTRATIVE CONTROLS RECORD RETENTION (Continuedi

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

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

e. Records of transient or operational cycles for those unit components ,

identified in Table 5.0.G-1.

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f. Records of reactor tests and experiments,

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.

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.

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

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 commences and associated installation and maintenance records. .

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

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel 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.

6.12 HIGH RADIATION AREA j 6.12.1. In lieu of the " control device" or " alarm signal" required by paragraph 1 20.1601(a) of 10 CFR *1, each high radiation area in which the intensity of radiation is greater an 100 mrem /hr but less than 1000 mrem /hr** shall be barricaded and consp 'usly posted as a high radiation area and entrance thereto shall be con ' ed '

by requiring issuance of a Radiation Work Permit *.

Any individual or gr ;, 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 issuance requirement during the performance of their assigned radiation l protection duties, provided they comply with approved radiation protection l procedures for entry into high radiation areas. I

- Measured at 30 cm from the radiation source or from any surface that the radiation penetrates.

i HATCH - UNIT 1 6-20 Amendment NO. 190 ,

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ADMINISTRATIVE EONTROLS -l 1

to enter such areas shall be provided with or accompanied by one or more of.

'the following:

a. A radiation monitoring device which continuously indicates the. J radiation dose rate in the area. ;

b A radiation monitoring device which continuously integrates the -;

radiation dose rate in the area and alarms when a preset integrated !

dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the are?, us been- !

established and personnel have been made knowledgeable of them. 't

c. An individual qualified in radiation protection procedures who is !

equipped with a radiation dose rate monitoring device. This individual shall be responsible for prow? ding positive control over .;

the activities within the area and shall perfom periodic radiation !

surveillance at the frequency specified by the facility Health l Physics supervision in the Radiation Work Permit.- ;

c 6.12.2. The requirements of 6.12.1., above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr* but less than 500 rads in I bour.** In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the. a keys shall be maintained under the administrative control of the Shift ,

Supervisor on duty and/or the Laboratory Foreman on' duty. ,

6.13. INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT l

The licensee shall implement a program to reduce leakage from systems outside i

containment that would or could contain highly radioactive fluids during a' serious transient or accident'to as low as practical levels. This program -

shall include the following:

1) Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2) System leak test requirements, to the extent pemitted by system design and radiological conditions, for each system at a frequency not.

to exceed refueling cycle intervals. The systems subject to this testing ;

are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, (4) HPCI, and ($) RCIC.

6.14. 10 DINE MONITORING The licensee shall implement a program which will ensure the capability to accurately detemine the airborne iodine concentration in vital areasm under 'l accident conditions. This program sha11' include the following:

!) Training of personnel,

2) Procedures for monitoring, and

3) Provisions for maintenance of sampling and analysis equipment.

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Measurement made at 30 centimeters from the radiation source or from any ,

surface that the radiation penetrates.

- Measurement made at I meter from the radiation source or from any surface' that the radiation penetrates.

t mAreas requiring personnel access for establishing hot shutdown condition.

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MATCH - UNIT 1 6-21 Amendment No. 190 i

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ADMINISTRATIVE CONTROLS 4

6.16 POST ACCIDENT SAMPtlNG AND ANALYSl$

A program shall be established, implemented, and maintained to ensure the capability to obtain and analyze samples of reactor coolar.t. 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 recuired 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 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,

b. Become 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 00CM 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 PAD 10 ACTIVE EFFtVENTS CONTp0L PDOGpAM 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 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 00CM,

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

liquid effluents to UNRESTRICTED AREAS conforising to 10 CFR Part 20 Appendix B, Table II, 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, HATCH - UNIT 1 6-23 Amendment No. 190

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20Mf41ST:ATIVE CC

ca010 ACTIVE EULUENTS C0'4TDOL PDOGPAM (Centinued) ,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMSER OF THE PUBLIC from radioactive materials in ltouid ef fit.enu releaseo from each unit to UNRESTRICTED AREAS conforming to -

Appenoix 1 to 10 CFR Part 50,

5) Determination of cumulative and projected dose contrtoutions from radioactive effluents for the current calendar cuarter and current calendar year in accordance with the methodology ano parameters in i the 0 % M at least every 31 days,

6) L1-itatiens on the OPERABILITY and use of the liouid and caseous -

effluent treatment systems to ensure that the accropriate portiers of these systems are used to reduce releases of racicactint, onen the crojected doses in a 31-day ceriod would exceed 2 percent of tre auidelines for the annual DOSE or dose commitment conforming to Aapercix ! to 10 CFR Dart 50,

7) Limitations on the dose rate resulting from radioactive matertal released in gaseous effluents from the site to areas at and beyono the SliE SOUNDARY as follows:

a. Jor noble gases, less than or equal to a dose rate of ,

00 mrem / year to the total body and less than or equal to a cose rate of 3000 mrem / year t) the skin, and

b. Fcr lodine-131 e-133, tritium, and all radionuclides in carticulate ' h half-lives greater than 8 days, less than or equal t< rate of 1500 mrem / year to any organ.

8) Lim 1tations ( * .e annual and quarterly air doses resulting from noble gases roeased in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50,

9) Limitations en the annual and quarterly doses to a MEMBER OF THE PUBLIC frem lodine-131, lodine-133, tritium, and all radionuclides in carticulate form with half-lives greater than 8 days in caseous effluents released from each unit to areas beyond the S!TC 60Vf;0ARL conforming to Appendix 1 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 uranium fuel cycle sources conforming to 40 CFR Part 190.

6.19 PADIOLOGICAL ENVIPONMENTAL MONITORINO PROGPAM A program shall be established, implemented, and maintained to monitor the radiation and radionuclides in the environs of the plant. The program shall provide: (1) representative measurements of radioactivity in the btghest 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.

and (3) include the following: ;

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARf are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in an Interlaboratory Comparison Program to ensure that Independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

l HATCH - UNIT 1 6-23a Amendment No. 190

ADMINISTRATIVE CONTROLS 6.20 PROCESS CONTROL PROGRAM (PCP) '

A program shall be established, implemented, and maintained to 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 require-ments, and other requirements governing the disposal of solid radioactive waste.

Changes to the PCP:

a. Shall 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 j appropriate analyses or evaluations justifying the change (s), j and

2) A determination that the change will maintain the overall conformance of the solidified waste product-to existing requirements of Federal, State, or other applicable regulations,

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

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HATCH - UNIT 1 6-23b Amendment No. 190

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HATCH UNIT 2 TECH SPEC :

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AMENDMENT 129 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION P&E 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-24 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-33 3/4.3.5 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION 3/4 3-37 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-43 Seismic Monitoring Instrumentation 3/4 3-47 Remote Shutdown Monitoring Instrumentation 3/4 3-50 Post-Accident Monitoring Instrumentation 3/4 3-53 Source Range Monitors 3/4 3-56 Traversing Incore Probe System 3/4 3-57 i

Main Control Room Environmental Control System 3/4 3-58 ;

(MCRECS) Actuation Instrumentation Radioactive Liquid Effluent Instrumentation 3/4 3-60a i Explosive Gas Instrumentation 3/4 3-60f l ;

l 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM 3/4 3-61 !

3/4.4 REACTOR COOLANT SYSTEM i 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 d-1 Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 i

Amendment No. 129 HATCH - UNIT 2 V l

i INDEX BASES '

SECTION EAE ,

INSTRUMENTATION (Continued)

Remote Shutdown Monitoring B 3/4'3-3 Instrumentation Post-Accident Monitoring B 3/4 3-4 Instrumentation Source Range Monitors B 3/4 3 Traversing Incore Probe System B 3/4 3-4 l Chlorine Detectors ' B 3/4 3-4 Fire Detection Instrumentation B 3/4 3-4 Radioactive Liquid Effluent Instrumentation B~3/4 3-5 Explosive Gas Instrumentation B 3/4 3-5 l 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM B 3/4 3-5 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION B 3/4 3-Sa !

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM B 3/4 4 ~

Jet Pumps B 3/4 4-1 Idle Recirculation Loop Startup B-3/4 4-la 3/4.4.2 SAFETY / RELIEF VALVES B 3/4.4-la Low-Low Set Systems B 3/4-4-Ib 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems B 3/4 4-2 Operational Leakage B 3/4 4-2 3/4.4.4 CHEMISTRY B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY. B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS B 3/4 4-4 HATCH - UNIT 2 XI Amendment No. 129 r

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INDEX ADMINISTRATIVE CONTROLS SECTION PEE SAFETY REVIEW BOARD (Continued)

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 PROCEDVRES 6-12 19 REPORTING RE0VIREMENTS ROUTINE REPORTS 6-13 STARTVP REPORT 6-13 ANNUAL REPORTS 6-13 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 6-14 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6-14a l .;

MONTHLY OPERATING REPORT 6-14d CORE OPERATING LIMITS REPORT 6-14d l

SPECIAL REPORTS 6-17 ;

6.10 RECORD RETENTION 6-17 6.11 RADISTION PROTECTION PROGRAM 6-18 6.12 HIGH RADIATION AREA 6-18 l

l Meneen . 29 HATCH - UNIT 2 XVI

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INDEX ADMINISTRATIVE CONTROLS SECTION A P_AJE 6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT 6-19 6.14 IODINE MONITORING 6-20 6.15 ENVIRONMENTAL OUALIFICATION 6-21 6.16 POST-ACCIDENT SAMPLING AND ANALY115 6-22 6.17 0FFSITE DOSE CALCULATION MANUAL 6-22 6.18 RADI0 ACTIVE EFFLUENTS CONTROL PROGRAM 6-22 6.19 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 6-22a 6.20 PROCESS CONTROL PROGRAM (PCP) 6-22b i

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HATCH - UNIT 2 XVII Amendment No. 129

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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 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.

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

OFFSITE DOSE CALCULATION MANUAL The OFFSITE 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 Ertvironmental 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.

GASE0US RADWASTE TREATMENT SYSTEM This definition transferred to the ODCM per NRC Generic Letter 89-01. l HATCH - UNIT 2 1-7 Amendment No. 129

1.0 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 not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose. This category may include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

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 figure 3.11-1.

UNRESTRICTED AREA UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee or any area within the SITE BCUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

DOSE E0VIVALENT 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 quantity and isotopic mixture of I-131, I-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 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, concentration, or other operating condition in such a l manner that replacement air or gas is required to purify the l confinement. ]

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-4 TABLE 3.3.6.1-1 4

x: R ADIATION MONITORING INSTRUMENTATION

. t j E APPLICABLE

! y MINIMUM CHANNELS OPERATIONAL ALARM / TRIP MEASUREMENT INSTRUMENTATION OPERABLE CONDITIONS SETPOINT RANGE 4

ACTION i 1. Off4ee l Post Treatment l Mordtere 2 1, 2 (e) 10 ' to 10' cpe 50 4 (2D11-K615 A, B) 1- 2. Control Room ,

j' intake Monitore 2 1,2,3,4,5 1 mr/hr 'O.01 to 100 mr/hr 51 i (1Z41-R615 A, B) 4 1

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" Velve not to exceed the :;ii_.; of the eteok release limit irdested in Specificedon 8.18(7). ]

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,vr...,e-, ...-# . . _ . ym... , u--m - r www. . - - .r # , -.r. s,.,- .- ...,r-.t.-, ,, ,,,,..m., ,.,., *m,e #.#,.. .,_e , , - ..n . .y. ,,cmw,, . . , , . . ., n.._ .-

INSTRUMENTATION RADI0 ACTIVE LIOVID EFFLVENT INSTRUMENTATION This specification transferred to the ODCM per _NRC Generic Letter 89-01.

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f HATCH - UNIT 2 3'4 3-60b through 3/4 3-60e Amendment No. 129

l-r INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION l LIMITING CONDITION FOR OPERATION <

3.3.6.10 The explosive gas monitoring instrumentation l .

channals shown in table 3.3.6.10-1 shall be. 0PERABLE !

with their alarm / trip setpoints set to ensure tha.t the limits of Specification 3.11.2.6 are not exceeded. l APPLICABILITY As shown in table 3.3.6.10-1.

ACTION

a. With an explosive gas monitoring instrumentation l_

channel alarm / trip setpoint less conservative than a value that will ensure that the limits of 3.11.2.6 are met, without delay restore the l setpoint to a value that will ensure that the limits of Specification 3.11.2.6 are met or declare the channel inoperable and take the ACTION shown in table 3.3.6.10-1.

b. With the number of channels OPERABLE less than the minimum channels required by table 3.3.6.10-1, take the ACTION shown in table 3.3.6.10-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why ;

this inoperability was not corrected in a timely manner. ,

c. One instrument channel may be inoperable for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to perform required surveillances prior to entering other l applicable ACTIONS. ;

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

JURVEILLMCE RE0VIREMENTS .

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4.3.6.10 Each explosive gas monitoring instrumentation l i channel shall be demonstrated OPERABLE by performance of ,

the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL l j FUNCTIONAL TEST operations at the frequencies shown in '

table 4.3.6.10-1.

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HATCH - UNIT 2 3/4 3-60f Amendment No. 129

l y TABLE 3.3.6.10-1 (SHEET 1 OF 2) g a

o EXPT.OStVE G AS MONITORING INSTRUMENTATION r

i Minimum 5 Channels C Inotrument OPER %BLE Apolicobility Leremeter ACTION

-4

" 1. Mein Condenser Offges Treetment System Explosive Gas Monitoring System Hydrogen Monitor (1) % Hydrogen 106 ta b

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G O

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--_---._---_.--__-____.-_--_-___--.z- - _ - ,

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TABLE 3.3.6.10-1 (SHEET 2 0F 2)

EXPLOSIVE GAS MONITORING INSTRUMENTATION Table Notations

- During main condenser offgas treatment system operation.

ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided: (a) gss samples are collected once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the ensuing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or (b) using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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HATCH - UNIT 2 3/4 3-601 Amendment No. 129 i

, _ . - ._. ._ i

y, TABLE O.3.G.10-1 (SHEEY 1 OF 2)

=?

z EXPLOSIVE G AS MONITORING g-

, INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

Z Q CHANNEL SOURCE CHANNEL

" CHANNEL FUNCTIONAL instrument CHECK CHECK CAlfBRAT10N TEST

1. Main Condenser Offges Treatment System Explosive Ges Monitoring Hydrogen Monitor D** NA Q(2) M w

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TABLE 4.3.6.10-1 (SHEET 2 0F 2)

EXPLOSIVE GAS MONITORING l INSTRUMENTATION SURVEILLANCE RE0VIREMENTS Table Notations

- During main condenser offgas treatment system operation.

(1) Deleted (2) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a. One volume-percent hydrogen, balance nitrogen

b. Four volume-percent hydrogen, balance nitrogen.

HATCH - UNIT 2 3/4 3-60k Amendment No.129

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS ,

CONCENTRATION This specification transferred to tne ODCM per NRC Generic Letter 89-01.

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l RADI0 ACTIVE EFFLUENTS DD.S.E This specification transferred to the ODCH per NRC Generic Letter 89-01.

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i HATCH - UNIT-2 3/4 11-5 Amendment No. 129

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I RADI0 ACTIVE EFFLUENTS LIOUID WASTE TREATMENT This specification transferred to the ODCH per NRC Generic Letter 89-01.

HATCH - UNIT 2 3/4 11-7 Amendment No. 129

f RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION _

3 .11.1. 4 ") The contents within any outside temporary tank shall be limited to s 10 curies, excluding tritium and l 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 above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents within the limit and provide notification to the Comrission 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 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 treatment system.

HATCH - UNIT 2 3/4 11-8 Amendment No. 129

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS ,

DOSE RATE This specification transferred to the ODCH per Generic Letter 89-01.

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HATCH - UNIT 2 3/4 11-10 Amendment No. 129

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RADI0 ACTIVE EFFLUENTS l j

DOSE. NOBLE GASES l l

This specification transferred to the ODCM per NRC Generic Letter 89-01. '

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HATCH - UNIT 2 3/4 11-13 Amendment No. 129

RADI0 ACTIVE EFFLUENTS DOSE. RADIOI0 DINES. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM. AND RADIONUCLIDES OTHER THAN N0BLE GASES This specification transferred to the ODCM per NRC Generic Letter 89-01.

HATCH - UNIT 2 3/4 11-14 Amendment No. 129

r RADI0 ACTIVE EFFLUENTS SASE005 RADWASTE TREATMENT This specification transferred to the ODCM per NRC Generic Letter 89-01.

HATCH - UNIT 2 3/4 11-15 Amendment No.129

i RADI0 ACTIVE EFFLUENTS 3/4.11.2.5 TOTAL DOSE This specification transferred to the ODCM per NRC Generic Letter 89-01.

l-i HATCH - UNIT 2 3/4 11-16 Amendment No. 129

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HATCH - UNIT 2 3/4 11-17 Amendment No. 129 l l

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to s 4 percent by volume.

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 within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. 4 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, Specification 3.3.6.10.

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i HATCH - UNIT 2 3/4 11-18 Amendment No. 129

RADIOACTIVE EFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2.7 The gross gamma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation system pretreatment monitor station shall be limited to s 240,000 pCi/second. ,

APPLICABILITY At all times.

ACTION With the gross gamma radioactivity rate of the aforementioned six noble gases at the pretreatment monitor exceeding 240,000 pCi/second, restore the gross radioactivity rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least OPERATIONAL CONDITION 2 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SVRVEILLANCE RE0ViREMENTS 4.11,2.7.1 The radioactivity rate of the aforementioned six noble gases near the outlet of the main condenser air ejector shall be continuously monitored in accordance with the ODCM. l 4.11.2.7.2 The gross radioactivity (beta and/or gamma) rate of the six aforementioned noble gases from the main condenser air ejector shall be determined to be within the above limit at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the pretreatment monitoring station:

a. Monthly when plant is operating.

b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an evacuation system pretreatment increase of greater than 50 percent, as indicated by the condenser monitor, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the primary coolant.

HATCH - UNIT 2 3/4 11-19 Amendment No.129

RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE This specification transferred to the PCP per NRC Generic Letter 89-01.

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING This specification transferred to the ODCM per NRC Generic Letter 89-01, l

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HATCH-UNIT 2 3/4 12-1 Amendment No. 129

s INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.6.9 RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION This specification transferred to the 0DCM per NRC Generic Letter 89-01.

3/4.3.6.10 EXPLOSIVE GAS INSTRUMENTATION ,

The monitoring instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system. 'The OPERABILITY and use of this. instrumentation.is consistent with -

the requirements of General Design Criterion 63 of Appendix A l

to 10 CFR Part 50.

3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.

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HATCH - UNIT 2 B 3/4 3-5 Amendment No. 129

RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification transferred to the ODCH per NRC Generic Letter 89-01.

3/4.11.1.2 DESI This specification transferred to the ODCH per NRC Generic Letter 89-01.

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HATCH - UNIT 2 B 3/4 11-1 Amendment No. 129

RADIOACTIVE EFFLUENTS , ,

BASES l'

3/4.11.1.3 LJOUID WASTE TREATMENT This specification transferred to the ODCM per NRC Generic j t

Letter 89-01.

3/4.11.1.4 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 1 concentrations would be less than the limits of 10 CFR Part 20, ,

Appendix B (to paragraphs 20.1001 - 20.2401), Table 2 (Column 2), .

f 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 letter 89-01.

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RADI0 ACTIVE EFFLUENTS BASES >

3/4.11.2.2 DOSE. N0BLE GASES This specification transferred to the ODCM per NRC Generic letter 89-01.

m HATCH - UNIT 2 B 3/4 11-3 Amendment No. 129

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE. RAD 1010 DINES. RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN N0BLE GASES This specification transferred to the ODCM per NRC Generic Letter 89-01.

HATCH - UNIT 2 B 3/4 11-4 Amendment No.129

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.h RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.4 GASEOUS WASTE TREATMENT :

This specification transferred to the ODCM per NRC Generic Letter.89-01.

3/4.11.2.5 ESE ,

This ~ specification transferred to the ODCM per NRC Generic Letter 89-01. .

3/4.11.2.6 EXPLOSIVE (:AS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability . limit of {

hydrogen. (Automatic control features are included in the system i to prevent the hydrogen and oxygen concentrations from reaching-these flammability limits. These automatic control features '

include isolation of the source of hydrogen, . automatic diversion ,

to recombiners or injection of dilutants to reduce ~the .'

concentration below the flammability limit.)' Maintaining the concentration of hydrogen below its flammability limit provides 4) assurance that the releases of radioactive materials will be l controlled in conformance with the requirements of General. i Design Criterion 60 of Appendix A to 10 CFR Part 50. .;

3/4.11.2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the -

main condenser provides reasonable assurance that the total-body J) exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of'10 CFR Part 100 in J l

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HATCH UNIT'2 B 3/4 11-5 Amendment No. 129

RADI0 ACTIVE' EFFLUENTS BASES

{

the event this effluent is inadvertently discharged-without ;

treatment directly to the environment. This specification '!

implements the requirements of General Design Criteria-60 and 64~

of Appendix A to 10 CFR'Part 50.

1 3/4.11.3 SOLID RADIOi4CTIVE WASTE ,;

This specification transferred to the PCP per NRC Generic Letter 89-01. .

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.0 The General Manager-Nuclear Plant shall provide direct executive l oversight over all aspects of Plant Hatch.

6.1.1 The Assistant General Manager-Plant Operations (AGM-PO) shall be responsible for overall unit operation, except for the Radiological Environmental Monitoring Program as described below and for delegation in writing of the succession of this responsibility during his absence. Certain plant support functions shall be the responsibility of the Assistant General Manager-Plant Support (AGM-PS). j 6.1.2 The General Manager-Nuclear Plant or his designee shall be responsible for the Radiological Environmental Monitoring Program as described in Specification 6.19 and for the writing of the Annual Radiological l Environmental Surveillance Report.

6.1.3 Each of the above-mentioned individuals is responsible for the accuracy of the procedures needed to implement his responsibilities.

6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Plant Hatch Unit 2 updated FSAR.

b. The AGM-P0 shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President-Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety.

HATCH - UNIT 2 6-1 Amendment No. 129

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 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 greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,m e.g., reactor operations l 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 on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the 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 challenges to safety / relief valves.

c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; l (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was ;

exceeded and results of one analysis after the radiciodine was ;

reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Cleanup system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per l gram as a function of time for the duration of the specific activity l above the steady-state level; and (5) The time duration when the !

specific activity of the primary coolant exceeded the radiciodine limit.

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

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ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORTW 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 vear. 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 ODCM and Sections IV.B.2, IV.B.3, and 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 Part 20. l HATCH - UNIT 2 6-14 Amendment No. 129

ADMINISTRATIVE' CONTROLS :

ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT4 )

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 i 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.

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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 station; however, the submittal shall specify the releases of radioactive -

material from each unit.

HATCH - UNIT 2 6-14a Amendment No.129

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HATCH - UNIT 2 6-14c Amendment No. 129 .;

ADMINISTRATIVE CONTROLS I

HONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience-shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Office of Inspection and Enforcement no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.11.a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

(1) Control Rod Program Controls - Rod Block Monitor for Specification 3.1.4.3, (2) The Average Planar Linear Heat Generation Rate for Specification 3.2.1 and Surveillance Requirement 4.2.1, (3) The Minimum Critical Power Ratio for Specifications 3.1.4.3 and 3.2.3 and Surveillance Requirement 4.2.3, and (4) The Linear Heat Generation Rate for Specification 3.2.4 and Surveillance Requirement 4.2.4.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the following documents.

(1) NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel," (applicable amendment specified in the CORE OPERATING LIMITS REPORT).

(2) " Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment Nos.151 and 89 to facility Operating Licenses DPR-57 and NPF-5," dated January 22, 1988.

c. The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspectc,e.

HATCH - UNIT 2 6-14d Amendment No. 129

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

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 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 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 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.

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 commences and associated installation and maintenance records.

o. Records of reviews performed for changes made to the OFFSITE DOSE i I

CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM l

Procedures for personnel radiation protection shall be prepared consistent with l maintained the requirements of 10 CFR Part 20 and shall be approvedadhered to for all operations 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph of 10 CFR 20 each high radiation area in which the intensity of 20.1601(a)is radiation greater tha,n 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 Work Pemit*.

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 protection duties provided they comply with ap proceduresforenf.ryintohighradiationareas.provedradiationprotection

- Measured at 30 cm from the radiation source or from any surface that the radiation penetrates.

HATCH - UNIT 2 6-18 Amendment No. 129

l ADMINISTRATIVE CONTROLS l

to enter such areas shall be provided with or accompanied by one or more of the following:

4

a. A radiation monitcring device which continuously indicates the l radiation dose rate in the area. j

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be res)onsible for providing positive control over the activities #ithin t1e area and s:1all perform periodic radiation surveillance at the frequency specified by the facility Health Physics supervision in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high ,

radiation area in which the intensity of radiation is greater than 1000 mrem /hr* but less than 500 rads in I hour.** In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Laboratory Foreman on duty.

6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

1) Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2) System leakage test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals. The systems subject to this testing are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, (4) HPCI, and (5) RCIC.

Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.

- Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.

HATCH - UNIT 2 6-19 Amendment No. 129

. 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, 'i 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR ;

Part 50 and not adversely impact.the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Become effective after review and acceptance by the PRB and the ,

approval of the General Manager-Nuclear Plant. l 1

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 j

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 ODCM, (2) shall be implemented by o)erating procedures, l and (3) shall include remedial actions to be taken w1enever the program limits are exceeded. The program shall include the following elements: l

1) Limitations on the OPERABILITY of radioactive liquid and gaseous monitoring instrumentation including surveillance-tests and setpoint I determination in accordance with the methodology in the ODCM, HATCH - UNIT 2 6-22 Amendment No. 129 ;

i 1

6.18 RADIDACTIVE EFFLUENTS CONTROLS PROGRAM (Continued)

2) Limitations at all times on the concentrations of radioactive <

9aterial released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with lb CFR 20.1302 and with the methodology-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 effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,

6) Limitations on the OPERABILITY and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions r of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material !

released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY as follows:

a. For noble gases, less than or equal to a dose rate of 500 mrem / year to the total body and less than or equal to a dose rate of 3000 mrem / year to the skin, and

b. tritium, and all radionuclides in For ladine-131, particulate formIodine-133, with half- lives greater than 8 days, less than or equal to a dose rate of 1500 mrem / year to any organ.

B) 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 1 to 10 CFR Part 50,

9) ! imitations on the annual and quarterly Joses to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, ti cium, and all radionuclides in particulate form with half-lives greater than 8 days in caseous effluents 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 dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

6.19 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A program shall be established, implemented, and maintained to monitor the radiation and radionuclides in the environs of the plant. The program shall provide: (1 in the highest potential e)xposure pathways, and (2) verification ofrepresentative measurem 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 I to 10 CFR Part 50, and (3) include the following:

HATCH - UNIT 2 6-22a Amendnent No. 129

6.19 PADI0 LOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, ,

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 Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.20 PROCESS CONTROL PROGRAM (PCP)

A program shall be established, implemented, and maintained to 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 o,f solid radioactive waste.

Changes to the PCP:

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

shall contain: '

1) Sufficient information to support the change together with the ;

appropriate analyses or evaluations justifying the change (s), and 1

2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective after review and acceptance by the PRB and the !

approval of the General Manager-Nuclear Plant. ;

HATCH - UNIT 2 6-22b Amendment No. 129

ML20059E683

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