ML20196B438

Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift

ML20196B438
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/24/1998
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20196B408	List: 0CAN119801, Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift ML20196B438
References
NUDOCS 9812010100
Download: ML20196B438 (44)

Text

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The ANO-1 plant manager shall be responsible for overall unit operation l

and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 An individual with an active Senior Reactor Operator (SRO) license shall be designated as responsible for the control room command function while the unit is above the Cold Shutdown condition. With the unit not above the Cold Shutdown condition, an individual with an active SRO license or Reactor Operator license shall be designated as responsible for the control room command function.

6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE CRGANIZATIONS 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 organizatien charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the unit specific titles of those personnel fulfilling its responsibilities of the positions delineated in these Technical Specifications shall be documented in the Safety Analysis Report (SAR).

b.

The ANO-1 plant canager shall be responsible for overall unit safe l

1 operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c.

A specified corporate executive 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. The specified corporate executive shall be documented in the SAR.

d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

UNIT STAFF l

6.2.2 The operations manager or an operations staff middle manager shall l

hold a senior reactor operator license.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

9812010100 981124

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PDR ADOCK 05000313 P

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Amendment No. M,M,-34,M, M, M, 117 M,64, M, M, M,4M,4M, M4,44,44

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6.2.2.1 Administrctiva c:ntrols chnl1 b2 octcblichsd to limit ths amount of overtime worked by plant staff performing safety-related functions. These administrative controls shall l

be in accordance with the guidance provided by the NRC Policy i

Statement on working hours (Generic Letter 82-12).

l 6.3.

FACILITY STAFF QUALIFICATIONS l

6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the designated radiation protection l

l manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

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6.5 DELETED 1

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l Amendment No. M,49,M,47,47,H,H,

117a M,83,85,99,M9, M&,H4,M&,M4, MG, 449-l l

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Tablo 6.2-1 ARKANSAS NUCLEAR ONE MINIMUN SHIFT CREW COMPOSITION #

e UNIT 1 LICENSE COLD AND REFUELING CATEGORY ABOVE COLD SHUTOOWN SHUTDOWNS SOL 2

1*

OL 2

1 NON-LICENSED 3

1 1

4

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising refueling operations after the initial fuel loading.

1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

Additional Requirements:

1.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

2.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

3.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

4.

All refueling operations after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

5.

When the unit is above the Cold Shutdown condition, an individual shall provide advisory technical support for the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

l Amendment No. M,M,M,M,M4,MS 118 (Next page is page 126)

6.6 ner.rTrn 6.7 martTV r. Tuft vint.aTTnu 6.7.1 The following actions shall be taken in the event a safety Limit is violated:

a.

The facility shall be placed in at least hot shutdown within one hour.

b.

The Nuclear Regulatory Commission shall be notified pursuant to 10 CFR 50.72 and a report submitted pursuant to the requirements of 10 CFR 50.36 and specification 6.6.

6.8 Pancanunts awn Pananaus 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced belows a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.

b.

Refueling operations.

c.

Sus,sillance and test activities of safety related equipment.

d.

(Deleted) e.

(Deleted) f.

Fire Protection Program Implementation.

g.

New and spent fuel storage.

h.

offsite Dose Calculation Manual and Process Control Program implementation at the site.

1.

Post accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous affluents, and the containment atmosphere).

Amendment No. M,49,M,M,M,M,

126 64,83,99,H e,H 4,443,M 9,493

6.8.2 (Dalstsd) 6.8.3 (Deleted) 6.8.4 The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained:

A program shall be established to implement the leakage rate testing of the reactor building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, l Performance-Based Containment Leak-Test Program,l dated September 1995.

The peak calculated reactor building internal pressure for the design basis loss of coolant accident, Pa, is 54 psig.

The maximum allowable reactor building leakage rate, La, shall be 0.20% of containment air weight per day at Pa.

Reactor building leakage rate acceptance criteria is s 1.0 La-During the first unit startup following each test performed in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and s 0.75 La for Type A tests.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Reactor Building Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Reactor Building Leakage Rate Testing Program.

i Amendment No, M,M,M,M,M,M, 127 M,M,M,M 9,4 M,M 3,4 M,M 9, W,

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Amendment No. M,48,nB 128 l

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o 6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.11 HIGH RADIATION AREA 6.11.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10CFR20, each high radiation area (as defined in 20.202 (b) (3) of 10CFR20) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

l a.

A radfotion monitoring device which continuously indicates the l

radiation dose rate in the area.

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b.

A r.aiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a pre-set integrated done is received.

Entry into such areas with this j

monitoring dev..ce may be made after the dose rate level in the j

area has been established and personnel have been made i

l 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 responsible for providing positive control l

over the activities within the area and shall perform periodic l

radiation surveillance at the frequency specified in the radiation work permit.

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l Amendment No. 44,S4,63,30/2t/90 129 Gesee,44, S4, SS, HO,444, H-3 l

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6.11.2 Tha requiremente of 6.11.1 c.bova, chn11 cleo cpply to each high

-radiation area in which the intensity of radiation is greater than 1000 mram/hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the administrative control of the shift supervisor on duty l

and/or the designated radiation protection manager.

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Amendment No. 84,444 129a(Next page is 140)

e Tha d3sa cceignmento to v rious duty functiens may ba sotimatoe bensd on pocket dosimeter, TLD, or film badge measurements.

Small exposures totaling 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.

6.12.2.3 Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis by the 15* of each month following the calendar month covered by the report.

6.12.2.4 Annual Report All challenges to the pressurizer electromatic relief valve (ERV) and pressurizer safety valves shall be reported annually.

6.12.2.5 Annual Radiological Environmental Operating Report

• The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 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 Offsite Dose calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted in a supplementary report as soon as

possible, 6.12.2.6 Radioactive Effluent Release Report **

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and sol!d waste released from the unit. The material provided shall be consistent wir the a

objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.l.

• A single submittal may be made for ANO.

The submittal should combine those sections that are common to both units.

• • A single submittal may be made for ANO.

The submittal should combine those sections that are common to both units. The submittal shall specify the releases of radioactive material from each unit.

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Amendment No. 9,34, 39,4-7,-73,83, Se, 141 MB,494

6.12.5 Spacial R3 ports Special reports shall be submitted to the Administrator of the appropriate Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.

a.

Tendon Surveillance, Specification 4.4.2.2 b.

Inoperable Containment Radiation Monitors, Specification 3.5.1, Table 3.5.1-1.

c.

Deleted d.

Steam Generator Tubing Surveillance - Category C-3 Results, Specification 4.18.

e.

Miscellaneous Radioactive Materials Source Leakage Tests, Specification 3.12.2.

f.

Deleted g.

Deleted h.

Deleted l

1.

Deleted l

j.

Degraded Auxiliary Electrical Systems, Specification 3.7.2.H.

k.

Inoperable Reactor Vessel Level Monitoring Systems, Table 3.5.1-1 1.

Inoperable Hot Leg Level Measurement Systems, Table 3.5.1-1 m.

Inoperable Main Steam Line Radiation Monitors, Specification 3.5.1, Table 3.5.1-1.

Amendment No. 44,4M,M4,MS,MB, 146a H3

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The ANO-2 plant manager ANO shall be responsible for overall unit l

l operations and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 An individual with an active Senior Reactor Operator (SRO) license shall be designated as responsible for the control room command function while the unit is in MODE 1, 2, 3, or 4.

With the unit not in MODE 1, 2, 3, or 4, an individual with an active SRO license or Reactor Operator license shall be designated as responsible for the control room conmand function.

6.2 ORGANIZATION l

6.2.1 OFFSITE 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 including the unit specific titles of those personnel fulfilling its responsibilities of the positions delineated in these Technical Specifications shall be documented in the Safety Analysis Report (SAR).

b.

The ANO-2 plant manager shall be responsible for overall unit safe l

operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c.

A specified corporate executive shall have corporate responsibility for l 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.

The specified corporate executive shall be documented in the SAR.

l d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 UNIT STAFF l

a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

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b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

ARKANSAS - UNIT 2 6-1 Amendment No. 6, M,W,M,M,M, M,444,44G l

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c.

At loact two licznncd Operataro chtll be prOscnt in th3 csntrol room 1

during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e.

All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

In MODES 1, 2, 3, or 4, an individual shall provide advisory technical support for the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the i

qualifications specified by the Commission Policy on Engineering Expertise on shift.

j g.

Administrative control shall be established to limit the amount of overtime worked by plant staff performing safety-related functions These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).

h.

The operations manager.or an operations staff middle manager shall hold l a senior reactor operator license.

ARKANSAS - UNIT 2 6-2 Amendment No. M, M, M, M, M, M, M, SS, M4, M2

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i TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

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LICENSE APPLICABLE MODES i

CATEGORY 1, 2, 3, s4 5& 6 l

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SOL 2

1 OL i

3 1

i Non-Licensed l

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• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE j

ALTERATIONS.

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1. Shift crew composition may be+1ess than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to-within the minimum requirements of Table 6.2-1.

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I ARKANSAS - UNIT 2 6-4 Amendment No. 30,MS i

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ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the designated radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 6.4 DELETED i

6.5 DELETED t

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ARKANSAS - UNIT 2 6-5 Amendment No. 6,M,M,GO, (Next page is page 6-12a)

E9, M, M, M, M, H4, M9, M3,W,Me

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ARKANSAS - UNIT 2 6-12a Amendment No. W, M G

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following acti0ns shall be taken in the event a Safety Limit is violated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The Vice President, Operations ANO and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

The Nuclear Regulatory Commission shall be notified pursuant to 10CFR50.72 and a report submitted pursuant to the requirements of 10CFR50.36 and Specification 6.6.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced belows a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and tett activities of safety related equipment.

d.

(Deleted) e.

(Deleted) f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants. These procedures should include provisions to assure that sufficient margin is maintained in CPC Type I addressable constants to avoid excessive operator interaction with the CPCs during reactor operation.

NOTE:

Modifications to the CPC software (including changes of algorithms and fuel cycle specific data) shall be performed in accordance with the most recent version of "CPC Protection Algorithm Software Change Procedure,"

CEN-39(A)-P that has been determined to be applicable to the facility. Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.

h.

New and spent fuel storage.

1.

ODCM and PCP implementation.

j.

Post accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluent, and the containment atmosphere).

6.8.2 Deleted l

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ARKANSAS - UNIT 2 6-13 Amendment No. M,M,44,M,M,64, M, M, M, M, M,444,4M,444,449, MG M4 l

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ADMINISTRATIVE CONTROL 6.8.3 Deleted 6.8.4 The following program shall be established, implemented, and maintained:

a.

Radioactive Effluent Controls Program This program conforms 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 shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1)

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2; 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 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 10 CFR 50, Appendix I; 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 functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; ARKANSAS - UNIT 2 6-14 Amendment No. 6, M, M, M, M, M, M4, M S,444, M O, M 3

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1 ADMINISTRATIVE CONTROLS l

starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the l

specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month l

following the calendar month covered by the report.

SPECIAL REPORTS l

6.9.2 Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each report., These l

reports shall be submitted covering the activities identified below i

pursuant to the requirements of the applicable reference specification

)

l a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Deleted c.

' Deleted d.

Deleted e.

Deleted f.

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g.

Deleted l

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ARKANSAS - UNIT 2 6-16 Amendment No. M,69,M,M,MG,

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ADMINISTRATIVE CONTROLS 6.10 DELETED l

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ARKANSAS - UNIT 2 6-22 Amendment No. 60,M,'M

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ADMINISTRATIVE CONTROL 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 (DELETED) 1 ARKANSAS - UNIT 2 6-23 Amendment No. M,M,43,-73,4M,M4

ADMINISTRATIVE CONTROLS 6.12.2 (DELETED) 6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area (as defined in 20.202(b) (3) of 10 CFR 20) in which the intensity of radiation is 1000 l

mram/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted 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 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 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 i

individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.

J 6.13.2 The requirements of 6.13.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the administrative control of the shift supervisor on l

duty and/or the designated radiation protection manager.

ARKANSAS - UNIT 2 6-24 Gedee dated ^:t icr M, MM Amendment No. M,M,60,M,M,M6

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5 MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (FORINFO ONLY)

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a 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vic; D:::ident, Op::: tion: ANO-1 plant manaaer shall be responsible for overall f::ility unit _ operation and shall delegate in writing the succession to this responsibility during his absence.

3.1.2 An individual with an active Senior Reactor Operator (SRO) 13 cense shall be decianated as responsible for the control room command function while the unit is above the Cold Shutdown condition.

With the unit not above the Cold shutdown condition, an individual,with an active SRO license or Reactor Operator license shall be desianatpd as rA_sponsible for the control room command function.

6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit i

operation and corporate management, respectively.

The onsite and I

offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of rathority, 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 approrriate, in the form of organizstion charts, functional descriptions of departmental responsibilities and relationships, and job descriptions toc key personnel positions, or in equivalent forms of documentation. The:e requirements includina the unit specific titles of those personnel fulfillina its responsibilities of the positions delineated in these Technical Specifications shall be documented in the O?. M: nuel Op;;;ti:n: Safety Analysis ReLort (SAR).

b.

The 0:nc::1 M n:g::, Pl:nt Oper:ti:n: ANO-1 olant manaaer shall be l

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 Vic: D ::ident, Op::ation: ANO A specified corporate executive l

shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in oparating, maintaining, and providing technical support to the plant to ensure nuclear safety. The specified corporate executive shall be documented in the SAR.

d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

FACILITY MNII STAFF l

f 6.2.2 The M:n:g::, Op : tion: :nd Shift Sup :vi::: operations manaaer or an operations staff middle nanaaer shall hold a senior reactor operator license.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

l Amendment No. M,M,44,M,M,M, 117 M,64, M, M, M, M9, MG,-144,443,147 i

A e

l l

e o'

lic2nce..Esch en-duty chift sh=ll be compossd of et least tha minimum chift crcw camposition shewn in Tchle 6.2-1.

I l

2 l.

l l

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J Amendment No. M,M,M,M,nM, 117 M,44,4G, M, M, M9,MG, M4, MB,147 w

o..

e 6.2.2.1 Administrctiva centrols chcil ba estcblishsd to limit tha amount of evartime worksd by plant staff parforming safety-related functions. These administrative controls shall be in ac cordance with the guidance provided by the NRC Policy i

l Statement on working hours (Generic Letter 82-12).

6.3.

FACILITY STAFF QUALIFICATIONS 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for.94--the designated radiation protection l

manager, who anall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 :nd ( ' th: Shift

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cf the pl:nt f:: t::nzi:nt: :nd ::ridente.

6.4 T"'.!"!"O gggg l

S.t.1

.'. : t::ining :nd ::pl :-- nt t :ining pr:;:= f; th; unit etaff :h:11 h: nint:in:d rad:: the dir::ti:n :f the "_.: :ger,

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6.5 DELETED l

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h Amendment No. M,40,M,M,4-7, M,M, 117a 44, M, M, M, M9,444, M4, MG,444, M&,179

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l Tcble 6.2-1 ARKANSAS NUCLEAR ONE MINIMUM shirr CREW COMPOSITION #

l UNIT 1 3ICENSE COLD AND REFUELING CATEGORY ABOVE COLD SHUTDOWN SHUTDOWNS SOL 2

1*

OL 2

1 NON-LICENSED 3

1 S"!"" "'IC"!! C'.L.'.~/! SO!'

1

"::: ::q;ir:d l

'*Does not include the licensed Senior Reactor Operator or Senior Reactor Operator. Limited to Fuel Handling, supervising refueling operations after the initial fuel loading.

1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided insnediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

Additional Requirements:

1.

At least one licensed Operator shall be in the control roon when fuel is in the reactor.

2.

At least two licensed Operators shall be present in the control room during reactor _ start-up, scheduled reactor shutdown and during recovery from reactor trips.

3.

An individual qualified in radiation protection procedures shall be on. site when fuel is in the reactor.

4.

All refueling operations after the initial fuel loading shall be j

directly supervised by either a licensed Senior Reactor Operator i

or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

5.

B EEMDWhen the unit is above the Cold shutdown condition, an individual shall orovide advisory technical succort for the unit operations shift crew in the areas of thermal hydraulics. reactor enaineerina, and enant analysis with reaard to the safe operation of the unit.

Th:.s individual shall meet the cualifications specified by the Commission Pol:,cv Statement on Enaineerina Excertise on Shift.

Amendment No. M,40,M,60,4M,158 118 (Next once is naae 126) l

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6.6 P2"OP"'?2LE - r.~ :"' ?I"'IO" DELETED 1

i l

5.5.1

• ^2"CP"'?2h5 T.".J:"' ch ll h: :ny ;f th::: ;;nditi:n: Op::ifi d j

in S::ti:n 50.?? t: 10 CF" "::t 50.

f.S.2 The f:11;uing ::ti

:h:11 b: t h: f:: "2 PORTABLE-EVEN N l

? ::p::t ch:11 b; ddtt:d t: the t------1::ica pur:::nt t:

l th: ::pi nmt: cf ::ti:n 50.72 t: 10 CF" "::t 50, :nd b.

5 :h."2"CP"'?2LE r.~.2:"' ch;.11 he ::viered h-j the "50,

nd th :::;1t; Of thi; ::vi:n ch ll b; :nt;;1tted t; th; S".C l

nd th: '.'i : ":::id:nt, "p:::.t i::: ?::C.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least hot shutdown within one hour.

b.

The Nuclear Regulatory Consnirsion shall be notified pursuant to 10 CFR 50.72 and a report submitted pursuant to the requirements of 10 CFR 50.36 and Specification i

6.6.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

I The appHcM r procedures recommended in Appendix "A" of a.

Regulatory %46s 1.33, November, 1972.

b.

Refueling operations, Surveillance and test activities of safety related c.

equipment.

l l

d.

(Dr:leted) e.

(Deleted) f.

Fire Protection Program Implementation.

g.

New and spent fuel storage.

l h.

Offsite Dose Calculation Manual and Process Control i

Program implementation at the site, i.

Post accident sampling (includes sampling of reactor l

coolant, radioactive iv-lines and particulates in plant gaseous effluents, and the containment atmosphere).

6 Amendment No. 44,M,M,M,42,4%

126 M, M, M,4M, M4, MA MG,193 l

l s

6.8.2 E::h p::::dur: cf 5.9.1 25:::, 2nd ch:ng:: in intent th:::te, h:11 5: ::vi xed :nd :pp:: :d :: :: quired by th: ;?"O pric: t:

l i=pl;;;ntati:n :nd ::vi;u:d peri:dicelly :: ::t f :th in l

cdninist:stive pre:: dure:. (Deleted) 6.8.3 Ch n;:: t: p :: du::: :f 5.9.1 ch::: ::y 5: : d: :nd i=plexant:d pri : t: htnining th: ::vi:n :nd :pp::::1

q;i::d i f.f.2 zh;;; p::vid:d:

The intent f th: ::igin:1 p::::d :: i: n:t :ltered.

l E.

Th ch:ng; i: 2pp::v;d by ta; r- '::: cf the plant l

nag =ent :t:ff, :t 1:::t :n f wh: held:

S nic:

l n:::ts: Op:::ter'; lic: :: :n " nit 1.

The :heng; i; d::nn:nted, ::vi:x:d :nd :ppr:v;d :: ::quir:d by th:

0.'."O, within it d;y: cf implement:ti:n.(Deletedi 6.8.4 The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained:

l A program shall be established to implement the leakage rate testing of the reactor building au required by 10 CFR 50.54(o) and 10 CFR 50, i

Appendix J, Option B, as modified by approved exemptions. This l

program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test 6

Program," dated September 19952 The peak calculated reactor building internal pressure for the design basis loss of coolant accident, Pa, is 54 psig.

?

The maximum allowable reactor building leakage rate, La, shall be 0.20% of containment air weight per day at Pa.

l Reactor building leakage rate e.cceptance criteria is s 1.0 La.

During the first unit startup following each test performed in i

i accordance with this program, the leakage rate acceptance criteria l

are s 0.60 La for the Type B and Type C tests and s 0.75 La for Type A tests.

l The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Reactor Building Leakage Rate Testing Program.

i i

The provisions of Specification 4.0.3 are applicable to the Reactor Building Leakage Rate Testing Program.

t i

l i

Amendment No. M,M,M,M,M,M, 127 M, M, M, M9, M, MS, 4 M, MG, M6, MG,185 I

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Amendment No. M,M,118 128

7 3

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ee-: qui;r: t :: ::vi:x: ef t::t: nd :ng :in:nt: pt::::nt t: IOcEn50.50.

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n :::d: ;f ::: ting: Of th: PSC :nd th: Inc.

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n::::d: :: ::vi:x: p::f;;;;d f:: ch:ng:: 2nd: :: th: Off:it; D::: C:lcui:ti:n M:nu 1 nd 2 ::::: C: t :1 02:g 22.

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n::::d; cf th: :::vi:: liv:: f th: :::1: cf :11 hyd::ulic

it::: ;;11rril: t: Sp::ifi::ti:n 3.lf including th; dt

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in:t:ll:ti:n and : int;n:n;; :::::d.

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6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent l

with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.11 HIGH RADIATION AREA a

6.11.1

-In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10CTR20, each high radiation area (as defined in l

20.202 (b) (3) of 10CFR20) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more l

of the followings i

A radiation monitoring device which continuously indicates the a.

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 pre-set i

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 nede j

knowledgeable of them.

An individual qualified in radiation protection procedures who c.

is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.

Amendment No. M,M,H,10/2 4,'SO 129 Gedee,44, M, M, MO,M4,193

)

^

6.11.2.

i Ths rsquiremento of 6.11.1 cbava, shell cleo apply to ecch high r diaticn area in which th3 intansity of rtdiaticn is greater than 1000

'4 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into_such areas and access to these areas shall be maintained under the administrative control of the sghift agupervisor on duty l

J and/or the. designated radiation protection manager.-

1 4

4 d

i 5

i l

4 Amendment No. 44, 124 129a(Next page is 140)

-- =

=

~.

Th2 dons escignmento to various duty functions may ba estimates beced on pockOt dscimeter, TLD, or film brdga mescurements.

Small exposuros totaling 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.

{

i 6.12.2.3 Monthly Operating Report

{

Toutine reports of operating statistics which in:1 d:: ap,d shutdown experience

'll

?v:::g: 0:lly Unit r:x:: Level 44)

Op::: ting Oct: n:p :b f3} Unit Sh:td:rn: :nd 0:v;; n;d::ti: :

M)

M::::tiv Cr--

y ;f Op;;; ting inp;;ien;;

l shall be submitted on a monthly basis t: th: Dirc t :, Offic: ;f P.:::;;;.:nt 2

20555, uith : ;;;y t; th: pp :prict: n:;i:::1 Office by the fifteenth 15....th of each month following the calendar month covered by the report.

6.12.2.4 Annual Report All challenges to the pressurizer electromatic relief valve (ERV) and pressurizer safety valves shall be reported annually.

6.12.2.5 Annual Radiological Environmental Operating Report

• l The Annual Radiological Environmental Operating Report covering the operation of i

the unit during the previous calendar year shall be submitted by May 15 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 Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted in a supplementary report as soon as possible.

6.12.2.6 Radioactive Effluent Release Report **

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a.

The report shall include a surmary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.E.1.

• A single submittal may be made for ANO.

The submittal should combine those sections that are common to both units.

• • A single submittal may be made for ANO.

The submittal should combine those sections that are common to both units. The submittal shall specify the releases of radioactive material from each unit.

Amendment No. 9,G4,49,4h-74,43,88, 141 444,193

m.masM h44.3

,4 ap ssa, A. M s..@ma m a4.4.4, E A &A MtJ.d44mir.

4 4.am&.uswn A A A.ama-as A#4 Si.d A deM d4 h%g4J&a -4 4 M4A -.E

1. AJ,MSM,.4.S$ 4.4M -E-45. AC.E66.M 4M.

44_ M Ae 444-64,6m5%m.-ms+4&Me au-inWFE=*

d e e.no 4 i

f l

i I

s W OF CN ANO-2 TECHNICAL SPECIFICATIONS (FORINFO ONLY)

I J

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6.0, ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vic: rz::ident, Op:::ti : ANO-2 olant manaaer ANO shall be responsicle for overall f::ility unit _ operations and shall delegate in

(

writing the succession to this responsibility during his absence.

0.1.2 An individual with an active Senior Reactor ODerator (SRO) license _shall be desianated as responsible for the control room command function while the unit is in MODE 1, 2,

3, or 4.

With the unit not in MODE 1, 2,

3, or j

4, an individual with an active SRO license or Reactor Operator license shall be desianated as responsible for the control room command function.

l 6.2 ORGANIZATION 6.2.1 OFFSITE 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.

Lines of authority, responsibility, and communication shall be a.

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 includina the unit soecific titles of those eersonnel fulfillina its responsibilities of the positions delineated in these Technical Specifications shall be documented in the ^A ". ne:1 Op::et4eneSafety Analysis Recort (SAR).

b.

The C:n;;;l ".:n:g::, 01:nt Op:::ti:n ANO-2 clant manaaer shall be l

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 Vi : 0:::id:nt, 0;;;;ti:n: A"O._soecified corporate executive l

3 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. The soecified corporate executive shall be documented in the SAR.

d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2-FAGEM9VUNIT STAFF l

a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

j b.

At least one licensed operator shall be in the control room when fuel is in the reactor.

l ARKANSAS - UNIT 2 6-1 Amendment No. 6, M, M, M,86, M, 98,444,119

~. ~

- - ~. - --

l 4

t l

c.

At least two licznsed Oparators shall be prosant in tha control room l

during reactor start-up, ochsduled reactor shutdown end during l

recovery from reactor trips.

I d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

9 All CORE ALTERATIONS shall be directly supervised by either a

~!

[

e.

licensed Senior Reactor Operator or Senior Reactor Operator Limited to Puel Handling who has no other concurrent responsibilities during l

this operation.

t f.

BEL 59& bin MODES 1, 2, 3,

or 4, an individual shall Drovide advisory technical succort for the unit operations shift crew in the areas of thermal hydraulics, reactor enaineerina, and plant analysis with reaard j

to the safe operation of the unit.

This individual shall meet the oualifications specified by the Ccmmission Policy on Encineerina Expertise on Shift.

r g.

Administrative control shall be established to limit the amount of overtime worked by plant staff performing safety-related functions These administrative controls shall be in accordance with the t*

guidance provided by the NRC Policy Statement on working hours f

(Generic Letter No. 82-12).

h.

The Mnn:g::, ^p:::ti ;; :nd shift 2;p :vi :: soerations manaaer or an ooerations staff middle manaaer shall hold a senior reactor operator license.

l l

l l

ARKANSAS - UNIT 2 6-2 Amendment No. M, M, M, M,M, M, M,98, H4,132

~

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the designated radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 6.4 TAMMINGDELETED l

5.t.1

?. ::t :ining :nd ::p12: =;nt t :ining p :g::: f; the unit :t:ff

h:11 i: n int:in;d und:: the dirc:ti:n ;f the ";n:ger, T: ining nd En.;;;;.cy Pl:nning and :h:.11 n.;;t :: :::::d th ::quiren nt: and

ndati::: cf S::ti:n 5.5 cf ?2:S! "19.1 1971 :nd ?.ppendi

"?" cf 10 CFP 2 :t 55.

f.0.2 0 1. T50 6.5 DELETED ARKANSAS - UNIT 2 6-5 Amendment No. 6,44,44,M,

(Next once is oace 6-12a) 39,63,M,46,G4,444,444, 444,447,160

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ARKANSAS - UNIT 2 6-12a Amendment No. 4-G,160

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The Vice President, Operations ANO and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The Nuclear Regulatory Commission shall be notified pursuant to c.

10CFR50.72 and a report submitted pursuant to the requirements of 10CFR50.36 and Specification 6.6.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

The applicable procedures recommended in Appendix "A" of a.

Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

(Deleted) e.

(Deleted) f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants. These procedures should include provisions to assure that sufficient margin is maintained in CPC Type I addressable constants to avoid excessive operator interaction with the CPCs during reactor operation.

NOTE:

Modifications to the CPC software (including changes of algoritham and fuel cycle specific data) shall be performed in accordance with the most recent version of "CPC Protection Algorithm Software Change Procedure,"

CEN-39(A)-P that has been determined to be applicable to the facility. Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.

h.

New and spent fuel storage.

i.

ODCM and PCP implementation.

j.

Post accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluent, and the containment atmosphere).

6.8.2 E ch p::::dur: cf f.S.1 ch:ve, and :h ng;; in intent therets, ch ll bc ::vicued :nd pp::ved :: :: quired by th O?.M^ pri : to i=ple.; nt:ti:n :nd

vicued p icdic;11y :: ::t f::th in cdminist :tiv; p::: duceerDeleted ARKANSAS - UNIT 2 6-13 Amendment No. M, M, +3, M, M,63,

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The ch:ng: i: d:::::nted, ::vi :d nd :pp::ved :: :: quired by th: ^?.MO, withir 11 d:y: Of i=pl:;ent:ti:n 6.8.4 The following program shall be established, implemented, and j

maintained:

l a.

Radioactive Effluent Controls Program This program conforms 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 shall be contained in the CDCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1)

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, i

Appendix B, Table II, Column 2; 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; 4)

Limitarions 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 10 CFR 50, Appendix I; 5)

Detennination 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 daysi 6)

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; 7)

Limitations on the dose rate resulting from radioactive material i

released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; ARKANSAS - UNIT 2 6-14 Amendment No. 6,M,M, M,M,M,444, 449,447,440,193

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1 ADMINISTRATIVE CONTROLS I

starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-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 radiciodine limit.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis t th Oirector, Offi;; cf n ::urc; M:n:g : nt, " S. Nucle:: n:gul:tery 0;

'_ :i ca, 5::hingt:n, 0.0.

20555, uith : ;;py t; the n ;ien:1 Offic: no later than the 15th of each month

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following the calendar month covered by the report.

SPECIAL REPORTS 1

l 6.9.2 Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

I b.

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ARKANSAS - UNIT 2 6-16 Amendment No. M,40,M,M,MG, 167,191

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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 l

and adhered to for all operations involving personnel radiation exposure.

1 6.12 (DELETED) l l

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I ARKANSAS - UNIT 2 6-23 Amendment No. M,@, G,.72,4-1-6,193 i

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6.12.2 (DELETED) l 6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area (as defined in 20.202 (b) (3) of 10 CFR 20) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following A radiation monitoring device which continuously indicates the a.

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 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 responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the i

radiation work permit.

6.13.2 The requirements of 6.13.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 naem/hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the administrative control of the sshift egupervisor on l

duty and/or the designated radiation protection manager.

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l ARKANSAS - UNIT 2 6-24 Ordee dated October 24, 4-940 l

Amendment No. 41,29,60,94,94,116 l