ML20117G760

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Proposed Tech Specs Re Conversion of Design Features Section
ML20117G760
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/23/1996
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20117G753 List:
References
NUDOCS 9609050317
Download: ML20117G760 (30)
v • d • e


Text

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, INDEX DESIGN FEATURES SECTION PAGE l 5.1 Site I.ocation................................................. 5-1 l l l

5.2 Reactor Core.................................................. 5-1 l !

5.2.1 Fuel Assemblies........................................ 5-1 l 3 5.2.2 Control-Element Assemblies............................. 5-1 l 5.3 ' Fuel Storage.................................................. 5-2 l

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5.3.1 Spent Fuel Storage Rack Criticality.................... 5-2 l l l

5.3.2 New Fuel Storage Rack Criticality...................... 5-2 -

l 5.3.3 Drainage............................................... 5-2 l ,

5.3.4 Capacity............................................... 5-2 l I i L

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l 9609050317 960823 PDR ADOCK 05000368 P PDR i

ARKANSAS - UNIT 2 XV Amendment No. 60,

i RADICACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS

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DOSE RATE LIMITING CONDITION FOR OPERATION 1

3.11.2.1 The dose rate.due to radioactive materials released in gaseous  ;

effluents from the site to UNRESTRICTED AREAS (see ODCM Figure 4-2) shall l i be limited to the following: '

a. For noble gases: Less than or equal to the 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
b. For iodine-131, for tritium and for all radionuclides in particular form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

During periods of containment purging the dose rate may be averaged over a one hour interval.

APPLICABILITY: At all times.

l ACTION:

a. With the dose rate (s) exceeding the above limits, without delay restore the release rate to comply with the above limit (s),
b. The provisions of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and l procedures'of the ODCM, 4.11.2.1.2 The dose rate due to iodine-131, tritium, and all radionuclides 1 in particulate form with half-lifes greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

l ARKANSAS - UNIT 2 3/4 11-7 Amendment No. 60,M,M4,

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, RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The dose due to noble gases released in gaseous effluents from ANO-2 to UNRESTRICTED AREAS (see ODCM Figure 4-2) shall be: l a During any calendar quarter, less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year, less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.
b. The provisions of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

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ARKANSAS - UNIT 2 3/4 11-10 Amendment No. 40,M,H4,

, RADIOACTIVE EFFLUENTS DOSE - IODINE-131, TRITIUM, AND RADIONUCLIDFS IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 T ' he dose to a MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from ANO-2 to UNRESTRICTED AREAS (see ODCM Figure 4-2) shall be: l

a. During any calendar quarter, less than or equal to 7.5 mrems to any organ, .and
b. During any calendar year, less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131,. tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above lindts, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.
b. The provisions of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.

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1 ARKANSAS - UNIT 2 3/4 11-11 Amendment No. 60,M,94,M4, l

c RADXOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION ]

3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be used to re' duce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses from ANO-2 to UNRESTRICTED AREAS (see ODCM Figure 4-2) would exceed .625 mrad for gamma radiation and 1.25 mrad for l ,

beta radiation in any calendar quarters or when the projected doses due to iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days would exeSed 1.0 mrem to any organ over a calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.
b. The provisions of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.

i ARKANSAS - UNIT 2 3/4 11-12 Amendment No. 60,M,94,M4,

. RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 When degasifying the reactor coolant system, the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive material in gaseous waste prior to their discharge when the projected gaseous effluent doses )

for ANO-2 to UNRESTRICTED AREAS (see ODCM Figure 4-2) would exceed .625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar l )

quarter.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.

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b. The provisions of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least cace per 31 days in accordance with the ODCM.

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ARKANSAS - UNIT 2 3/4 11-13 Amendment No. 60,G1,94,444,

., 5.0 DESIGN FEATURES 5.1 Site Location The site for Arkansas Nuclear One is located in Pope County, Arkansas on the north bank of the Dardanelle Reservoir (Arkansas River), approximately 6 miles west-northwest of Russellville, AR. The exclusion area boundary shall have a radius of 0.65 statute miles from the center of the reactor.

5.2 Reactor Core 5.2.1 Fuel Assemblies The reactor shall contain 177 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2 ) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel refety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. Other cladding material may be used with an approved exemption.

5.2.2 Control' Element Assemblies The reactor core shall contain 81 control element assemblies.

ARKANSAS - UNIT 2 5-1 Amendment No.

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

g DESIGM FERTURES 5.3 Fuel Storage 5.3.1. Spent Fuel Storage Rack Criticality The spent fuel storage racks are designed and shall be maintained l with:

a. Fuel assemblies stored in the_ spent fuel pool in accordance ]

L with Specification 3.9.12; t

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b. k.rr 5 0.95 if fully flooded with unborated water, which l

, includes an allowance for uncertainties as described in '

-Section 9.1 of the SAR; and 1

, c. A nominal 9.8 inch center to center distance between fuel '

assemblies placed in the storage racks.

( 5.3.2 New Fuel Storage Rack Criticality l

I The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.1 weight percent;
b. kerr s 0.95 if fully flooded with unborated water, which 1 includes an allowance for uncertainties as described in I Section 9.1 of the SAR;
c. k.cr 5 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the SAR; and
d. A nominal 25 inch center to center distance between fuel assemblies placed in the storage racks.

5.3.3 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 399' 104".

5.3.4 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 988 - fuel assemblies.

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f ARKANSAS - UNIT 2 5-2 Amendment No. G4,71,96,

ADMINISTRATIVE CONTROL  !

6.8.3 Changes to procedures of 6.8.1 above umy be made and implemented prior to obtaining the review and approval required in 6.8.2 above provided:

a. The intent of the original procedure is not altered,
b. The change is approved by two members of the plant management ,

staff, at least one of whom holds a Senior Reactor Operator's  !

License on Unit 2. j

c. The change is documented, reviewed and approved as required by the QAMO, within 14 days of implementation.

6.8.4 The following program shall be established, implemented, and -

maintained:  ;

a. Component Cyclic or Transient Limit This program provides controls to track the SAR Section 5.2.1.5 j cyclic or transient occurrences to ensure that components are i ma'ntained

. within the design limits.

6.9 REPORTING REQUIREMENTS l 1

ROUTINE REPORTS I I

6.9.1 In addition to the applicable reporting requirements of Title 10, j Code of Federal Regulations, the following reports shall be submitted to l the Administrator of the Regional Office unless otherwise noted.  ;

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.- Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific j details required in license conditions based on other commitments shall be j included in this report.  !

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of j star *.up test program, and resumption or commencement of commercial power '

operation), supplementary reports shall be submitted at least every three j months until all three events have been completed.

ARKANSAJ - UNIT 2 6-14 Amendment No. 6,64,M,86,M,98,M4, M9,444, MO,

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, ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, ]

Code of Federal Regulations, the following records shall be retained for at 4 least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.
b. Records and logs of principal maintenance activities, inspections, ,

repair and replacement of principal items of equipment related to nuclear safety. ,

c. All REPORTABLE EVENTS.

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d. Records of surveillance activities, inspections and calibrations  ;

required by these Technical Specifications.

e. Records of changes made to the procedures required by ,

Specification 6.8.1.

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~f. Records of radioactive shipments,

g. Records of sealed source and fission detector leak tests and results,
h. Records of annual physical inventory of all sealed source material of record.

l 6.10.2 The following records shall be retained for the duration of the Facility Operating Licenses

a. Records and drawing changes reflecting unit design modifications i made to systems and equipment described in the Final Safety l Analysis Report.

b.. Records of new and irradiated fuel inventory, fuel transfer and assembly burnup histories.

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 in the Component Cyclic or Transient Limit program required by Specification 6.8.4.

ARKANSAS - UNIT 2 6-22 Amendment No. 60,G1,94,

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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS

(FORINFO ONLY) h l

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  • 1 c TNDEX i DESIGN FEATURES J

f SECTION PAGE [

t 5.1 64@ESite Location............................................ 5-1 l i "xclu icn .'.:::. . . . 51 .

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5.42 REAGTGR-GARERe a c t o r Co r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 l 5.2.1 Fuel Assemblies......................................... 5-41 l l 5.2.2 Control Element Assemblies............................. 5-41 l l

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. . . ,. Fuel Storage..................................... 5-2 5.3.1 Critic:lity Spent Fuel Storage Rack Criticality....... 5-62 l !

5.3.2 Criticality New Fuel Storage Rack Criticality......... 5-62 l l t

5.3.3 Drainage............................................... 5-62 l !

5.3.4 Capacity............................................... '5-62 l f

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l ARKANSAS - UNIT 2 XV Amendment No. 40,

e

, RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE j LIMITING CONDITION FOR OPERATION i

3.11.2.1 The dose rate due to radioactive materials released in gaseous )

effluents from the site to UNRESTRICTED AREAS (see ODCM Figure 2i_2b-1--3) shall be l limited to the following:

a. For noble gases: Less than or equal to the 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
b. For iodine-131, for tritium and for all radionuclides in particular form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

During periods of containment purging the dose rate may be averaged over a one hour interval.

APPLICABILITY: At all times.

ACTION: l 1

4 a. With the dose rate (s) exceeding the above limits, without delay I restore the release rate to comply with the above limit (s). )

)

, b. The provisions of Specificatione 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above 'lind ts in accordance with the methods and procedures of the ODCM.

4.11.2.1.2 The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half-lifes greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

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ARKANSAS - UNIT-2 3/4 11-7 Amendment No. 60,M,-144,

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

, RADIOACTIVE EFFLUENTS j DOSE - NOBLE GASES i LIMITING CONDITION FOR OPERATION l

3.11.2.2 The dose due to noble gases released in gaseous effluents from ANO-2 to UNRESTRICTED AREAS (see ODCM Figure Mb4-3) shall be: l

  • a During any calendar quarter, less than or equal to 5 mrads for 2

gamma radiation and less than or equal to 10 mrads for beta -

radiation, and 1

] b. During any calendar year, less than or equal to 10 mrads for i gamma radiation and less than or equal to 20 mrads for beta radiation.

r APPLICABILITY: At all times.

-! ACTION:

t

! a. With the calculated dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days t l 3 b. The provisions of Specificatione 3.0.3 are not applicable. l i

j SURVEILLANCE REQUIREMENTS i

4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calcndar year shall be determined in accordance with the ODCM at least once per 31 days.

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ARKANSAS - UNIT 2 3/4 11-10 Amendment No. 60,M,H4,

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

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RADIOACTIVE EFFLUENTS i

DOSE - IODINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM l

, LIMITING CONDITION FOR OPERATION l

~

3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-13,1, from tritium, and from all radionuclides in particulate form with half-lives greater than l 8 days in gaseous effluents released from ANO-2 to UNRESTRICTED AREAS (see ODCM Figure 4-26v1-3) shall be: l ,

a. During any calendar quarter, less than or equal to 7.5 mrems to any organ, and
b. During any calendar year, less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater t than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.
b. The, provisions of Specificatione 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS F 4.11.2.3 Dose calculations. Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.

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l ARKANSAS - UNIT 2 3/4 11-11 Amendment No. 60,M,94,H4,

f

, RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION l 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be used to reduce i

radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses from ANO-2 to UNRESTRICTED AREAS (see EFigure 3 ,26,4-3) would exceed .625 mrad for gamma radiation and 1.25 mrad l for beta radiation in any calendar quarter; or when the projected doses due to iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days would exceed 1.0 mrem to any organ over a calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report, submit a Special Report pursuant to Specification 6.9.2.h within 30 days.
b. The provisions of Specificatione 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.

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ARKANSAS - UNIT 2 3/4 11-12 Amendment No. 60,M,G4,444,

. i

, RADIOACTZVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 When degasifying the reactor coolant system, the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive material in gaseous i waste prior to their discharge when the projected gaseous effluent doses for ANO-2 to UNRESTRICTED AREAS (see ODCM Figure 4-2&r-1---3) would exceed .625 mrad l for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report, submit a l Special Report pursuant to Specification 6.9.2.h within 30 days. ,

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b. The provisions of Specificatione 3.0.3 are not applicable. l l

SURVEILLANCE REQUIREMENTS 1

1 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected  ;

at least once per 31 days in accordance with the ODCM.

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l ARKANSAS - UNIT 2 3/4 11-13 Amendment No. 60, M,94, 34,

. 5.0 DESfGN FEATURES l 1

5.1 S17E11e Location l l The site for Arkansas Nuclear One is located in Pope County, Arkansas on the north bank of the Dardanelle Res,ervoir (Arkansas River), approximately )

6 ndles west-northwest of Russellville, AR. The exclusion area boundary shall have a radius of 0.65 statute miles from the center of the reactor.

EXCLUSION AREA l i

5.1.1 The enclusion :::: ch:11 bc :: hern in Figu : 5.1 - 1. l LOW POPULAT!C" 20"E l 5.1.2 The leu p;pulation :en ch:11 bc : chaun in Figure 5.1 2. l ,

5.2 GGNTAJMMENTEeactor Core l 4

5,2.1 Fuel Assemblies j J

The reactor shall contain 177 fuel assemblies. Each assembiv shall consist of a matrix of zircalov or ZIRLO clad fuel rods with an initial composition of natural or slichtly enriched uranium dioxide (UO,) as f tel material. Limited substitutions of zirconium allov or stain 1rms steel filler rods for fuel rods, in accordance with I approved applications of fuel rod confiaurations, may be used. Fuel assemblies shall be limited to those fuel deslans that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety desian ]

bases. A limited number of lead test assemblies that have not completed representativo testine may be placed in non-limitina core recions. Other claddina material may be used with an approved exemption.

5.2.2 Control Element Assemblies The reactor core shall contain 81 control element assemblies.

OO"FICUnATIO" 5.2.1 The ::::ter containment building i: : : teel lined, ::infereed j eenc::t building of cylindrie:1 sh pe, with : dem: ssf and having th: <

following d::ign featurc:;

c. "c=in:1 incide dia=:ter - 115 feet.

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c. "ini=un-thi ckne s: Of concret x 11: - 3 . 7 5 f; t-v j
d. "inimur thickne:: ef ceneret: : sf - 3.25 fectw j
. "inimur thicknes: Of concrete f1:0: pad - 9 feet, eneepb at th: cump wh :: th mini =ur thickne:: is 5 feet.

f " =inal thickne:: ef steel liner - 0.25 inch :.

g. ":t f::: volume - 1.70 n 10' cubic feet.

ARKANSAS - UNIT 2 5-1 Amendment No.

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ARKANSAS - UNIT 2 5-2

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'5.3' Fuel Storage 5.3.1 Spent Fuel Storage Rack Criticality.

The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies stored in the spent fuel pool in accordance with Specification 3.9.12.

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b. kort s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the SAR; and
c. A nominal 9.8 inch center to center distance between fuel  ;

assemblies placed in the storage racks.

5.3.2 New Fuel Storage Rack Criticality The new fuel storage racks are designed and shall be maintained with:

j a. Fuel assemblies having a maximum U-235 enrichment of 4.1 weight I percent;

\ h. k.tr s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in

-Section 9.1 of the SAR;

c. keer s 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of I the SAR; and
d. A nominal 25 inch center to center distance between fuel assemblies placed in the storage racks.

5.3.3 Drainage f

l The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 399' 104".

5.3.4 capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 988 fuel assemblies.

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[ ADMINISTRATIVE CONTROL 6.8.3 Changes to procedures of 6.8.1 above may be made and implemented prior to obtaining the review and approval required in 6.8.2 above provided:

a. The intent of the original procedure is not altered,
b. The change is approved by two members of the plant nanagement staff, at least one of whom holds a Senior Reactor Operator's License on Unit 2.
c. The change is documented, reviewed and approved as required by the QAMO, within 14 days of implementation.

6.8.4 The followina proaram shall be established, implemented, and maintained:

a. Component Cvelic or Transient Limit This orocram provides controls to track the SAR Section 5.2.1.5 cyclic or transient occurrences to ensure that components are maintained within the desian limits.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following reports shall be submitted to the Administrator of the Regional Office unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6. 9.1. 2. The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in licence conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ARKANSAS - UNIT 2 6-14 Amendment No. 6,M,M, M,M,M,4M, 4%, M4, MO,

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i y' ADMINISTRATIVE CONTROLS  ;

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6.10 RECORD RETENTION f l

In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at {

least the minimum period indicated.  !

6.10.1 The following records shall be retained for at least five years:

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a. Records and logs of unit operation covering time interval at each  ;
j. power level.

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l b. Records and logs of principal maintenance activities, inspections,  !

l repair and replacement of principal items of equipment related to i j nuclear safety.  ;

i

, c. All REPORTABLE EVENTS.

, d. Records of surveillance activities, inspections and calibrations

required by these Technical Specifications. '

r

e. Records of changes made to the procedures reguired by l

-Specification 6.8.1.

f. Records of radioactive shipments. ,
g. Records of sealed source and fission detector leak tests and results.
h. Records of annual physical inventory of all sealed source material r of record.  ;

i 6.10.2 The following records shall be retained for the duration of the i Facility Operating License:

a. Records and drawing changes reflecting unit design modifications i made to systems and equipment described in the Final Safety >

Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfer and assembly burnup histories.
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 in the Component Cvelic or Transient Limit procram reouired by Specification 6.8.4.ide.;tified i.- T:ble 5.'.l. ,

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ARKANSAS - UNIT 2 6-22 Amendment No. 40,M,94,

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