ML20141C564

Proposed Tech Specs Changes Restoring Table 2 to Table II & Revision to One of Offsite Dose Calculation Manual, Pages Previously Submitted.Also Includes Amended Pages Modified to Amends Issued Since Change Request Submitted

ML20141C564
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/18/1997
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20141C560	List: 0CAN069705, Forwards Mods of Proposed TS Change Request Concerning Relocation of Radiological Effluent TS ML20141C564
References
NUDOCS 9706250316
Download: ML20141C564 (18)

Text

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i ANO-1 PROPOSED TECHNICAL SPECIFICATION CHANGES ~

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fp LIST OF FIGURES Number

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3.1.2 REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN LIMITATIONS 20a 3.1.2-2 REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP LIMITATIONS 20b 3.1.2-3 REACTOR COOLANT SYSTEM, NORMAL OPERATION COOLDOWN l.

LIMITATIONS 20c-3.1.9 LIMITING PRESSURE VS. TEMPERATURE FOR CONTROL ROD DRIVE OPERATION WITH 100 STD CC/ LITER H O 33 2

3.2-1 BORIC ACID ADDITION TANK VOLUME AND CONCENTRATION VS. RCS AVERAGE TEMPERATURE 35a 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE INDICATION 53a 3.5.4.2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT l

. INDICATION 53b

+

3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 3.8.1 SPENT FUEL POOL ARRANGEMENT UNIT 1 59c i

3.8.2 MAXIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION 2 STORAGE 59d l

3.'24-1 HYDROGEN LIMITS FOR ANO-1 WASTE GAS SYSTEM 110be i

4.4.2-1 NO)MALIZED LIFTOFF FORCE - HOOP TENDONS 85b 4.4.2-2 NORMALIZED LIFTOFF FORCE - DOME TENDONS 85c 4.4.2-3 NORMALIZED LIFTOFF FORCE - VERTICAL TENDONS 85d i

i 4.18.1 UPPF.R TUBE SHEET VIEW OF SPECIAL GROUPS PER SPECIFICATION l

4.18.3.a.3 110o2 l

5.4-1 ANO-1 FFSR LOADING PATTERN 116a i

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5 Amendment No. M,M,M,4M,44-3, iv 4-N,4-59, M 6, I

!;,q 6.8.5 Tha R:diozctiva Efflusnt Controls Progrcm shall be establichsd, implemented, and maintained:

This program conforum with 10 CFR 50.36a for the control of l

radioactive effluents and for maintaining the doses to raembers of the l

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:

a.

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; b.

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas cenforming to 10 CFR 20, Appendix B, Table II, Column 2; c.

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; d.

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; e.

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; f.

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 guidelinee for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; g.

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, Coluna li h.

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 10 CFR 50, Appendix I; i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and j.

Limitations on the annual dose or dose commitment to any member i

l of the public due to releases of radioactivity and to radiation j

from uranium fuel cycle sources, conforming to 40 CFR 190.

l Amendment No.

127a

0 1,,

MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) l 4

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LIST OF FIGURES Number Title Page 3.1.2-1 REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN LIMITATIONS 20a 3.1.2-2 REACTOR COOuANT SYSTEM NORMAL OPERATION-HEATUP LIMITATIONS 20b 3.1.2-3 REACTOR COOLANT SYSTEM, NORMAL OPERATION COOLDOWN LIMITATIONS 20c l

l 3.1.9-1 LIMITING PRESSURE VS. TEMPERATURE FOR CONTROL ROD DRIVE OPERATION WITH 100 STD CC/ LITER H2O 33 3.2-1 BORIC ACID ADDITION TANK VOLUME AND CONCENTRATION VS. RCS AVERAGE TEMPERATURE 35a 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE INDICATION 53a

3. 5.4. 2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT INDICATION 53b 3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 3.8.1 SPENT FUEL POOL ARRANGEMENT UNIT 1 lh 3.8.2 MAXIMUM BURNUP VS Il]JTJAL ENRICHMENT FOR REGION 2 STORAGE 59d 3.24-1 HYDROGEN LIMITS FOR ANO-1 WASTE GAS SYSTEM 110be 4.4.2-1 NORMALIZED LIFTOFF FORCE - HOOP TENDONS 85b 4.4.2-2 NORMALIZED LIFTOFF FORCE - DOME TENDONS 85c 4.4.2-3 NORMALIZED LIFTOFF FORCE - VERTICAL TENDONS 85d 4.18.1 UPPER TUBE SHEET VIEW OF SPECIAL GROUPS PER SPECIFICATION 11002 4.18.3.a.3 H0o2 b-1 --- 1

!XIMU ?.nE". ECUND*.nY FO" ".".DIO.".CTIVE RELE* SE CALCUL". TION (EXCLUSIO" 'nE*J 11-le l

l 5.2 1 l'*J!?. CEMENT OnC7J!!Z?.TIO!! O!L*.nT 119 62-2

""NCTMN"L OnC?l!!Z'.TIO" FCD PL*J T OPE!L*.TIONS 120 5.4-1 ANO-1 FFSR LO@ING PATTERN 116a Amendment No, M,-74,M,MS,444, iv 447, M9,446, l

4 6,8.5 The Radioactiv7 Effluent Controls Pro _qram shall ba_cstablished

-g, a

implemented, and maintained 1 j

This_pIqqram conforms with 10 CFR 50.36a for the control of radioactive effluents and for maintainina the doses to members of the publig_1r_om radioactive effluents as low as reasonably _ achievable.

The procram shall be contained in the ODCM, shall be impleme_ ate O y procedures, and shall include remedial actions to be taken whenever the proaram limits are exceeded.

The procram shall include the followina elements:

a.

Limitations on the functional capabjlity of radioactive lianisi and caseous monitorina instrumentation includina surveillance tests and setpoint determination in accordance with the methodoloav in the ODC_Ml b.

Limitations on the concentrations of radioactive material released in licuid ef fluents to unrestricted areas conforminJ to_10_CFR 20, App,endix B, Table II, Column 2_1 c.

Monitorina, sampJl_ing, and analysis of radigactive licuid and caseous ej fluents in accordance with 10 CFR 20.1302 and with the methodolocy_and_ parameters in the ODCML d.

Limitations on the annual and auarterly doses or dose commitment go a member of the public from radfoactive mat.erials in licuid o

eJiluests released from each unit to unrestricted areasc conformina to 10 CFR 50, Appendix Is e.

Determina_ tion of cumulative and proiected dose contributions from radioactive effluents for the current calendar cuarter and current calendar year in a nordance with the methodolocy and parameters in the ODCM at least every 31 daysj fu Limitations on the functignal capability and use of the liauid l

and caseous effluent treatment systems to ensure that

_apgr_gpriate portions of these evstems are used to reduce Leptases of radioactivity when the proiected doses in a period e

of 31 days would exceed 2% of the auidelines for the annual gigse or dose commitment, conformina to 10 CFR 50, Appendig_Il a.

Limitations on the dose rate resultina from radioactive material released in caseous effluents to areas bevond the site bounda_r_y conformina to the dose associated with 10 CFR 20, Appendix B t

Table II, Column is h.

Limitations on the_ annual and cuarterly air doses resultino I

fgom noble cases released in caseous effjuents from each unit to areas bevond the site boundary, conformina to 10 CFR 50, AJ oendix_I_

l 1.

Limitations on the annual and auarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form wi.th_ half _ liv _es > 8 d_ays_in caseous effluents released from each unit to argas beyond tbl site boundary, conforini_no to 10 CFR 50, Appendix It and L

Li Mt,ations on the anmual dose or dose commitment to any member of the public due_t_o releases of radioactivity and to Iadia_tiom frpm uranium fuel cycle sources, conformina to 40 CFA_L9_0 2

Amendment No.

127a

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l ANO-2 PROPOSED TECHNICAL SPECIFICATION CHANGES 1

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INDEX l'

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

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SECTION PAGE l

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE...............................

3/4 2-1

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3/4.2.2 RADIAL PEAKING FACTORS.........................

3/4 2-2 l

3/4.2.3 AZIMUTHAL POWER TILT...........................

3/4 2-3 7

3/4.2.4 DNBR MARGIN....................................

3/4 2-5 1

3/4.2.5 RCS FLOW RATE..................................

3/4 2-7 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE...........

3/4 2-8 3/4.2.7 AXIAL SHAPE INDEX..............................

3/4 2-9 3/4.2.8 PRESSURIZER PRESSURE...........................

3/4 2-10 i

l 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION.............

3/4 3-1 l

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................

3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...........

3/4 3-24 Seismic Instrumentation........................

3/4 3-30

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Meteorological Instrumentation.................

3/4 3-33 Remote Shutdown Instrumentation................

3/4 3-36 Post-Accident Instrumentation..................

3/4 3-39 l

l Chlorine Detection Systems.....................

3/4 3-42 3/4.3.4 TURBINE OVERSPEED PROTECTION...................

3/4 3-43 l

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ARKANSAS - UNIT 2 V

Amendment No, M, 60, W, M3, i

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INDEX l

ADMINISTRATIVE CONTROLS l

I SECTION PAGE

.i 6.6 REPORTABLE EVENT ACTION..................................

6-12 6.7 SAFETY LIMIT VIOLATION...................................

6-13 j'

6.8 PROCEDURES AND PROGRAMS..................................

6-13 l

t-6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS....................................

6-14a l

6.9.2 SPECIAL REPORTS....................................

6-16 6.9.3 RADIOACTIVE EFFLUENT RELEASE REPORT................

6-18 l

6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.

6-20 l

6.9.5 CORE OPERATING LIMITS REPORT.......................

6-21 6.10 RECORD RETENTION.......................................

6-22 6.11 RADIATION PROTECTION PROGRAM...........................

6-23 6.12 Deleted l

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6.13 HIGH RADIATION AREA....................................

6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM).................

6-25 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM...............

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l ARKANSAS - UNIT 2 XVII Amendment No. M,60,M,94,4M,M6, l

, = ~

'a A,

ADMINZSTRATIVE 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 management 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 OAMO, within 14 days of implementation.

l 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 l

effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from f

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:

l 1)

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determinarion 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 I

effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I; l

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 l

ODCM at luast 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 l

conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; l

l ARKANSAS - UNIT 2 6-14 Amendment No. 6,63,-73,66, M,98,4-14, 4M,4+7,4-60, l

l /.

ADMINISTRATIVE CONTROL 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; l

9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; 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 190.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the spplicable 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.

G.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 license conditions based on other commitments shall be I

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 l

startup test program, and resumption or commencement of commercial power l

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

i.

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4 ARKANSAS - UNIT 2 6-14a Amendment No. 6, M,M, M,M,M,M4, MG,447, MO,

/

MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FORINFO ONLY) l

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._.m.

...___.m F

, {.,

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l

3/4.2 POWER DISTRIb'JtIt LIMITS 3/4.2.1 LINEAR HEAT RATE...............................

3/4 2-1 3/4.2.2 RADIAL PEAKING FACTORS.........................

3/4 2-2 3/4.2.3 AZIMUTHAL POWER TILT...........................

3/4 2-3 3/4.2.4 DNBR MARGIN....................................

3/4 2-5 3/C.2.5 RCS FLOW RATE..................................

3/4 2-7 3/4.2.6-

' REACTOR COOLANT COLD LEG TEMPERATURE...........

3/4 2-8 l

3/4.2.7 AXIAL SHAPE INDEX..............................

3/4 2-9 3/4.2.8 PRESSURIZER PRESSURE...........................

3/4 2-10 3/4.3 INSTRUMENTATIOli, 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION.............

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................

3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentatior............

3/4 3-24 Seismic Instrumentation........................

3/4 3-30 Meteorological-Instrumentation.................

3/4 3-33 Remote Shutdown Instrumentation.....

3/4 3-36 Post-Accident Instrumentation..................

3/4 3-39 Chlorine Detection Systems.....................

3/4 3-42 3/4.3.4 TURBINE CVERS PEED PROTECTION...................

3/4 3-43 Fire Detection In:trumentation 3/t 3-t3 "cdicactiv: C:::cus Eff1uent Me.Re*+ng

.-.., m, 3 / '. 3 - '. 5 In:trument: tion ARKANSAS - UNIT 2 V

Amer dment No. 24,60,M4,M3,

I 4

W

. i, INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTION..................................

6-12 6.7 SAFETY LIMIT VIOLATION.......................

6-13 6.8 PROCEDURES AND PROGRAMS..................................

6-13 l

I 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS....................................

6-14a, l

6.9.2 SPECIAL REPORTS....................................

6-15 6.9.3 GEMIANNUAL-RADIOACTIVE EFFLUENT RELEASE REPORT.....

6-18 l

6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAJ OPERATING REPORT.

6-20 6.9.5 CORE OPERATING LIMITS REPORT.......................

6-21 6.10 RECORD RETENTION.......................................

6-22 6.11 RADIATION PROTECTION PROGRAM...........................

6-23 6.12 DeletedENVI-RONMENT.*I. OL'*I.IFIC*.T!ON.

5 23 l

6.13 HIGH RADIATION AREA....................................

6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM).................

6-25 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM...............

6-26 I

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ARKANSAS - UNIT 2 XVII Amendment No, M,60,M,94,W,4M,

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

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

,(,

ADMINISTRATIVE CONTROL 6.8.3 Changes to procedures of 6.8.1 above may b'e 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

. ant management L

staff, at least one of whom holds a Senior Reactor Operator's License on Unit 2.

i L

c.

The change is documented, reviewed and approved as required by 1

the QAMO, within 14 days of implementation.

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

a.

Radioactive Effluent Controls Procram This proaram conforms with 10 CFR 50.36a for the c.ontrol of radioactlye i

ef fluents and for maintainina the doses to MEMBERS OF THE PUBLIC from radioactive effluents _as_)ow as reasonably achievable.

The procram sh_all be contained in the'ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the procram ligigs gre exceeded.

The procram shall include the followino elements:

1)

Limitations on the functional capability _of_ radioactive liauid and o

gaseous monitorina instrumentation includtna surveillance tests and setooint determination in accordance wi.th the methodoloav in the ODCM; 2)

Limitations on the cancentIations of radioactive material released in liauid effluents to UNRESTRICTED AREAS conformina to 10 CFR Part 20, ggoendix B, Table II, Column 2; 3)

Monitorina, samplina, and analysis of radioactive licuid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodoloav and paramsters in the ODCM; 4)

Limitations on the annual and ouarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioact.1ve materials in-licuid effluents released from each unit to UNRESTRICTED AREAS, conformina to 10 CFR 50, Appendix I; 5)

Determination of cumulative and croiected dose contributions from radioactive effluents for the current calendar cuarter and current 5

calendar year in accordance with the methodoloav and parameters in the OpCM at least eve.tv 31 days; 6)

Limitations on the functional capability and use of the liauid and gaseous effluent treatment systems to ensute that applopriate pottiions o

of.these systems are used to reduce releases of radioactivity when the gro1ected doses in a period of 31 days would exceed 2% of the guidelin.es for t he annual dose or dose cuamitment, conformina to R CFR 50 Appencix il 7)

Limitations on the dose rate resultina from radioactive material released in caseous effluents to areas beyond the site boundary conformine to the dose associated with 10 CFR 20, Appendix B, Table IIA Column 17 ARKANSAS - UNIT 2 6-14 Amendment No. 6, M,-7-3, M, M, M, M4, M9, M-h MO,

..1_

i ADMINZSTRATIVE CONTROL 8)

Limitations on the annual and cuarterly air doses resultina from noble cases released in caseous effluents from each unit to areas 3evond the site boundary, conformina to 10 CFR 50, Appendix I 9)

Limitations on the annual and auarterly doses to a MEMBER OI_IBE EUBLIC from iodine-131 _ lodine-133, tritium, and all radionuclides in t

particulate form with half lives > 8 days in caseous ef fluents released from each unit to areas bevond the site boundarv, conformina to 10 CFR 50. Appendix Is and 10)

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLMC due to. releases of radioactivity and to radiation from u_ranium fue?. cycle sources, conformina to 40 CFR 190.

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 license 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.

ARTMSAS - UNIT 2 6-14g Amendment No. 6, M, M, M, M, M,444, l

4%, W, %9,

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DRAFT REVISION OF THE ODCM WITH CHANGES INCORPORATED (FOR INFO ONLY) i (The proposed change to the this draft revision to the ODCM have been included to assist in the review process.

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4 l4 LICENSE.075 Page 100 Rev.RETS 6.8.4 The following program shall be established, implemented, and maintained:

a.

Radioactive Effluent Controls Program (Refer to Unit 1 Technical Specification 6.8.5.)

b.

Radiological Environmental Monitoring Program l

l A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative, measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in l

this manual, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

l

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in this manual, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are l

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

census, 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.

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