Text

Proposed Tech Spec Changes Re Verification of Transient Analysis code,CESEC-III & Spent Fuel Pool Expansion
	ML20215E835
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/12/1986
From:	; ARKANSAS POWER & LIGHT CO.
To:	;
Shared Package
ML20215E819	List: 2CAN128601, Proposed Tech Spec Changes Re Verification of Transient Analysis code,CESEC-III & Spent Fuel Pool Expansion; ML20215E814;
References
	2CAN128601, NUDOCS 8612230135
	Download: ML20215E835 (28)
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8612230135 861212 PDR ADOCK 05000360 P PDR 2CAN128681

, INDEX.

ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N..................................... 6-12 6.7' SAFETY LIMIT VIOLATION...................................... 6-13 6.8 PROCEDURES.................................................. 6-13 6.9 REPORTING REQUIREMENTS 6.9.1' ROUTINE REP 0RTS........................................ 6-14 6.9.2 SPECIAL REP 0RTS........................................ 6-19

6. 9. 3 ' SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT......... 6-19a l 6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENT OPERATING REPORT....... 6-21 6.10 RECORD RETENTION........................................... 6-22 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-23 6.12 ENVIRONMENTAL QUALIFICATION................................ 6-23 6.13 HIGH RADIATION AREA........................................ 6-24 6.14 ~OFFSITE DOSE CALCULATION MANUAL (0DCM)..................... 6-25

{ ARKANSAS - UNIT 2 XVII Amendment No. 2I, 60 i

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REACTIVITY CONTROL SYSTEMS MODERATE TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:

a. Less positive than 0.5 x 10- Ak/k/*F, whenever THERMAL--POWER is

$70% of RATED THERMAL POWER.

b. Less positive than 0.0 Ak/k/*F whenever THERMAL POWER'IS >70% of

-RATED THERMAL POWER, and

c. Less negative than -3.4x10 Ak/k/*F at RATED THERMAL POWER.

APPLICABILITY: MODES 1 and 2*# l

(' ACTION:

With the moderator temperature coefficient outside any one of the above

limits, be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.1.4.1 The MTC shall be determined to be within its limits by i confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with.the above limits.

t 4.1.1.4.2 The MTC shall be determined at the following frequencies and

{' THERMAL POWER conditions during each fuel cycle:

! a. Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.

- b. At any THERMAL POWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 800 ppm.

c. At any THERMAL POWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 300 ppm.

With K,7f21.0.

See Special Test Exception 3.10.2. l ARKANSAS - UNIT 2 3/4 1-5 Amendment No. 24, 85

e-t REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA drop time,

.from a fully withdrawn position, shall be 5 3.0 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

a. T,yg 2 525 F, and

b. All_ reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With the drop time of any full length CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2.

b. With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:

a. For all CEAs following each removal of the reactor vessel head,

b. For specifically affected individual CEAs following any l maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and

c. At least once per 18 months.

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l ARKANSAS - UNIT 2 3/4 1-23 AMENDMENT NO.

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s PEACTIVITY CONTROL SYSTEMS PART LENGTH CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.7 The part length CEA group shall be limited to the insertion limits shown on, Figure 3.1-3 with PLCEA insertion between the Long Term Steady State Insertion Limit and the Transient Insertion Limit restricted to:

a. 5 5 Effective Full Power Days per 30 Effective Full' Power Day interval, and

b. 5 14 Effective Full P0wer Days per calendar year.

APPLICABILITY: MODE 1*.

ACTION:

a. With the part length CEA groups inserted beyond the Transient Insertion Limit, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either:

1. Restore the part length CEA group to within the limits, or

12. Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the PLCEA group position using Figure 3.1-3.

b. With the part length CEA groups inserted between the Long Term Steady State Insertion Limit and the Transient Insertion Limit for intervals > 5 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, either:

1. Restore the part length group to within the Long Term Steady State Insertion limits within two hours, or

2. Be in at least HOT STANDBY'within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENT 4.1.3.7 The position of the part length CEA group shall be determined to be within the Transient Insertion Limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The accumulated time during which the part length CEA group is inserted beyond the Long Term Steady State Insertion Limit but within the Transient Insertion Limit shall be determined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See Special Test Exception 3.10.2. l ARKANSAS - UNIT 2 3/4 1-28 AMENDMENT NO. 37 l

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REACTOR COOLANT SYSTEM.

SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. $ 1.0 pCi/ gram DOSE EQUIVALENT I-131, and

b. $ 100/E pCi/ gram.

APPLICABILITY: MODES 1, 2, 3, 4, and 5. -

ACTION:

MODES 1, 2 and 3*:

, a. With the specific activity of the primary coolant > 1.0 pci/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T,yg (500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific activity of the primary coolant > 100/E pCi/ gram, be in at least HOT STANDBY T,yg (500 F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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ARKANSJE - UNIT 2 3/4 4-18 AMENDMENT NO.

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y REACTOR COOLANT SYSTEM (ACTION: (Continued)

MODES 1, 2, 3, 4, and 5:

c. With the specific activity of the primary coolant > 1.0 pCi/ gram DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-4 until the

specffic activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

' s ARKANSAS - UNIT 2 3/4 4-19 AMENDMENT NO.

4,6.2.1 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENT (Continued)

c. At least once per 18 months, during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on CSAS and RAS test signals.

2. Verifying that upon a RAS test signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established. l

3. Verifying that each spray pump starts automatically on a CSAS test signal.

d. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

U ARKANSAS - UNIT 2 3/4 6-11 AMENDMENT NO.

S; ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Verifying the diesel starts from ambient condition. on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the

-auto-connected shutdown loads through the time delay relays and operates for > 5 minutes while its generator is loaded with the shutdown loads.

6. Verifying that on an ESF actuation test signal (without loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for > 5 minutes.

7. Deleted 1 8. Simulating a loss of offsite power in conjunction with an ESF actuation test signal, and E _a) Verifying de-energization of the emergency busses and load shedding from the emergency busses, b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected emergency (accident) loads through the 4

load. sequencer and operates for > 5 minutes while its generator is loaded with the emergen'cy loads.

. . c) Verifying that all diesel generator trips, except engine overspeed, lube oil pressure, and generator j differential, are automatically bypassed upon a Safety Injection Actuation Signal.

9. Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to 3135 Kw and during the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded l . to 2850 Kw. Within 5 minutes after completing this 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test, repeat Specification 4.8.1.1.2.c.5. l l

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l l ARKANSAS - UNIT 2 3/4 8-4 AMENDMENT NO. 56

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ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.3 As a minimum, the following D.C. electrical sources shall be OPERABLE:

TRAIN "A" consisting of 125-volt D.C. bus No. 1, 125-volt D.C. battery bank No. 1 and a full capacity charger.

TRAIN "B" consisting of 125-volt D.C. bus No. 2, 125-volt D.C. battery bank No. 2 and a full capacity charger.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With one of the required battery banks inoperable, restore the inoperable battery bank to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b, With one of the required full capacity chargers inoperable, demonstrate the OPERABILITY of its associated battery bank by performing Surveillance Requirement 4.8.2.3.a.1 within one hour l and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. If any Category A limit in Table 4.8-2 is not met, declare the battery inoperable.

SURVEILLANCE REQUIREMENTS 4.8.2.3. Each 125-volt battery bank and charger shall be demonstrated l OPERABLE:

a. At least once per 7 days by verifying that:

1. The parameters in Table 4.8-2 meet the Category A LIMITS, and

2. The total battery terminal voltage is greater than or equal to 129 volts on float charge for a 60 cell battery bank and greater than or equal to 124.7 volts on float charge for a 58 cell battery bank.

b. At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110 volts, or battery overcharge with battery terminal voltage above 150 volts, by verifying that:

1. The parameters in Table 4.6-2 meet the Category B LIMITS,

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! ARKANSAS - UNIT 2 3/4 8-8 AMENDMENT NO. 54, 75

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~ELECTICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall

.be energized and OPERABLE:

1 - 125-volt D.C. bus, and 1 - 125-volt battery bank and charger supplying the above D.C. bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. bus shall be determined OPERABLE and energized at .least once per 7 deys by verifying correct breaker alignment and indicated power availability.

4.8.2.4.2 The above required 125-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3. l 4

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i ARKANSAS - UNIT 2 3/4 8-10 AMENDMENT NO.

TABLE 4.11.2 (Continued)

TABLE NOTATION L a. The Lower' Limit of Detection.(LLD) is' defined in Table-Notation a. of

. Table __4.11-1 of Specification 3.11.1.1.

b. The principal gamma emitters for which:the LLD specification will apply Lare exclusively the following radionuclides: .Kr-87, Kr-88, Xe-133,

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Xe-133m,1Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58,' _ Co-60, _ Zn-65, ~ Mo-99,7 Cs-134, Cs-137, Ce-141 and.Ce-144 for

, -particulate emissions. .This list does not mean that only these nuclides are to be detected and reported. Other peaks which are-measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for

the. analyses-should not be reported as being present at the LLD level

-for'that nuclide. When unusual circumstances result in LLD's higher than required, the. reasons shall be documented in the Semiannual , j --

Radioactive Effluerit Release Report.

c. Tritium grab sampler shall be taken_from the Reactor Building ventilation exhaust at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

d. Tritium grab samples shall-be taken at least once per 7 days from the ventialtion exhaust.from the spent fuel area, whenever spent fuel is in the spent fuel pool.

e. The ratio fo the sample flow rate to the sampled stream flow rate shall' Lbe known for the time ~ period covered by each dose or dose. rate calculation made in accordance with Specification 3.11.2.1, 3.11.2.2, and 3.11.2.3.

f. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after-changing (or after removal'from the sampler).

g. .For certain radionuclides with low gamma yield or low energies, or.for-certain radionuclide, mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inversely proportional to the magnitude of the gamma yield (i.e., 1 x E-4/I, where I is the photon abundance expressed as a decimal' fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be

-greater than 10% of the MPC value specified in 10 CFR 20,' Appendix B, Table II, Column I.

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(2-e' ARKANSAS - UNIT 2 3/4 11-9 AMENDMENT NO. 60 a

RADIOACTIVE EFFLUENTS DOSE - 10 DINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The 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 Figure 5.1-3) shall be: I

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 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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 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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b ARKANSAS - UNIT 2 3/4 11-11 AMENDMENT NO. 60

s RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE-TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be used to reduce l radioactive materials in gaseous waste prior to their discharge when.the projected gaseous effluent doses from ANO-2 to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed .625 mrad for gamma radiation and 1.25 mrad for. l

- 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 Specifications 3.0.3 and 3.0.4 are not applicable.

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

' RADI0 ACTIVE 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 Figure 5.1-3).would exceed .625 mrad for l

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 treatnent 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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 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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ARKANSAS - UNIT 2 3/4 11-13 AMENDMENT NO. 50

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERA's _0N 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden

of greater _than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) which yields a calculated dose commitment due to I-131, tritium, and radio-nuclides in particulate form greater than the values currently being calculated in Unit 2 Specification 4.11.2.3, submit lo-cation description in the Semiannual Radioactive Effluent Release Report per Specification G.9.3.

b. With a land use census identifying a location (s) which yields a calculated dose commitment (via the sample exposure pathway) greater than at a location from which samples are currently being obtained in accordance with the Specification 3.12.1, identify the new location in the Semiannual Radioactive Effluent Release Report per Specification 6.9.3. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The sampling location having the lowest calculated dose commitment (via the same exposure pathway) may be deleted from this monitoring program aftor October 31 of the year in which this land use census was conducted.

c. The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 by door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the land use census shall be included in the Annual Radiological Environment Report.

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Broad Leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

ARKANSAS - UNIT 2 3/4 12-8 AMEN 0 MENT NO. 60

P ' REACTOR COOLANT - SYSTEM '

. BASES steam generator tube rupture accident in conjunciton with an assumed steady state primary-to-seconary. steam generator. leakage rate of 1.0 GPM.and a-concurrent loss of offsite. electrical power. 'The values for the limits on'

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specific: activity represent interim limits based upon a parametric evaluation by.the NRC of typical site _ locations. .These values are-U conservative in thet specific site parameters.of the Arkansas Nuclear One

, ' site, such as' site boundary location and meteorological conditions, were not

considered-in this evaluation. The NRC is finalizing site. specific criteria which will be used as the basis for the reevaluation of the specific

, activity limits of this site. This reevaluation may result.in higher j- limits.

The ACTION statement permitting POWER OPERATION to continue for limited time ,

1 periods with the primary coolant's specific activity > 1.0 pCi/ gram DOSE

-EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following

changes in THERMAL POWER.

Reducing T to' 500*F prevents the release of activity should a steam generatorfu0eru(pturesincethesaturationpressureoftheprimarycoolant i is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements. provide adequate assurance that excessive specific

activity levels in the primary coolant will be detected in sufficient time F to take corrective action. Information obtained on iodine spiking will be ,

used-to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analys'es following power changes may'be .

E pe'rmissible if justified-by.the data obtained.

3 3/4.4.9 PRESSURE /TEMRERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the

!- effects of cyclic loads due to system temperature and pressure changes.

These cyclic loads are introduced by normal load transients, reactor trips, j and startup and shutdown operations. The various categories t

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4 4

i ARKANSAS - UNIT 2 B3/4 4-5 AMENDMENT NO.

5

DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,295 i 400 cubic feet at a nominal T avg f 545 F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 5.6.1 1 The spent fuel racks are designed and shall be maintained so that the calculated effective multiplication factor is no greater than 0.95 (including all known uncertainties) when the pool is flooded with unborated water.

CRITICALITY - NEW FUEL 5.6.1.2 The new fuel storage racks are designed and shall be maintained with a nominal 25.0 inch center-to-center distance between new fuel assemblies such that K will not exceed 0.98 when fuel having a maximum enrichmentof4.1weig8[Ipercent U-235 is in place and aqueous foam will not exceed 0.95 when the storage area is moderationisassumedandk[I floodedwithunboratedwatef The calculated k

includes a conservative -

allowance of 2.1% Ak/k for uncertainties.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 399' 10 ".

CAPA0ITY 5.6.3 The spent-fuel storage r al is designed and shall be maintained with a storage capacity limited to no nore than 988 fuel assemblies. l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 9

5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

1 ARKANSAS - UNIT 2 5-5 AMENDMENT NO. 24, 71

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OPERATOR OPERATOR RR WE (t) THE HEALTH PHYSICS SUPERINTENDENT REPORTS TO THE TECHNIC AL SUPPORT MANAGER IN ADMINISTRATIVE MATTERS Afl0 ROUTifat HEALTH PHYSICS CONCERNS ANO ME REPOftTS TO THE DIRECTOR SITE NUCLEAR OPERATIONS IN MATTERS OF >

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OPERATOR OPERATOR leITEltFACE WITH THE DIRECTOR SITE NUCLE AR OPERATIONS IN DAILY COMMUNICATIONS, AND HAS DIRECT ACCESS TO THE SENIOR VICE PRESIDENT ENERGY SUPPLY ON ANY M ATTERS CONCERNING NUCLEAh QUALITY,

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OPERATOR OPERATOR FIGURE 6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATIONS ARKANSAS UNIT 2 6-3 Amendment No. J7,79,57,73 1

ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices COMPOSITION r

6.5.2.2 The Safety Review Committee shall be composed of a Chairman and at least eight members which collectively have the experience and l competence required by ANSI /ANS-3.1-1981 to review problems in the areas specified in Section 6.5.2.1, a-h.

The Vice President, Nuclear Operations shall designate, in writing, the Chairman and all SRC members.

The Chairman shall designate, in writing, the alternate Chairman in the absence of,,the SRC Chairman.

ARKANSAS - UNIT 2 6-8 AMENDMENT No. 5, 17, 25, 52, 73

ADMINISTRATIVE CONTROLS' ANNUAL REPORTS 2' 6.9.1.4 Annual reports covering the. activities of.the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. -The initial report shall be submitted prior to March 1 of the year following initial criticality.

C.9.1.5. Reports ~ required on an annual basis shall include:

a. A tabulation on an annual basis for the number.of statior, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their apociated man rem axposure '

according to work and job functions,- e.g., reactor >perations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste.prtcessing, and refueling. The dose assignment to various duty fun.tions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body. dose received form.

external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

c. Documentation of all challenges to the pressurizer safety valves.

d. A diesel generator data report which provides the number of valid tests and the number of valid failures for each diesel generator.

e. The results of specific activity analysis in which the primary coolant exceeded the limits.of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radio' iodine performed prior to exceeding the limit, results of analysis while limit was exceeded the results of one analysis after the radioiodhe NtWity was reduced to less than limit.

Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean up system flow. history

> 1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2/ This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

ARKANSAS - UNIT 2 6-15 AMEN 0 MENT NO. 5, #I J

1.-

ADMINISTRATIVE CONTROLS

-starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4)' Graph of the I-131 concentration and one other 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 radiofodine

~

limit.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating ' statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office no.later than the 15th of each month following the calendar month covered by the report.

6.9.1.7 Deleted.

6.9.1.8 Deleted.

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ARKANSAS - UNIT 2 6-16 AMENDMENT NO. 52 L

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A)MINISTEMIVE_CONIRots S)ECIAL REPORTS 6.9.2. Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each report. These repnrts 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.

b. Inoperable Seismic Monitoring Instrumentation, Specifica-tion 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation, Specifica-tion 3.3.3.4.

d. Seismic event analysis, Specification 4.3.3.3.2.

e. Inoperable Fire Detection Instrumentation, Specification 3.3.3.8.

f. Inoperable Fire Suppression Systems, Specifications 3.7.10.1 and 3.7.10.2.

g. Deleted. I

h. Radioactive Effluents, Specifications 3.11.1.1, 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.2.5, and 3.11.3.

4 This report shall include the following:

1) Description of occurrence.

2) Identify the cause(s) for exceeding the limit (s) .

3) Explain corrective action (s) taken to mitigate occurrence.

4) Define action (s) taken to prevent recurrence.

5) Summary of consequence (s) of occurrence.

6) Describe levels exceeding 40CFR190 in accordance with 10CFR20.405(c). ,

i. Inoperable Containment Radiation Monitors, Specification 3.3.3.1.

j.

Steam Generator Tubing Surveillance -- Category C-3 Results, Specification 4.4.5.5.

k. Maintenance of Spent Fuel Pool Structural Integrity, Specification 3.7.12.

1 ARKANSAS - UNIT 2 6-19 AMENDMENT NO. 60, 63 1

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ADMINISTRATIVE CONTROLS

1. Radiological Environmental Monitoring Sample Analysis, Specification 3.12.1.

m. Unplanned Offsite Release during one hour period of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. This report shall be submitted within 30 days of the occurrence of the event and shall include the following information:

1. Description of the occurrence.

2. Identify the cause(s) of exceeding the limit (s).

3. Explain corrective action (s) taken'to mitigate occurrence.

4. Define action (s) taken to prevent recurrence.

5. Summary of the consequence (s) of occurrence.

SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

l 6.9.3 Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of operations shall be submitted within 60 days after January 1 and July 1 of each year.

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

7 ARKANSAS - UNIT 2 6-19a AMENDMENT NO.

O e

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.4 R utine radiological. environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of year.

a. The annual radiological environmental operating report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use census required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report l shall provide an analysis of the problem and a planned course of 4 action to alleviate the problem.

b. The annual radiological environmental operating reports shall include summarized and tabulated results of all radiological environmental samples-taken during the report period. In the event that some 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 as soon as possible in a supplementary report.

c. The report shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.

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

0 ARKANSAS - UNIT 2 6-21 AMENDMENT NO.

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. ADMINISTRATIVE CONTROLS ;

o6.10 ' 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 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, L repair and replacement of principal items of equipment related to

nuclear safety.

c. All REPORTABLE EVENTS.

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.

i f. ~ Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and

results.

I h. Records of annual physical-inventory of all sealed source material I of record. i 6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records and drawing changes reflecting unit design modifications 1 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 l components identified in Table 5.7.1. 7 ARKANSAS - UNIT 2 6-22 AMENDMENT NO. 60 o

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ADMINISTRATIVE CONTROLS 6.12.2 By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the 00R Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

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

b. A ractation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset l 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 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 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 duty and/or the Health Physics Superintendent.

0/dd/ ddfdd OdtdBd/ 244 1980 ARKANSAS - UNIT 2 6-24 AMENDMENT NO. 274 294 60 t i

2CAN128601, Proposed Tech Spec Changes Re Verification of Transient Analysis code,CESEC-III & Spent Fuel Pool Expansion

Text

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