ML19320A264

Amend 12 to License DPR-51,allowing Removal of Surveillance Capsules During Cycle 1

ML19320A264
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/11/1976
From:	Ziemann D Office of Nuclear Reactor Regulation
To:
Shared Package
ML19320A261	List: ML19320A260 ML19320A264 ML19320A269 ML19320A273
References
NUDOCS 8004210552
Download: ML19320A264 (9)

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I ARKANSAS POWER 4 LIGHT COMPANY

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DOCKET NO. 50-313 4

ARKANSAS NUCLEAR ONE - UNIT NO. I b

AENDNENT 'It) FACILITY OPERATING LICENSE Amendment No. 12 License No. DPR-51 i

1.

The Nuclear Regulatory Coussission (the Commission) has found that:

I A.

The applications for amendment by Arkansas Power 4 Light Company (the licensee) dated May 19, June 4 and June 10, 1976, comply with the standards and requirements of the Atomic Energy Act of i

1954, as amended (the Act), and the Constission's rudes and s.

L regulations set forth in 10 CFR Chapter I; i

B.

The facility will operate in conformity with the application, l~

- the provisions of the Act, and the rules and regulations of j

the Commission; C.

There is reasonable assurance (i) that the activities authorized ~

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities dll be conducted in compliance with the Commission's regulations; I

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D.

The issuance of this amendment till not be inimical to the comanon defense:and security or to the health and safety of the public; and I

f E.

'nte issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable l

requirements have been satisfied.

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j Form AEC 313 (Rev. 9 53) ABCM 0240

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.

3.

This License amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION driginal dgne5N 1)ennis L. ziemann Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors Attachment :

Changes to the Technical Specifications Date of Issuance:

JUN 11 1976 In l

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• Form AEC.318 (Rev. 9 53) ABOC 0240

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Tcblo 4.1-3 MINIMUM SAMPLING AND ANALYSIS FREQUENCY Item' Test Frequency 1.

Reactor Coolant a.

Gamma Isotopic Analysis a.

Bi-weekly (7)

. Samples b.

Gross Activity Determination b.

3 times / week a.d at least every third day ('; ;6; ;7'.

c.. Gross Radiciodine Determination c.

Weekly (3)(6)(7)

Weekly (7)(11) l' d.

Dissolved Gases d.

Chemistry (C1, F, and 0 )

e.

2 e.

3 times / week (5)

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f.

Boron Concentration f.

3 times / week g.

Radiochemical Analysis for g.

!!onthly (7) 1 Determination (2)(4) 2.

Borated Water Boron Concentration Weekly and after Storage Tank Water Samole each makeup 3.

Cope Flooding Tank Boron Concentration Monthly and after Sample each makeup 4

Spent Fuel Pool Boron Concentration Monthly and after Water Sample each makeup (9)

S.

Secondary Coolant a.

Gross Radioiodine' Concentration a.

Weekly (5)(7)(10)

Samples b.

Isotopic Radioiodine b.

Monthly (7)(10)

Concentration (4) 6.

Sodium Hydroxide Sodium Hydroxide Concentration Quarterly and Tank Sample

,after each makeup 7.

Sodium Thiosulfate Sodium Thiosulfate Concentration Quarterly and Tank Sample after each makeup Notes:

(1) A gross radioactivity analysis shall consist of the quantitative measurement of the total radioactivity of the primary coolant in units of uCi/gm.

The total primary coolant activity shall be the sum of the degassed beta-gamma activity and the total of all identified gaseous activities 15 minutes after the pridary system is sampled.

Whenever the gross radioactivity concentration excee'ds 104 of the limit specified in the Specification 3.1.4.1 or increases by 10 ;.Ci/gm from the previous, measured level, the frequency of sampling and analyzing shall be increased to a minimum of once/ day until.a steady activity level is es.tablished.

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' Amendment No. 12

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(2)

A radiochemical analysis shall consist of the. quantitative measurement of the activity for each radionuclide which is identified in the primary

' coolant 15 minutes after the primary system is sampled.

Dic' activities for the individual is:: topes shall be used in the determination of F..

A radiochemical analysis and calculation of E and iodinc isotopic activity

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shall be perforced if the measured gross activity changes 17 more than 10 uCi/gm from the previous measured level.

I:e gacma energy per disinte-gration for those radioisotopes determined to be present shall be as given in " Tabic of Isotopes" (1967) and beta energy per disintegraticn shall be as given in USNRDL-TR-802 (Part II) or other references using the equivalent values for the radioisotopes.

(3)

In addition to the weekly me[surement, the radioiodinc concentration shall

'ho determined if the measured gross radion'etivity concentration changes by more than 10'uCi/cm from the previous measured Icycl.

(4) l'odinc isotopic activitics shall be weighted to give I-131 dose equivalent activity.

(5)

In addition to the weekly men'surement, the radioiodine concentratica sh :11 he deteruined if therc arc indications that the primary to sceandary coolant Icakage rate has increased by a factor of 2.

(6)

W.cncycr the steady state radioiodine or gross radioactivity concentratien of prior operation is greater than 1 percent but less than 10 percent of Specification 3.1.4.1, a sauple of reactor coolant shalI be taken tithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any rcact or, criticality atal analyzed for va lioactive iodines c f I-131 throup,h I-135 and gross radioactivity ns well as the coolant sarplc

.and analyses required by the above.

l!henever the steady state radiciodinc or gross radioactivity concentration of prior operation is greater than 10 percent of Specification 3.J.4.1, a sanple of reactor coolant shall be takeit prier to any reactor criticality and analy::cd,for radioactive iodines of I-131 through 1-335 and gross radioactivity as well as the coolant sample and analyses required by above.

(7)

Not required when plant is in the cold sliutdom condition or refueling shutdown condition.

(8) 02 analysis is not required when plant is in the cold shutdown condition or refueling shutdown condition.

(9), Required only when fuel is in the pool and prior to transferring fuel

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to the pool.

(10)

Not required when not generating steam in the steam generators.

(11) The following shall be required only during Cycle 1 operation after 340 effective full power days:

Gross radiciodine shall be determined at least three times per week a.

during power operation.

Amendment No. 12

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If the steady state ' gross radioiodine concentration increases by a factor of ten or more, the NRC shall be promptly notified with a written followup per Specification 6.12.3.1.

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l Amendment No.12 f

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e IS-261 Item Co-conent Exception 6.4.

Bolting 2%

Not Applicable 6.6 Integrally Welded Not Applicable Valve Sapports 4.2 3 The structural integrity of the reactor coolant system boundary shall be maintained at the level required by the original accep-l tance standards throughout the life of the station. Any evidence, as a result of the tests outlined in Table IS-261 of Section XI of the code, that defects have developed or grown, shall be investigated.

4.2.4 To assure the structural integrity of the reactor internals through-out the life of the unit, the two sets of cain internals bol s 4

(connecting the core tarrel to the core support shield and to the lower grid cylinder) chall re=ain in place and under tension. This

- will be verified by visual inspection to deterine that the velded i

bolt locking caps remain in place. All locking caps vill be inspect-ed after hot functional testing and whenever the internals are removed from the vessel during a refueling or =aintenance shutdown.

The core barrel to core support shield caps will be inspected each refueling tutdown.

4 4.2 5 Sufficient records of each inspection shall be kept to allow comparison and evaluation of future inspections.

4.2.6 Complete surface and volumetric examination of the reactor coolant Pump flywheels vill be conducted. coincident with refueling or maintenance shutdowns such that within a 10 year period after start-up all four reactor coolant pump flywheels will be examined.

1 Reactor vessel specimens shall be removed an'd examined, to deter-4.2. *(

eine changes in material properties, at specimen exposure (E>lMey) equivalent to 3, 9.5,16 and 22.5 Effective Full Power Years (EFPY) of operation. This withdrawal schedule may be modified to coincide with those refueling outages or plant shutdowns, when the reactor y

head is removed, most closely approaching the withdrawal schedule.

i Results of _these examinations shall be used to update Technical.

l Specification 3.1.2.

Specimens not subjected to destructive testing af ter the first 0.93 EFPY of Cycle 1 may be removed and stored during the remainder of Cycle 1, but shall be re-installed prior to Cycle 2.

Bases The surveillance program has been developed to comply with Section XI of the ASME Boiler and Pressure Vessel Code Inservice Inspection of Nuclear Reactor Coolant Systems,1971, including 1971 Ninter Aedenda edition.

The' number of reactor vessel specimens and the frequencies for removing 1

and testing these specimens are provided to assure compliance with the requirements of Appendix H to 10 CFR Part 50.

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43 TESTING FOLIDWIIIG OPDTING OF SYSTEM i

Applicability I

Applies to test requirements for Reactor con 1 ant System integrity.

dbjective To assure Reactor Coolant System integrity prior to return to c -iticality following nor=al openin,g, modification, or repair.

Specification 4.3 1 When Reactor Coolant System repairs or modifications have been'

=ade, these repairs or codifications shall be inspected and tested to meet all applicable code requirements prior to the reactor being cade critical.

4.3.2 Following any opening of the Reactor Coolant System, it shall be leak tested at not less than 2285 psig prior to the reactor being made critical.

433 The limitations of Specification 31.2 shall apply.

Bases Rhpairs or =odifications cade to the Reactor Coolant System are inspectable and testable under applicable codes, such as B 317, and ASME Boiler and Pressure Vessel Code,Section IX, IS-400.

For nor=al opening, the integrity of the Reactor Coolant System, in terms of strength, is unchanged.,. If the systw does not leak at 2285 psig (operating pressure +100 psi; 150 psi is noma.)1 ystem. pressure fluctuation),

it vill be leak tight during nor=al operation.\\

FSAR, Section 4 l

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4.12 EYDROGEN PURGE SYSTEM SURVEILLANCE

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Applicability Applies to the surveillance of the, hydrogen purge system.,

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Objective To. verify an acceptable Icyc1 of.efficic ncy and operability of the hydrogen purge system.

Specification 4.12.1 At least once per refueling period '(not to exceed 18 months) the following conditions shall be demonstrated:

ThepressuredropacrossthecombinedHEPAfiltersandcharcoaI

.a.

adsorber banks is less :han 16 inches of water at system design flow r'te (+ 10%).

a b.'. Each' system inlet heater unit operates at rated power.

4.12.2.a.

The tests and sampic analysis of Specification 3.14.1.a,b, 4 c. shall be performed initially

• and at least once per refuel-ing period (not to exceed IS conths) c after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, fire or chemical release in any ventilation one co==unicating with the system..

b.

Cold DOP testing shall also be perforced after each complete or partial replacement of a HEPA filter bank or after any structural naintenance on the system housing.

c.

Halogenated hydrocarbon testing shall also be perfor=cd after each complete or partial feplacement of a charcoal adsorber bank or after any structural =aintenance on the syste= housing.

'4.12.3 Each circuit shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each conth.

4.12.4 Ilydrogen concentration instruments shall be calibrated at leas t once per refueling period (not to exceed 18 months) with proper

.considerntion to moisture effect.

Basis Since the hydrogen purge. system is not normally operated, a periodic test is ' required to show.that the syste= is available for hydrogen control following an accident.

During this test the system will be-inspected for such things as water, oil, or other foreign material, gasket deterioration in the !! EPA units, and unusual or excessive noise or vibration when the fan motor is running.

• Initial tests shall be performed within 9 months of the date of l

1ssuance of Amendment 10 to Licence No. DPR-51.

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ATTACIBfENT TO LICENSE AMENDMENT NO.12 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313

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i Replace existing pages 74, 75, 77 and 109b of the Technical Specif1-

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cations contained in Appendix A to the license with the attached revised _

pages bearing the same mmbers and additional page 75a. The changed I

areas on the revised pages are identified by a marginal line. Also, page 78 is enclosed as a matter of convenience in updating the Technical i

Specifications. There are no changes on this page.

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summaus t narse form AEC 318 (Rev. 9-53) ABCM 0240

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