ML20077G905

Proposed Tech Specs,Revising Limiting Conditions for Operations Sections 3.0.4,4.0.3 & 4.0.4 & Associated Bases & Associated Tech Spec

ML20077G905
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/27/1991
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20077G903	List: 2CAN069104, Application for Amend to License NPF-6,revising Limiting Conditions for Operations for Associated Bases,Per Generic Ltr 87-09 ML20077G905
References
NUDOCS 9107030073
Download: ML20077G905 (54)

Text

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ENCLOSURE PROPOSED TECilNICAL 9PECIFICATION AND RESPECTIVE SAFETY ANALYSES IN Tile MAUER OF AMENDING LICENSE NO. NFP-6 ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368 9107030073 910627 PDR ADOCK 05000368 P PDR 1

PROPOSED CilANGE The proposed changes to the ANO-2 Technical Specitications (TS) would incorporate the recommendations provided in the NRC's Generic hotter 87-09 dated June 4, 1987. This proposal rnvises 1.imiting Conditions for Operat ions (LCO) Section 3.0.4 and Survoillanco Sect.f ons 4.0.3 and 4.0.4, their associated Bnsns, and thoso associntnd TS which no longnr need to be exempt from thn provisions of TS 3.0.4 due to its rewording. Dnintion of the approprinto except ions are provided in the nttached revised TS.

. MEGROUND The proposed changes to TS 3.0.4, 4.0.3 end 4.0.4 nro thoso changes recommendnd in Genoric hotter 87-09. ,

Thn chango to TS 3.0.4 would alleviato unnecessary restrictions on modo changes. This proposal will allow modo changes when in an ACTION statement which nilows continued operation for an unlimited period of timo. With the change to TS 3.0.4, individual exceptions to TS 3.0.4 where the ACTION statement daea_nni requiro a shutdown are no longer nncessary pursuant to Generic hottor 87-09. Exceptions to 3.0.4 in TS that do requiro a plant shutdown are retained. It should be noted that this chango does not endorso or encourago plant startup with inoperable equipment.

The proposed change to TS 4.0.3 would eliminato unnecessary shutdowns which are now required dun to inndvertent surpassing of survoillance intervals.

The chango clarifles tho applicability of the ACTION requirements, to specify a specific necept.nble timo limit for completing a missed 1 surveillanco in certain circumst.ancos, and specifies that a missed survoillanco continues to constitutes a violation of tho Opernbility Requirements of an LCO. It is overly conservative to assumo that systems or components nrn inoperablo when a survnlllanco has not been.porformed, because the vast majority of survoillanens do in fact demonstrate that.

systems or components are operablo. When a survoillanco in missed, it is primarily a question of opornbility that has not been verified by the performanco of a Survoll1anco Requirement. Because the allownble outage timo limits of some ACTION rnquirnments-do not provido an approprinto timo for performing a missed'aurveillance before Shutdown Requirements applies, the TS should include n Limo limit that allows a delay of required actions to permit the performanco'of the missed survoillanco based on consideration of plant condit.lons, adequato planning, avallnbility of personnel, the time i required to perform thn surveillanco, and the sofoty significance of the delay in completing the surveillance. The staff has concluded that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is an acceptable timo limit for completing a missed surveillance when the allowable outagn times of the ACTION requirements aro less than this limit, or when timo is needed to obtain a temporary waiver of the Surveillanen: Requirement.

The proposed change to TS 4.0.4 is noccanary to allow the plant to proccod through or to required OPERATIONAL HODES to comply with ACTION requirements even though applicablo Survoillance Requirements may not have bonn performed. Two possible conflicts exist between TS 4.0.3 and 4.0.4. The first conflict arison because TS 4.0.4 prohibita entry into an OPERATIONAL MODE or other specified condition when Survoillanco Requirements havn not been perfor ad within the specified surveillanco interval. A conflict with this requirv ent exists when a modo changn is required as a consequencn of l ACTION requirements and when the Survnlllance Rnquirements that. becomo applicable have not boon performed within the specified surveillance l

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interval. TS 4.0.4 nhould not be used to prevent passage through or to OPERATIONAL MODES as requirnd to comply with ACTION requirements because to do so would increase the potential for a plant upset. and would challengo sa f ety r,ystems. Also certain surveillances should bn allowed to be performed during a shutdown to comply with ACTION requirements. Along with the modification of TS 4.0.3 to permit a delay of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the applicability of ACTION requirements TS 4.0.4 needs clarification to allow pannage through or to OPERATIONAL MODES as required to comply with the ACTION requirements.

A second conflict could arise becauso, when Surveillance Requirements can only be completed af ter entry into a mode or specified condition for which the Surveillance Rnquirements apply, an exemption to thn requirement s of TS 4.0.4 is allowed. However, upon entry into this modo or condition, the requirements of TS 4.0.3 may not be met because the Surveillance Requirements may not havn been performed within the allowed surycillance interval. Thornfore, to avoid any conflict betwoon TS 4.0.3 and 4.0.4, the wording is now clear that it is not the intent of TS 4.0.3 that the ACTION requirements proclude the performanen of survnillances allowed under any exemption to TS 4.0.4 and that t he delay of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in TS 4.0.3 for the applicability of ACTION requirements nor provides an approprint.e time limit for thn completion of thoso Surynlllance Requirements that become applicable as a consequence of allowance of any exception to TS 4.0.4.

The staff, in Generic Letter 87-09 concluded that these revis ions wot.1d result in improved TS and encouraged licensees to proposed these changes.

Revision of thn Bases sections for ANO Unit 2 TS are also proposed. These changes are likewise taken f rom Generic Lotter 87-09.

DISCLSSION The proposed changes to ANO Unit 2 TS would incorporate recommendations provided in NRC Generic Letter 87-09. The changes would alleviate unnecessary restrictions on modo changes, ollminato unnecessary shutdowns which are not required due to inadvertent surpassing of surveillance intervals and allow the plant to proceed through or to required OPERATIONAL MODES to comply with ACTION requirnments even though applicable Surveillance Requirements may not have been performed.

Entergy Operations recognizes that it is incumbent upon us to reasonably assure the operability of TS required equipment prior to entry in applicable modes of operation and that these changes do not. In any way diminish this responsibility. Missed survnillances will continun to rnceive prompt management attention and be thoroughly evaluated to assure appropriate correctivo actions are implemented. Additionally, a missed surveillance will continue to be reported as a Licensee Event Report.

The following deviations from the specific wording of the Generic Letter havn been incorport:ted in this change for futhor clarification:

1. In the Bases for LCO 3.0.4 one sentonce has been rewritten for operator human factors improvement with no intent change. Also, the term ' shutdown' is defined as a required reduction in modo consistent with currnnt plant practices.

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2. In Surveillance Requirement 4.0.3 "The ACTION Requirement may be delayed" has been rewritten to "The time at which the Action is taken may be delayed" as a human factors improvement.

3. In the Bases for 4.0.3 an e,f lanation of conditions greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has been added as a human factors improvement.

DETERMINATIO!! 0F SIGNIElC#1I_J162ARDE An ovaluation of the proposed chango has been performed in accordance with 10CFR50.91(a)(1) regarding no significant hazards cons 1 dotation using the standards in 10CFR50.92(c). A discussion of those standards as they relate to this amendment request follows:

Criterion 1 - Does not involve a Significant increase in the Probability or Consequences of an Accident Proviously Evaluated.

The proposed amendment does not involve an increase in the probability or consequences of any previously evaluated accident.

, The change to TS 3.0.4 will allow modo changes while the Unit is in an ACTION statomont which does not prohibit power operation. Exceptions to TS 3.0.4 have already boon taken in manv c5 the individual ACTION statements.

This change will allow a modo change when appropriate TS ACTION statements are implemented. Current TS Identify sufficient actions should the component or system becomo inoperablo during the applicablo mode of operation. Those actions ensure that an adequato level of protection exists until the equipment can be repatrod. The proposed chango allows the Unit to entor OPERATIONAL MODES if the actions have been mot.

Incorporating the. proposed change into 3.0.4 w111 onsure that exceptions will be consistently applied throughout the TS, when justified.

The change to TS 4.0.3 will allow a delay of implementation of ACTION requirements for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under cortain conditions when a surveillance has hoon missed. Additionally, in some casos a surveillanco should be delayed for optimum plant conditions. This will not significantly increase the probability or the consequences of an accident, in that surveillances normally verify system or component operability as opposed to discovering inoperability. Without the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay, it.is possible that a missed surveillance would force the Unit to be placed in a shutdown condition. Avoidance of these unnecessary shutdowns is bonoficial as this induces stressos into the reactor vessel materials and far outweights any disadvantages associated with the additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in which to perform a missed surveillanco.

Additionally, if a plant shutdown is required before a missed surveillanco is completed, it is likely that it would be conducted when the plant is being shut down because completion of a missed surveillance would terminato i

the shutdown requirement. This is undesirable sinen it increases the risk

to the plant and public safety for two reasons. First, the plant would be in a transient stato involving changing plant conditions that offer the potential for an upset that could load to a demand for the system or c.omponent bning tested. This would occur when the system or component is olthor out of service to allow performance of the surveillance test or thoro is a Icwor level of confidence in its operability because the normal surveillanco interval was exceeded. If the surveillanco did demonstrato that the system or component was inoperable, it usually would be proforable to restore it to operable status before making a major chango in plant

L opernt.ing conditiont., Second, a shutdown would incronso the pressure on t he plant sta f f . to expeditiously compint o the required surveillanco so that the plant could be rnturned to power oporation. This would further inctnaso the potential for a plant upset when both the shutdown ned surveillanco nctivitics place a domand on the plant operators.

The change to TS 4.0.4 will not result in a changn to tho design or operation of the facility, thornfore, t hir, chango wi '.1 not result in nn incienso in the probability or connequn1ces of an arcident previously evalunted.

Criterion 2 - Does not crento the possibility of a Now or Different Kind of Accident from any Previously Evnlunted.

The proposed changes will not create the possibility of a new or dif ferent kind of accident from any accident previously evaluated for the reasons stated holow.-

The chango to TS 3.0.4 will allow the plant to entor applienhlo OpERATIONAh MODES if an ACTION statement which already allows continued operation is mot. Sevoral TS ACTIONS currently allow continued operation with an inoperablo component or system when complianco with the ACTION requirements is satinfled. No new modes of operation arn boing introduced by this chnngo.

The change to TS 4.0.3 would allow the plant to continun operation for an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter discovery of a missed survoillanen. Minning a survn111ance does not menn that a component or system la inopornblo, in most cases, surveillances demonstrato the continund opornbility of the components and systems. This chango will not affect the design of the plant and will not allow thn pinnt. to be operated outsido the currently allowed modes of oporation.

The chango Lo TS 4.0.4 will allovinto a contradiction within the TS. Thn proposed change to.TS 4.0.4 in noenssary to allow the plant to proccod through or to required OPERATIONAL MODES to comply with ACTION requiroments even though applicablo Survnillanco Requirements may not have been performed. This chango does not offect any of the accident analyses.

Criterion 3'- Does not.Involvo a Significant Roduction in the Margin of Safety.

The proposed amendments will not involvo a significant reduction in a margin of safety.

The change to TS 3.0.4 will allow modo changes while still in ACTION statements that do not require plant shut. downs, givnn that ACTION statements are complied with prior to changing modo. Exceptions to 3.0.4 nro aircady contained wit.hin many of the applicablo ACTION stat omonts.

Incorporating a standard exception within the body of the requiremnnt will ensure consistent application of the exception.

The changn to TS 4.0.3 will allow up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to porform a ml.nsed surveillance. In some cases this will climinato the need for a pinnt shutdown. The overall effect in a not gain in pinnt snfoty dun to avoidance of unnecessary shutdowns due to missed survoillnnces.

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The chango to TS 4.0.4 will oliminato a contradiction within the TS and is necessary to allow the plant to procot3J through or to required OPERATIONAh MODES to comply with ACTION requirements even though applicable Survoillanco Requirement.s may not have been performed. This chango doos <

not cffect any margin of safety.

The NRC in issuing Generic hotter 87-09 recommended thoso changes and concluded that t. hey would result in improved TS. Entergy Operations concurs with this conclusion.

The Commission has orovided guidance in 51 FR 7750 dated March 6, 1986, concerning the application of the standards for dotormining whether a significant hazards considoration exists. The proposed amendment most closoly matches examplo (vil):

"A change to conform.a licenso to changes in the regulations, whero the license change resulta .in rainor changes to facility operations clearly in keeping with t.he regulations."

Based on the above.ovaluation, it in concluded that the proposed TS chango does not constituto a significant hazards concern.

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r PROPOSED TECilNICAL SPECIFICATION CilANGES

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY L1tilIISLCONDln0LE0fLorEldT10N 3 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 In the event a Limiting Condition for Operation and/or associated ACTION requirements ca. mot be satisfied because of circumstances in excess of those addressed in the specification within I hour, action shall be initiated to place the unit in r. MODE in which the specification does not apply by placing it, as applicabic, in at least 110T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least 110T SilUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SilUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless corrective measures are completed that permit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery or until the reactor is placed in a mode in which the specification is not applicable.

Exceptions to these requirements shall be stated in the individual specificatlon.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions of the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or other specified condition may be made in accordance with ACTION requirement when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prmrent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual specifications.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s), and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are sat.infied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, ACTION shall be init!ated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in at 1 cast 110T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least 110T S!!UTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD SilVTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This specification is not applicable in MODES 5 or 6.

ARKANSAS - UNIT 2 3/4 0-1 Amendment No. H ,

APpLICAb!LITY WREIRM.CLEEQW21ENIE LContinuW 4.0.1 Surveillance Requirements shall be applicable during tho OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise st.ated in an individual Survoillanco Requirement.

4.0.2 Each Survoillanco Requirement shall be performed within the speciflod survoillanco interval with a maximum allowable extension not to exceed 25 porcent of the specified survnillance interval.

4.0.3 Failure to perform a Surycillanco Requirement within the allowed surveillanco interval defined by Specification 4.0.2 shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The timo limits of the ACTION requirements are applicable at the time it is identified that. a Survoillanco Requirement has not. been performed. The time at which the ACTION is taken may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the survoillance when the allowable outage timo limits of the ACTION reqhirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Survoillanco Requirements do not havo to ho performed on inoperabl-equipment.

4.0.4 Entry into an OPERATIONAL MODE or other speciflod applicability condition shall not be made unless the Surveillanco Requiremont(s) associated with the Limiting Condition for Operation have boon performed '

within the stated surveillanco interval or as otherwise specified. This provision'shall not provent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

4.0.5 Surveillanco Requirements for inservico inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a. During the timo per!od:

1. From issuance of the Facility Operating Licenso to the start of facility commercial operation, inservice testing of ASME Codo Class 1, 2 and 3 pumps and valvos shall be performed in accordance with Section XI of the ASME Boller and Pressure Vessel Code 1974 Edition, and Addenda through Summer 1975, except where specific written rollof has been granted by the Commission.

2. Following start of facility commercial operation, inservico inspection of ASME Code Class 1, 2 and 3 components and ineorvice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and pressuro Vessel Code and applicable Addenda as regulrod by 10 CFR 50, Section 50.55a(g), except where specific written rollef has boon granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

ARKANSAS - UNIT 2 3/4 0-2 Amendment No. 42,JP),

TABLE 3.3-1 REACTOk PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANhTLS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRID OPERABLE MODES ACTION

1. Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1, 2 and

• 1

2. Linear Power Level - High 4 2 3 1, 2 2 l

3. Logaritheir Power Level-High

a. dcartup and Operating 4 2(a)(d) 3 2 and

• 2 I

b. Shutdown 4 0 2 3, 4, 5 3

4. Pressurizer Pressure - High 4 2 3 1, 2 2 I

5. Pressurizer Pressure - Low 4 2(b) 3 1, 2 and

• 2 (

6. Containment Pressure - High 4 2 3 1, 2 2 1

7. Stear Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 and

• 2 3

8. Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2 g

9. Local Power Density - High 4 2(c)(d) 3 1, 2 2 l ARKANSAS - UNIT 2 3/4 3-2 Amendment No. 21,

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

TABLE 3.3-1 (Certinued)

REACTOR PROTECTIVE INSTRIENTATION i

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MINIMCM TOTAL ~NO. CHANNELS CHANNELS APPLICABLE t

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES LN i

10. DNER - Low 4 2(c)(d) 3 1, 2 2 I

11. Steam Generator Level - High 4/SG 2/SG 3/SG 1, 2 2 I

12. Reactor Protection System '4 2 4 1, 2 and

• 4 Logic

13. Reactor Trip Breakers 4(f) 2 4 1, 2 and

• 4

14. Core Protection Calculators 4 2(c)(d) 3 1, 2 2 and 6 l j 15. CEA Chlculators 2 1 2(e)- 1, 2 5 and 6 l I ,

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TABbE 3.3-1 (Continued)

TABLE NQIAIIDN

• With the protective system trip breakers in the closed position and the CEA drive system ccpable of CEA withdrawal, I

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(a) Trip may be manually bypassed above 10 % of RATEl)  : by pass shall be automatically removed when TilERHA1. POWER TIIERHAbPOWEg%of is $ 10 RATED TilERHAI. p0WER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizor pressure is 2 500 psia.

~0 (c) Trip may be manually bypassed below 10 % of IIATED TilERHAb POWERj4 bypass shall be automatically removed when TilERHAb POWER is 2 10 % of RATED TilERHAL POWER. During testing puruunnt to Special Test Exception 3.10.3. trip may be manually bypassed below 1% of' RATED TilERMAb POWER; bypass shall be automatically removed when TilERHAb POWER is 2 1% of RATED TilERMAi, POWER.

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e) Soc Special Test Exception 3.10.2.

(f) Each channel shall be comprised of two trip breakers; actaal trip logic shall be one-out-of-two taken twice.

ACTION STATEMENTS-ACTION 1 - With .the number of channels OPERABbE one less than required by the Mini.aum Channels OPERABbE requirement, restore the Inoperable channel to OPERAhLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in 110T STANDBY within ' the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open t.he protective system trip breakers.

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TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATIOM MINIMU3 TOTAL NO. CHANNELS CHANNELS APPLILABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

4. MAIS STEAM AND FEEDWATER ISOLATION (MSIS)

a. Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1,2,3,4 8

b. Steam Generator 4/ steam 2/ steam 3/ steam 1, 2, 3 9 I Pressure - Low generator generator generator

5. CONTAINMENT COOLING (CCAS)

a. Manual (Trip Buttons) 2 sets of 2 I set of 2 2 sets of 2 1, 2, 3, 4 8

b. Containment Pressure -

High 4 2 3 1,2,3 9 l

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c. Pressurizer Pressure -

Low 4 2 3 1, 2, 3(a) 9 }

6. RECIRCULATION (RAS)

a. Manual (TRIP Buttons)(c) 2 se.s of 2 1 set of 2 2 sets of 2 1,2,3,4 8 per train per train per train i

b. Refueling Water Tank - Low 4 2 3 1,2,3 9 l

l ARKANSAS - UNIT 2 3/4 3-12 Amendment No.

I

TABLE 3.3-3 (Continued) l ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 1

-MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

7. LOSS OF POWER

a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage) 2/ Bus 1/ Bus 2/ Bus 1,2,3 8 i

b. 460 volt Emergency Bus Undervoltage (Degraded Voltage) 1/ Bus 1/ Bus 1/ Bus 1, 2, 3 8

8. EIIERGENCY FEEDWATER (EFAS)

a. Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1, 2, 3, 4 8 per S/G per S/G per S/G

b. SG Level and Pressure (A/B) - Low and AP (A/B) - High 4/SG 2/SG 3/SG 1, 2, 3, 4 9 l

c. SG Level (A/B) - Low and No S/G Pressure -

Low Trip (A/B) 4/SG 2/SG 3/SG 1,2,3,4 9 l l

i l

1 AREANSAS - UNIT 2 3/4 3-13 Amendment No.

IABL Q l-3 (Continued)

IAELE NOTATION (n) Trip function may bo bypassed Jn this HODE when pressurfzor pressure is below 400 psin; bypass shall be automatically removed when pressurizer prosauro is 2 500 psin.

(b) An SIAS signal in first necessary to enablo CSAS logic.

(c) Remoto manual not provided for RAS. Those nro local manuals at each ESF auxillary relay cabinet.

AGIl0N STATEMENIS ACTION 8 - With the number of OPERABLE channels one loss than the Total-Number of Channels, restore the inoperablo channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least IIOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SilVTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

^

ACTION 9 - With the number of OPERABLE channels one loss than the Total Number of Channels, operation may proceed provided the following conditions are natisfied:

n. The inoperable channel is placed in olthor the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. For the purposes of testing and maintenanco, the inoperable channot may bo bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of initial loss of OPERABILITY; however, the Inoperable channel shall then be either restored to

' OPERABLE status or placed in the tripped condition.

b. Within one hour, all functional logic units receiving an input from the inoperable channel are also placed in the same condition (either byonssed or tripped, as applienblo) as that required by a. abovo for the Inoperable channel,

c. The Minimum Channels OPERADLE requirement is mot;

l. however, one additional channel may be bypassed for up

! to 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> while performing tests and maintonnnce on l' that channel provided the other inopornblo channel is placed in the tripped condition.

i F

t l

ARKANSAS - UNIT 2 3/4 3-14 Amendmont No.

l

INSTRUMENTATION 3/4.3.3 MORlIQRJRG INSTRUMENTATl0N RADIATION MONTIORING_1RSTRUMENTAIl0N L1111T1HQ. .COND1Il0LE0R. QEERAT10N 3.3.3.1 Tho radiation monitoring instrumentation channels shown in Tablo 3.3-6 shall be OPERABLE with their alarm / trip sotpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm / trip sotpoint exceeding the valun shown in Table 3.3-6, adjust. the sotpoint. to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable. .

b. With one or more radiation monitoring channelr. Inoperable, take the ACTION shown in Tnblo 3.3-6.

c. The provisions of Specification 3.0.3 nro not. applicable.

l EURYEILLARCR.EQU.1 ret 1ENIS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CilANNEL CilECK,-CilANNEL CALIBRATION and CilANNEL FUNCTIONAL TEST operations dur.ng the modos and at t.he frequenclos shown in Table 4.3-3.

ARKANSAS - UNIT 2 3/4 3-24 Amendment No.

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

INSTRUMENTATION INCORE DETEGIQRS LIM 1.UN1 CONDITIQN.EQRRERAHON 3.3.3.2 The incore detection system shall be OPERABLE with:

a. At least 75% of all incoro detectors with at 1 cast one incore detector in each quadrant at each 1cvol, and

b. At least 75% of all incore detector locations, and

c. Sufficient operable incore detectors to perform at least six tilt estimates with at least ore tilt estimate at each of three invols.

An CPERABLE incore detector location shall consist of a fuel assembly containing either a fixed detector string with a minimum of throo OPERABLE rhodium detectors or an OPERABLE movable incoro detector capable of mapping the location.

A tilt estimate can be made from two sets of symmetric pairs of incore detectors. Two sets of symmetric pairs of incore detectors are formed by two pairs of diagonally opposite symmetric incore detectors, one incore detector per quadrant.

APPLICABILITY: When the incore detection system is used for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin.

ACTION:

With the incoro detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification 3.0.3 are not applicable. l EURYEILLAECE RE0_UIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

a. By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin.

b. At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core.

ARKANSAS - UNIT 2 3/4 3-28 Amendment No. 5),

INSTRUMENTATION SEISMIC INEIRQiLNIAI1ON M LIti1IlNG_CDSDII1RN_ EOR 0fERATIDH 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTIDS:

a. With one or more seismic monitoring instrument.s inoperable for more than 30 days, prepare and submit. a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status,

b. The provisions of Specification 3.0.3 are not applicable. l EURYEIL1dLNCILREQ41 ret 1ESIS __

4.3.3.3.1 Each of the above seismic monitoring Instruments shall be demonstrated OPERABLE by the performance of the CIIANNEL CilECK, CilANNEL CALIBRATION and CilANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CilANNEL CALIBRATION performed within 5 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant 5

effect upon facility features important to safety.

ARKANSAS - UNIT 2 3/4 3-30 Amendment No.

_...__m_. _ . _ _ . _ _ _ _ _ _ _ . _ _ . _ . _ . _ . . _ _ . _ . _ _ _ . _ _ - _ _ _ _ - _

JNSTRUMENTATION METEQE0 LOGICAL lRS11M1ENIAIl0N hlHlIlHG ERNDIT10LE0!LDIIRAIl0N 3.3.3.4 The matcorological monitoring lustrumentation chnnnoin shown in Tabin 3.3-8 shall bn OPERABl.E.

ALTLLCAIL11dII: AL a11 times.

ACIl0N:

n. With one or morn required meteorological monitoring channels inopornble for more than 7 days, preparo and submit. n Special Report. to the Commission pursuant to Specification 6.9.2 within the nnxt 10 days outlining the cauan of the malfunction and the plans for rnstoring the channnl(s) to OPERABI.E status.

l

b. The provisions of Specification 3.0.3 nro not applicablo.

l Sl!RYEILLANCE.REQMIREMERIS 4.3.3.4 Each of thn above motoorological monitoring instrumentation channels shall be demonstrated OPERABI,E by the performance of the CilANNEI.

CilECK and CIIANNEl. CAI.lBRATION operations rt tho irequencins shown in Table 4.3-5.

l i

i l

ARKANSAS - UNIT 2 3/4 3-33 Amnndment No.

1 a

INSTRUMENTATION l

CIILDRINE_DEIEGI.1DLEISIDiS LltilI1NG_COND1Il0N IO!LOI'ERAIl0N _

3.3.3.7 Two independent chlorinn detection systemn, wit h t heir alarm / trip setpoints adjusted to actuate at a chlorino concentration of 5 5 ppm, shall be Ol'ERABLE.

AI'I'IdCAD.ILLIX : MODES 1, 2, 3 and 4.

ACTION.

n. With onn chlorino dntnction system inoperable, restore the inoperable detection system to OPERABLE status within 7 days or within the nnxt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiato and mnintain operation of the control room emergency ventilation system in thn recirculation modo of opernt lon.

b. With no chlorine detect.Jon system OPERABLE, within I hour initiato and maintain operation of the control room emergency ventilation syst.om in the recirculation modo of operation.

SHRyEILLANCILREQQ1RfdERIS 4.3.3.7 Each chlorine detection system shall be demonstrated OPERABLE by performanen of a CilANNEL FIIECK at Inast onco por 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CilANNEL FUNCTIONAL TEST at least once por 31 days and a CllANNEL CALIBRATION at least once per 18 months.

ARKANSAS - UNIT 2 3/4 3-42 Amendment No.

INSTRUMENTAT10N F.1RL_.DflEGIl0N._lhslRaiLETAT 108 LltllIING GONDLI19N EDREERAIl0N __ ..

3.3.3.8 As a minimum, the fire detection inst rumentation for each fire detection zone shnwn in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.#

AGIl03:

With one or more of the fire detection instrument (s) shown in Table 3.3-11 inoperable:

a. Within I hour establish a ftre watch patrol to inspect the zone (s) with the inoperable instrument (s) at 1 cast once per hour.

Fire zones located inside primary containment are exempt irom this requirement during Modes 1 and 2.

b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Spc.srication 6.9.1, prepare and submit a Special Report to the r.. ya ; m o .n pursuant to Specification 6.9.2 within the next 30 lm v lining the action taken, the cause of the inoperability and the p ans and schedule for restoring the instrument (s) to OPERABLE status.

c. The provisions of Specification 3.0.3 are not applicable.

EllRYI1LLANGf._REqu1REMENIs 4.3.3.8.1 Each of the above required fire detection instruments shall be demonstrated OPERABhE at least once per 6 months by performance of a CilANNEL FUNCTIONAL TEST.*

4.3.3.8.2 The NFPA Code 72D Class A supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once por 6 months.*

4.3.3.8.3 The non-supervised circuits between the local panels in Specificat.lon 4.3.3.8.2 and the control room shall be demonstrated OPERABLE at least once per 31 days.

1. The fire detect. ion instruments located wit hin the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

• The minimum number of fire dntectors and circuits required inside the containment shall be funct.lonally t.ested during each cold shutdown exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed during the previous six months.

All fire detectors located inside the containment and their associated circuits shall be tested during each refueling outage.

ARKANSAS - UNIT 2 3/4 3-43 Amendment No. 22,

INSTRUMENTATION RADIDACTIVE GASEOUS ErrLUENT MONITORING INSTRUMENTATION Litt1IlR0 COSD111DRl0R.Dl'ERAIl0N_ -

3.3.3.9 The radioact ive gaseous e f f luent n... .. i t or ing inst rument a t ion channels shown in Tabic 3.3-12 shall bo OPERAll!.E with their nintm/ trip setpoints set to ensure that thn limits of Specification 3.11.2.1 are not exceeded.

AITLICAILildIII nuring rnicasen via t his pathwny.

. AcT10N1

n. With the following gaseous ef fluent monitoring in-strumentation channels alarm / trip setpoint less con-servative then required by the abovn specification, immediately surpend the relense of radioactivn gnscous effluents motiltored by the affected channel.

1. Wanto Gas lloldup System Nohin Gas Activity Monitor. (during periods of gaseous rniennes.)

2. Containment Purgn and Ventilation System h .,1c Gas Activity Honitor. (during periods of containment building PURGE.)

b. With less than the minimum number of monitoring instrumentation channoin OPERAllLE. take the action shown in Table 3.3-12.

c. Enturn the instruments to OPERABLE status within 30 days or, in lieu of any other report, explain in the next Seminnnual Radioactive Effluent Release Peport why the inoperability was not co:rected,

d. The provisions of Specifications 3.0.3 and 4.0.4 are not applicable.

MRYEILIMCE.EQV11MMIS -

4.3.3.9 Each radioactive gaseous offluent monitoring instrumenta-tion channel shsll be demonstrated 0:rRABl.E by performance of the CilANNEL CllECK SOURCE CllECK, CilANNEL CAI.IBRATION, and CllANNEL FUNCTIONAL TEST at the frequencies shown in Tabic 4.3-12.

ARKANSAS - UNIT 2 3/4 3-45 Amendment No. (p ,N ,

LNSTRlMENTMlO!!

RAI110ACI1YE.110U1D_EEr1UINIJiOR110 RING._INSIEUENIAIl0S L111111HQ CONDLT10LFDLDEERAI10N..

3.3.3.10 The radioactive liquid effluent monitoring inetrumentation channels shown in Table 3.3-13 shall bc OPERABl.E with their alarm / trip sntpoints not to ensure that the limits of Specification 3.11.1.1 are not exceeded.

AITL]EAh1Ll[Y.1 During rolonnes via this pathway.

ADTION:

a. With a radioactivo liquid offluent monitoring instrumentation channel alarm / trip sotpoint 1 css conservative than required by tho'above specification, immndiately suspend the rolcano of radioactive liquid offluents monitored by the affected channel, until the set point is changed to an acceptable conservative valun.

b. With less than the minimum number of monitoring instrumentation channols OPERABLE, take the action shown in Table 3.3-13.

c. Return the instruments to OPERABl.E status within 30 days or, in lieu of any other report, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected.

d. The provisions of Specifications 3.0.3 and 4.0.4 are not applicablo.

SURVEl'. LANCE rey ;lREMENTS 4.3.3.10 Each radioactivo liquid of fluent m 4toring instrumentation channel shall be demonstrated OPERABLE by per ..aance of the CifANNEL CilECK, SOURCE CilECK, CllANNEL CALIBRATION, and CilANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-13.

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ARKANSAS - UNIT 2 3/4 3-54 Amendment No, M , N ,

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

-_ _ ~ _ _ .

1 9

.REACTox_C001. ANT SJSTrg 3

JLiJalo t STRUGIURhL lNTLUR1D ASMLCDDLCLASS.L_2_AND_LC0tfrDNENIS  !

LlulTING_C0hD1110N20lL0fLRAT10N___

3.4.10.1 The structurnt inte3rity of ASME Codo Class 1, 2 and 3 components shall bn maintained in accordanen with Specificat ion 4.4.10.1.

AEfLICABIL1H : Ahh MODES AGIIOR:

n. With the structural integrity of any ASME Codo Class 1 component (s) not conforming to thn abovo requirements, restorn tha structural integrity of the af fected component (s) to within its limit or isointo the af fected component (s) prior to increasing the Ronctor Coolant System temperaturo morn than 50'F above the minimum temperaturn required by NDT considerntions,

b. With the structural integrity of any ASME Codo Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the af fected component (s) prior to increnning the Reactor Coolant System temperaturn nbove 200'F.

c. With the structurnl futegrity of any ASME Codo Class 3 component (s) not conforming to the abovo requirements, restore the structurn1 integrity of the af fected component to within its limit or isolato the af fect ed component f rom service.

SEY11LL8KCLREQVIRfJfENIS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywhool shall bo inspected por the recommendations of Regulatory Position C.4.b of Regulatory Guido 1.14. Revision 1, August 1975.

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ARKANSAS - UNIT 2 3/4 4-26 Amendment No.

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

EANLHEIEM 3/iti7.9 SEALED _SOURCILCONIAlilNAIl0N Li!11IING CDED1110M.IOK.Di'ERATION 3.7.9.1 Each scaled source containing radforective materInl nither in excess of 100 microcurles of beta and/or gnmma emitting motorial or 5 microcuries of alphn emitting material shall be frnn ' 2 0.005 microcuries of removabin contamination.

Al'51CABILITYi At all times.

ACTION;

n. Each scaled sourcn with removable contamination in excess of the nbove limit shall bn immediat ely withdrawn f rom use and:

1. Either dncontaminated and repnited, or

2. Disposed of in accordance with Commission Regulations,

b. The provisions of Specification 3.0.3 are not applicabin.

EAVE 1LLANCLREQUIREENIS 4.7.9.1.1 Ical_ReattitcEnta - Ench scaled source shall bn instod for lenkngo and/or contaminr4 tion by:

n. The licensco, or

b. Other persons spncifically nuthorized by thn Commission or an Agreement Stato.

- The test method shall havn a detection sensitivity of at lenst 0.005 microcuries 79r test samplo.

4.7.9.1.2 lest Ftrauencies - Each category of scaled sources (excluding startup sources and fission detectors previously subjected to core flux) shall bn tested at the f requencies described below.

l n. Equrces in usa - At, least once pot six months for all senled l sources containing radionctive material:

ARKANSAS - UNIT 2 3/4 7-27 Amendment No.

I PLANLSISIDiS 3Lhh10_ FIRLStil'IESfl0N_SISIEMS EIRILEUrl?ESSION_WAIEILSYSILM L111111NLGOND1Il9N_fDLOPERAIl0N._ _ _ . _ . _

3.7.10.1 The fire suppression watnr system shall bn OPERAfthE with;

n. Two high pressurn pumps, ench with a cepacity of 2500 ;;pm, with their dischargn nligned to the f i re s'apps oss ion hender .

b. An OPERABhn flow pnth capnhin of t r. king suct ion f rom the Daidnnelle Reservoir and transferring thn water through distribut ion piping with OPERABl E sect f onalizing cont rol or isoint.f on valves to the ynrd bydrant curb valves nnd the first valvo abend of the water floi. alntm device on each sprinkler, hoso standpipo or sprny system riser required to be OPERABLC por Specifications 3.7.10.2 nr.d 3.7.10.3.

APPLICAllLIY: At a11 times.

AGIIDS:

a. With one pump inoperable, restorn thn inopornhin equipment to OPERABht status within 7 dnys or, in lieu of any other report required by Specification 6.9.1, preparc and submit a Specint Report. to the Commission pursuant to Specifiention 6.9.2 within the next 30 dnys outlining the planu and proceduren to be used to providn for the loss of redundancy in this system. The provisions of Specification 3.0.3 are not npplicabin. l

b. With the firn suppression water system otherwinn inopernble:

1. Establish a Sackup fire suppression watnr system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2. Submit a Special Report in accordance with Specificntion 6.9.2; n) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgrara cr facsimile transminston no later than the first working day following the event, and ARKANSAS - UNIT 2 3/4 7-29 Amendment No.

1 l

f1 ANT SYSTEMS l

SPRAY AND/OR SPRINKLER S STEMS L1HlHSLCDNDin0LEOR_QT!;RAn0N 4

3.7.10.2 The following spray and/or sprinkler systems shall bn OPERADLE:  !

a. Emergency Diesel Cencrator Rooms f

Room 2093 - Einv. 369' l Room 2094 - Elev. 369' i

b. North Penetration Arcas, insido containment Elev. 386' Elev. 374' 6"  !

c. South penotratJon Arcas, inside Containment  ;

Elev. 386' <

31ov. 374' 6"

d. tiorth Penetration Room, Reactor Auxiliary Duf1 ding ,

Eley. 386' Elev 374' 6"

e. South Penetration Room, Reactor Auxiliary Building Elev. 386' '

Elev 374' 6"

f. Cablo Spreading Room - Elev. 372'

g. Diesel Fuel Storago Vaults APPLICABILITY: Whenev6r equipment in the spray / sprinkler protected areas is required to bo OPERABT.E.

ACTION: .

n. With one or more of the abovo required spray and/or sprinkler systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected arca(s) within I hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a SP 'fal Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and '

the plans and schedule for restoring the systes,to OPERABLE status.

b. The provisions of Specificatfor. 3.0.3 are not applicabin. l L

ARKANSAS - UNIT 2 3/4 7-33 Amendment No.

_ . ~ . . _ . . . _ . _ . _ . ._._ __ _ _ , . _ _ . _ . _ , . _ _ _ _ _ _ _ _ _ _ . _ _ , , , . _ _

PLAMT SYSIIJiS

, ELEILILOSE_11AI1OfiS i

L111111NLC0hD1Il0N EOR _0fERAIl0N i

3.7.10.3 The firo hoso stations shown in Tablo 3.7-7 shall bo OPERABhE. )

AE111.CAH1hlII: Whenover equipment in the areas protected by the fire hose stations is required to bc OPERABLE.

l AGIl08:

i

n. With one or more of the f aro hoso stations shown in Table 3.7-7 inoperable, toute an additional equivalent capacity (f ro hose to the unprotected aron (n) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. The provisions of specification 3.0.3 are not applicablo.

l l

l SVRYIILLANCILREQVIRfdiLNIS 4.7.10.3 Each of the fire hose stations shown in Tablo 3.7-7 shn11 be demonstrated OPERABLE:

a. At 1 cast once por 31 days by visual inspection of the station to  ;

casure all required equipment is at the station.

b.'At least once por 18 months by:

l l

1. Removing the hose for inspection and re-racking, and  ;

I

2. Replacement of all degraded gaskets in couplings.  ;

c. At least once por 3 years by:

t I

i 1. Partially opening each hc30 station valve to verify valvo OPERABILITY and no flow blockago.  :

i

2. Conducting a hose hydrostatic test at a pressure at least {

50 psig greater than the maximum pressure available at that  :

I hoso station.

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ARKANSAS - UNIT 2 3/4 7-35 Amendment No.

w ---n,+ -ww,,_.n. * - ,,w-.g-my -.e-. -s--www--.-+w-mme4,r,-er,-r-w-,

, ,em.,-en.-e,me-v---- ,-wm r n r , , ~ - -- n m w

PLANT _ SYSTEMS 21,LLll... FIRt_ BARRIERS L1tilIIC_ CORD 1I1Ml0R 0tERAIl0F 3.7.11 All fire barriors separating sainty related fire areas or separating portions of redundant safe shutdown systems required in the event of a fire shall be OPERABLE.

AffLLCADlLLI.Y At all times.

AGIl0N:

a. With one or more of the above fire barriers inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either

1. Establish a continuous fire watch on at least one side of the affected fire barrier, or

2. Verify the OPERABILITY of the fire detectors with control room alarm on at Icast one side of the af fected barrier arid establish an hourly (fro watch patrol,

b. The provisions of Specification 3.0.3 are not applicable. l E RYEILLANCE REQRIREliENIS 4.7.11 Each of the above required fire barriers, including scaling devices, aball be verified OPERABLE by:

a. Performing a visual inspection of each fire barrier (not including penetration seals) at least once per 18 months.

b. Prior to returning a fire barrier to OPERABLE status following repairs or maintenance by performance of a visual inspection of the affected fire barrier (s).

c. Performing a visual inspection of each fire door, fire damper and associated hardware at least once por 18 months. ,

I d. Performing a visual inspection of at least ten percent of l

each type of scaled penetration at least once per 18 months.

l If the penetration is determined to be in0perable, declare the affected barrier inoperable and perform a visual inspection of an additional ten percent of the' degraded typo

, of sealed penetrations. This inspection process shall continue until a ten percent sample with no visually apparent adverso degradation has been completed or until all required sealed pentrations of the degraded type have been inspected. Samples shall be selected such that each penetration seal will be inspected at least once per 15 years.

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. ARKANSAS - UNIT 2 3/4 7-37 Amendment No. $$,

KEEUEldRG._OfLEATIONS EUE L J1ANDh1NG..AKLA_XENIILAIl0N.li1EIEd hir11IING_CONDJIl0N10R_Ol'IRAl10N__. _ _ _

3.9.11 The fuel handling aren vent tlnt ion system shnll be operating and dincharging through the llEPA filters nad charcoal ndsorbers.

AITIdL WRin Whenever irrndtnted fuel is being moved in the storage pool and during crane operation with londs over the storage pool.

AGIlON:

n. With the fuel handling nren ventila'. ion syatem not operating, suspend all operations involving movement of fuel within the spent fuel pool or crnne operation with lands ovnt the npent fuel pool until the fuel handling aren ventilntion syst em is reat ored to operation.

b. The provisions of Specification 3.0.3 nre not npplienble.

SVMLILLANCE_REQUELMENIH 4.9.11.1 The fuel handling aten ventilation system shall be determined to be in operation and discharging through the llEPA filters and charcoal adsorbers at least once por 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.9.11.2 The fuel handling aren ventilation system shall be demonstrated OPERAhhE at the f ollowing frequencies when irradinted fuel is in the storage pool:

n. At least once per 18 months or (1) af ter any st ructurni maintenance on the llEpA filter or charcoal adsorber housings, or (2) following painting, fire or chemical relense in any ventilation zone communicating with the system by:

1. Verifying that t he ventilation system satisfies the inplace testing acceptance criterin and uses the test procedures of Regulatory Positions C.5.n, C.5.c and C.S.d of Regulatory Guide 1.52. Revision 2, March 1978, and the system flow rate is 39,700 cfm i 10%.

1 ARKANSAS - UNIT 2 3/4 9-12 Amendment No.

214 di RAD 10ACUYE EEELVENIS 3/4. IL1...LlWID EFFLVENIS LililIING_COND1IIDLIPR Di'ERAI10N )

l 3.11.1.1 The concentration of radioactivo material rolcased from the sito j in liquid offluents to the dischargo canal shell be limited to the concent rations speciflod in 10 CFR Part 20, Appendix B. Tablo 11. Column 2 for radionuclidos other than dissolved or entrained nobin gases. For  !

dissolved or entrained noblo gases, the concentration roloosed shall bo limited to 2 x 10-' - pC1/ml. ,

AEI'LICA111L1111 At a11 timoa.

ACTION:

a. With the concentration of radioactivo materin) roloaned exceeding the abovo limits, immediately initiate actions to rostoro concentrations to within the abovo limits. Provido notification to the Commission within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> nn:1 in lieu of any other ,

report, submit a Specini Report pursuant to Specification 6.9.2.h within 30 days.

b. The provisions of SpecificnLion 3.0.3 aro not applicable.

EURYEllLANCLREQNlREtiENIs 4.11.1.1.1 Radioactivo liquid wastes shall be sampled and analyzed ,

according t o the sampling and analysos program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyson shall be used in accordance with the methods in the ODCH to assure that the concentrations at the point of relcano are maintained within the limits of Specification 3.11.1.1.

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l ARKANSAS - UNIT 2 3/4 11-1 Amendment No. ff, i

L._ - ,- _ . . _ _ ___ _ _ _

EAD10AGI1YE EITLM!i DDBE L181IINQ_ CORD 1Il0M 101LorERAT108._ .

3.11.1.2 Thn doso commitment to a 11EHilER OF TilK PUlth1C f rom radioactivo entorials in liquid offluents rolcased from ANO-2 to the dischargo canal i

shall bn limitad:

n. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equn1 to 5 mrom to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to lesa than or equal tc 10 mrom +o any organ.

APPLICABILITYt At all times.

ACT10Ni

n. k'ith thn calculated doso from thn release of radioactivo materials in liquid offluents exceeding any of tho abovo limita, in lieu of any other report submit a Specini Report pursuant to Specification 6.9.2.h within 30 days,

b. The provisions of Specification 3.0,3 nro not applicable.

HRYLILIANCILEEMEt1ENIs 4.11.1.2 Dnan_.CAltulalinns. Cumulativo doaa contributions from liquid et fluents shall be determined in accordance with t'nn ODCM at least once per 31 days.

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ARKANSAS - UNIT 2 3/4 11-4 Amendmont No fi$,N ,

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EARIDAGLLYLE112!ElilS L10u11LRADh'ASIE_1EEATHENT Lin1IINQ 30MDIT10N JOR 01'ERAIl0N _ __

3.11.1.3 The 1,1 QUID R,0 WASTE TREATMhNT SYSTEM shall be used to reduce the radionctivo materials in liquid wastes prior to thnir dischnrge when the projected doses due to the liquid offluent, f rom ANC-2 to the discharge ennni, would exceed .18 mrom to thn total bcxty or .625 mrem to any organ in any calendnr quarter.

AITLICAlllLIILL At. all t imes.

AGIl0N:

n. With radionctive liquid wanto being discharged without trentment and in excess of the above limits, jn lieu of any other report, submit a Special Report pursunnt to Spoci ficat ion 6.9.2.h within 30 dnys.

b. The provisions of Specif f ention 3.0.3 nre not applienble. l SURYEILLANCE_REQUIREMENIS _ _ .-

4.11.1.3.1 Doses due to liquid releases shall bn projected at lenst once por 31 days in accordance with thn DDCM.

1 ARKANSAS - UNIT 2 3/4 11-5 Amendment No, ff , H ,

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

RADI0 ACTIVE EFFLUENTf LIQUID _.fl0LDUP TANKS

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LinlHND.X0SD1Il0N_IDR_Ql'IRAIl0N 3.!S.I.4 The quantity of radioactivo matarial contained in nach unprotected outside temporary radioactive liquid storago tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

l APPLICADILIT h At al1 times.

ACTION:

a. With the quantity of radioactive matnrfal exceeding the abovo limit, immediately suspend all additions of radioactive material to the af fected tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, i

b. The provisions of Specification 3.0.3 are not applicablo.

EURyEILLANCI. REQ'11EEnENIS 4.11.1.4 Tho quantity of radioactivo material contained in each unprotected outsido temporary radioactivo liquid storago tank shall be j datormined to be within the above limit by analyzing a representative sample of the contents of the tank at 1 cast enco per 7 days when radioactive matoriala arn being added to the tank.

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• Tanks included in this specification are those outdoor temporary tanks that do not have 1) liners, dikes or walls capable of holding the tank contents, or 2) tank overflows and surrounding area drains connected to the LIQUID RADWASTE TRFATHENT SYSTEM.

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l l ARKANSAS - UNIT 2- 3/4 11-6 Amendment No. 67, l

RALROACILYE ErrLUM IS 2/4.111L_.DASE0VS EFECUENIS DDSL FATE LIM 1IING_CREIl0N.E0!LOCIRAIIRN -_ _ _ _

3.11.2.1 The dose rato due to radioactive matnrialr. released in gnacous offluents from the site to UNRESTRICTED AREAS (son Figure 5.'-3) shall be limited to the following:

a. For noble gases: 1.c s s than or equal to thn 500 mrom/yr to the total bcxty and less than or equal to 3000 mrom/yr to the skin,

b. For icxtine-131, for tritium and for all radionuclides in particular form with half lives greater than 8 days: Less than or equal to 1500 mrom/yr to any organ.

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

AE111CABILITY: At all times.

ACIl0N:

5. With the dose rate (s) exceeding the above limits, without delay restorn t he release rate to comply with the above limit (s).

b. The provitfons of Specification 3.0.3 are not applicablo, t

SMRYELLLASCE_REQMIREMENIS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be dotormined to be within the above limits in accordance with the methods and procedures of the ODCH.

4.11.2.1.2 The doso rato due to lodino-131, tritium, and all radionuclides i in part iculato form with half-lifes groator than 8 days in gaseous of fluents shall be determined to be within the above limits in accordance j with the methods and proc.-dures of the ODCH by obtaining representative

samples and performing analyses in accordance with the sampling and i analysis program specified in Table'4.11-2.

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ARKANSAS - UNIT 2 -

3/4 11-7 amendment No. M ,7/,

i RADIDACTIVE ErrLUENIS DOSE - NOBLE GASES t L1HIIING.CRED1110N rOR_OfERATJQN_ _

3.11.2.2 The dono due to nobic gases released in gaseous ef fluents from ANC-2 to UNRESTRICTED AREAS (Sco Figure 5.1-3) shall be a During any calendar quarter, less than or equal to 5 mrads for  ;

gammt radiation and less than or equal to 10 mrada for beta radiation, and

b. During any calendar year, Insa than or equal to 10 mrada for gamma radiation and loss than or equal to 20 mrads for beta radiation. I APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from radioactivo noble gases in gaseous effluents exceeding any of the abovn 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 applicabin. ,

t EVM'AILLANCE_REQUIREHEMIS 4.11.2.2 Doso Calculations. Cumulativo dose contributions for noble gases for the current calendar quarter and current calendar year , hall be determined in accordance ith the ODCH at least once per 31 days.

t ARKANSAS - UNIT 1 3/4 11-10 Amendment No, fpipJ,

EAD10AGIn'L12fLEMIS HRE - IDDINE-11L_IR111RL_AND_Roul0NUCLIDESJN_l'ARIIC11LAIIdOM LIMinNG EOND1Il0LfDLOl'ERAIl0N 3.11.2.3 The dono to a HENDER OF TIIE PUHb10 from lodine-131, from tritium, and f rom all radionuclides in particulate form with half-lives greater than 8 days in gaseous of fluent s released f rom ANO-2 to UNRESTRICTED ARCAS (see Figuro 5.1-3) shall bot

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 mroms to any organ.

APPLICABILITY: At. all t imos.

ACTION:

a. With the calculated dono from the release of iodine 131, tritium, and radionuclidos in particulato form with half-lives greator than 8 days, in gaseous offluents exccoding any of the abovo 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.

MRYEILLANCE REQQ1REENIS 4.11.2.3 Dose Calculations. Cumulativo doso contributions for the current calendar quarter and current calendar year for fodine 131 tritium, and radionuclides in particulato form with half-lives greator than 8 days shall be determined in accordance with the ODCH at least once por 31 days.

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ARKANSAS - UNIT 2 3/4 11-11 Amendment No. 6$,PJ,74, 1

EADX0ACT1YL_EffLVENTS GASE0VLEADMASTE TREATHERI L1HLT.1NG S M 1HDblJDR DfERATl0N _ . _ _

3.11.2.4 The VENTILATION EXilAUST TREATHENT SYSTEMS shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous of fluent doses f rom ANO-2 to UNRESTRICTED AREAS (sco Figure 5.1-3) would exceed .625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter; or when the projected doses due to iodine-1:>1, tritium, and radionuclides in particulate form with half-lives greater than 8 dnys would exceed 1.0 mrom to any organ over a calendar quarter.

APPLICABILITY 1 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.

51!RYEILLAE!LREQRIREMENIS 4.11.2.4.1 Domes due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCH.

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l ARKANSAS - UNIT 2 3/4 11-12 Amendment No. (0,$J,74,

EADlDACI1YE_E1I1URiTE GASEDULEADMAEIL_IKTAIENI L1111T114G_COND1110NJDR SFER4110N __

3.11.2.5 When degnalfying the renctor coolant system, the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radianctive ir.nterial in gnscous wasto prior to their dischnrge when the projected gnseous ef fluent doses for ANO-2 to UNRES1RICTED AREAS (c.co rigure 5.1-3) would exceed .625 mrad for gamma rndfation and 1.25 mrnd for beta radiation in any calendar quarter.

AIT11CAh1LIIlt At all times.

AC110N1

n. With gaseous wastn 1 eing discharged without treatment and in excess of the above limits, in lieu of any other report, submit a Specini Report pursunnt to Specification 6.9.2.h within 30 days.

h. The provisions of Specification 3.0.3 nre not app 11 cabin.

EURYIILL6SCE_EEQUlREENIS 4.11.2.5.1 Doses dun to gnscous relenses f rom the site shall be projected at least once per 31 days in accordance with the ODCH.

ARKANSAS - UNIT 2 3/4 11-13 Amendment No. (p,PJ,74,

i RAD 10AC11YE.IIILVEND DAS_STORAG U ANKS L181IING COND1710N 1DK_011 RAIL 0N 3.11.2.6 The quantity of radianctivity contained in each gas storagn tank shall be limited to less than or equal to 300,000 curies noblo gases (considered an Xn-133).

AITLICABlh1III At a11 t imes.

bCIlDNi

n. With the quantity af radioactivo material in any gas storage tank exceeding the above limit, immediately sispend all additions of radioactivo material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduco the tank contents to within the limit.

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b. The provisions of Spocification 3.0.3 arn not applicabin.

EVEYEILLANCEJEQUlREMENIS 4.11.2.6 Tho quantity of radioactive material contained in each gas storagn tank shall bn det ermined to be within thn abovn limit at Innst onen per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive matorials arn bning added to the tank and the reactor coolant activity exceeds thn limits of Specification 3.4.8.

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, ARKANSAS - UNIT 2 3/4 11-14 Amendment No, ff, l ,

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

RADJ0 ACTIVE EFFLUENTS EXfLQSlyE_SAS MIXTURE l l

Lili1IING_.G.0SD1Il0LIpfLOPIRAHOS 3.11.2.7 The concentrat.fon of the hydrogen / oxygen shall be limited in the waste gas storage tanks to Region "A' of Figure 3.11.1.

AffLICABILITY: At all times.

ACTION:

a. When the concentration of hydrogen / oxygen in the waste gas storage tanks enters Region "B" of Figure 3.11.1, corrective action shall be taken to return the concentration values to Region "A" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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b. The provisions of Specification 3.0.3 are not applicable. ,

E.URYTJ EANCE EEQu1REMENT.S 4.11.2.7 The concentration of hydrogen / oxygen in the waste gas holdup system shall be determined to be within the above limite. with the waste gas system in operation, by continuously monitoring with the hydrogen / oxygen monitors required OPERAHLE by Table 3.11-3.

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i ARKANSAS - UNIT 2 3/4 11-14a Amendment No. (J, 1

_ , - . . _ ,--- .._ , _m , -

RAD 10AGIlXEJ1TLVERIfi JLblL4 SQL11LRAD10ACIINEJAfi1E LIM 1IIND_COND1Il0NJOR_DI:ERAIIV1. . . _ - ..

3.11.4 The solid radwnste system shall ho used in accordance with n PROCESS CONTROL PROGRAM to process wet rndionctive wastes to meet shipping and burial ground requirements.

ALTLICAlllL11Y2 At n11 times.

ACIl0H1

n. With the provisions of the PROCESS CONTRob PROGRAM not antisfied, suspend shipment of defectively processed or defectively packaged nolid radioactive wastes from the sito.

b. The provisions of Speciftention 3.0.3 nro not npplienhle.

FVKYLILLANCEJIQUIREMENIS 4.11.4 Propor solidification of wot radionctive waste shall be verified in accordance with the surveillanco requirements of the Process Control Program.

ARKANSAS - UNIT 2 3/4 11-16 Amendment No. (0,9J,

J/AlL_RADIDLWICALIM1ROSMLNIAkliONIIDRING Liti111NUONULIIDUR1LDl'LRAIlpM_(ContinuedL

c. With milk or fresh Icafy vegetable samples unnvailnble from any of the sample locations required by T;blo 3.12-1, identify locations for obt aining repincoment samples and add them to the radiological environmental monitoring progrnm within 30 days.

Tho specific locations from which snaples were unnvnilnblo may then be deleted f rom the monitoring program. Identify the causes of the unnynilabill'y of samples and identify the new location (s) for obtaining replacement samples in the next Semit.anual Radioactive Effluent Relear.o Report and also include in the report a revised tab 1n for the ODCM reficcting the new location (s).

d. The provisions of Specificat ion 3.'s.3 are not npplicabic.

HERILLANCI_EEQVIEDiENIs 4.12.1 The results of analyses performed on thn radiological environmental monitoring samples shall be summarized in the Annun Radiological Environ-mental Report.

ARKANSAS - UNIT 2 3/4 12-2 Amendment No. ff,H ,

Raul % QG.ICAL ENY1RONtiENTAL MOSITok1hD E_122 2 1 ANILUSI_CIMES LIMUNG_G0XILlH0lL1'OR 01'LRAUDF _

3.12.2 A land uso consus r, hall bn conducted and shall identify the location of the nenrest milk animal, the nearest residence, and thn nearest garden

• of greater than 500 squas e feet producing f resh leafy vegetables in each of the 16 meteorological sectors within a distance of fivn miles.

AE111CADILITY: At all times.

A0110Ht

a. With a land uso consus identifying a location (s) which yicids a calculated dose commitment due to 1-131, t ritium, and radio-nuclides in particulate form grester than the values currently being calculated in Unit 2 Specification 4.11.2.3, submit lo-cation description in the Semiannual Radioactivo Effluent Rolense Report por Specification 6.9.3.

b. With a land use census identifying a location (s) which yinids a calculated doso commitment (via the sample exposure pathway) greater than at a location from which samples are currently being obtained in accordance with the Speellication 3.12.1, identify the new location in the Semiannual Radioactivn Effluent Release Report por Specificat ion 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 doso commitment (via the samo ex~)suro pathway) may be deleted from this monitoring program af ter October 31 of the year in which this land usn census was conducted,

c. The provisions of Specification 3.0.3 are not applicable, l SURYUldWiCLREQEIREENIS 4.12.2 The lanc' 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, aeriel survey, or by consulting local agricultural authorities. The results of the land use census shall be included in the Annual Radiological Environment Report.

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

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ARKANSAS - UNIT 2 3/4 12-8 Amendment No. 4,H,#,

RAD 101M11 CAL _ENY1FDSM ENIALJiON110RI NG 3/h12t]_.1NIERIABORAIDRY_CDdfARISON_ PROGRAM L1HIIlNG.JDSDlIl0N_IDK_Ol'ERAIIRN__ __. -

3.12.3 Analyses shall bn performed on radionctivn materints supplied an part of thn Interinboratory Comparison Pror,rnm which hns been approvnd by NRC.

AEl'LICA!!1111111 At n11 tiens.

ACTION 1

n. With analyses not being performed as rerpiired above, report the corrective actions taken to prevent a recurrence to the Commission in the Annunt Radiological Environmental Report,

b. The provisions of Specification 3.0.3 nrn not applienbin. l SulWfdlJ.ANCE_REQtuREMENIS 4.12.3 Tha results of analyses performed as part of thn above required Interinboratory Comparison Program shall be included in the Annual Radiological Environmental Report.

ARKANSAS - UNIT 2 3/4 12-9 Amendment No. ff, H ,

3/ L L. R tLICA!1R I U DMLS - - . .

3.0 1Lt hrotjgh 3.0.4 Establish the gnneral requirements applicable to 1,imiting Conditions for Operrit tori. 'thesn r e<pii rernririt s a t n beined ori tiio requirements for I.imiting Conditions for Operation stated in the Codn of l'ederal Regulations, 10 CFR 50.36(c)(2):

"!,fmiting conditions for operation are the lowest functional capability or performanco invels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, thn licensen shall shutdown the reactor or follow any remedial ACTION permitted by th Technical Spncification until the condition can be mot."

3.0.1 Establishon the Applicability statement within each individual specification as the requirement for when (1.n., in which OPERATIONAL. MODES or other specified conditions) conformancn to the I.f mit ing Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial monsures thnt must be taken within specified timo limits when the requirement s of a Limit ing Condition for Operation are not met.

There are two basic typna of ACTION requiremonts. The first specifica the remedial recasures that permit continued operation of the facility which is not further restricted by the timo limits of the ACTION requirements, in this case, conformanco to the ACTION rnquirements provides an acceptablo level of safoty for unlimited continued operation as long as the ACTION requirement s continue to bo mot . The second type of ACTION requirement specifies a timo limit in which conformanco to the conditions of the bimiting Condition for Operation must be met. This timo limit is the allowable outago timn to restorn an inoperable system or component to OpERABhE status or for restoring parameters within specified limits. If these ACTIONS a-o not completed within the allowable outagn timo limits, a shutdovn is required to place the facility in a mode or condition in which the specification no longer applies, it is not intended that tho shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from servico in lieu of other alternatives that would not result in redundant systems or components being inoperable, i

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l ARKANSAS - UNIT 2 113/40-1 Amendment No. J7,

I! ASIS A entinuejl l

The specified tien limits of the ACTION requirement s are applicable from the point in timo it is identified that a Limiting Condition for Operation is not mot. Thn t ten limits of the ACTION requirement s nrn also applicabin when a system or component is removed from service for survnillance testing or investigation of operntlonal problems. Individual specificntions may include n specified tien limit for the completion of a Surveillance Requirement when equipment is removed from service. in this caso, thn allownble outage tien limits of the ACTION requirements arn applienbin when this limit expires if the surveillanco hns not been compinted. Whnn a shutdown is required t o comply wit h ACTION requirements, the pinnt may hnyn entered a mtxle in which a new specification becomes npplienh!c. In this case, the timo limits of the ACTION requirements would apply from the point in time that the new specification bncomes applienble if the requiremento of the Limiting Condition for Opnration arn not ent.

3.0.2 Establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Opernt ion are not met and the associated ACTION tequirements havn not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remndini mensures of the ACTION requirements is not required when complinnen with n I.imiting Condition for Operation is restored within the tiac intervn1 speciffed in the associnted ACTION requirements.

3.0.3 Establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by tho assocint ed ACTION roouirements. The purposn of this specification is to delinent e the time limits for placing the unit in a safe shutdown mode when plant operation cannot be maintained within thn limits for safe operation defined by the I,imiting Conditions for Opnration and its ACTION requirements. It is not intended to bn used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

One hour is allowed to prepare for nn orderly shutdown beforn initiating a change in plant operation. This time permits the operator to coordinato tho reduction in electrient generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower modes of operat fon permit the shutdown to proceed in a controlled and orderly manner that is wnll within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potentini for a plant upset that could challenge snfoty systems under conditions for which this specification applies.

ARKANSAS - UNIT 2 B 3/4 0-la Amendment No. O ,

MSELLWnthuti)

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are cornpleted, the shutdown may be terminated. The time limits ol' the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION requirements have been rnet or the t ime limits of the ACTION requirements have not expired, thus providing an allowance for the complet ion of the required ACTIONS.

The tien limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in the COLD SilVTDOWN HODE condition when a shutdown is required during the p0WER OPERATIONS MODE of operation. If the plant is in a lower mode of operation when a ahutdown is required, the time limit for reaching the next lower mode of operation applies. Ilowever, if a lower mode of opnration is reached in less tien than allowed, the total allowable time to reach COLD SilVTDOWN or other applicable mode, is not reduced, l'or example , if il0T STANDIiY is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach Il0T SilUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach Il0T SilVTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Thorofore, if remedial measures are completed that would permit a return to p0WER OPERATION, a penalty is not incurred by having to reach a lower mmic of operation in less than the total time allowed.

The same principle applies wit' regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a mode or condition of operation for another specification in which the requirements of the bimiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the dif ference may be added to the allowable outnge time limits of the second specification, llowever, the allowable outage time limits of ACTION requirements for a higher mode of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower mode of operation.

The chutdown requirements of Specification 3.0.3 do not npply in modes 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

3.0.4 Estab:ishes limitations on mode changes when a Limiting Condition for Operation is not met. It. precludes placing the facility in a higher mode of operation when the requirernents for a Limiting Condition for Operation are not mot and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in modes were permitted. The purpose of this specification is to ensure that facility ARKANSAS - UNIT 2 B 3/4 0-lb Amendment No. # ,

l MSIS_Lcontinuedl operat !on is not initinted or that higher modes of operation are not entered when corrective ACTION is being token to obtnin compliance with a specification by testoring equipment to OPERABl.E stntus or parameters to specified limits. Complinnce with ACTION rerpiirements thnt permit continued operat ion of the f acility f or nn unlimit ed period of t ime provides an acceptnbin level of safety foi continued operation without regard to the status of the plant before or after a modo change.

Therefore, in this case, if the requirements for cont inued operation hnvo been met in accordance with the requirements of the specifice4fo , thnn entry into that mode of operation is permissibic. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practico in restoring systems or components to OPERABLE status before pinnt startup.

When n shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in n lower mode of operation. For the purpose of compliance with this specification the term shutdown is defined as a required reduction in mode. .

lad This specification dnlinentes whnt additionn1 conditions must be satisfied to permit operation to continue, consistent with the ACTION stat 9ments for power sources, when a normni or emergency power source is not OPERABl.E. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable avl a system, subsystem, train, component or device in another Givision is inopernbic for another reason.

The provisions of this specification permit the ACTION statements associated with individuni systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associat ed electrical power source. It allows operation to be governed by the time limits of the ACTION statement associated with the 1 imitins; Condition for Operation for the normal or emergency power source, not tia individual ACTION statements for nach system, subsystem, train, component or device that in determined to be inoperable solely because of the inopernhility o r its normni or emergency power source.

For example, Specification 3.8.1.1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> out-of-servicn time when one emergency diesel generator is not OPERABLE.

If the definition of OPERABI.E were npplied without consideration of Specification 3.0.5, all systems, cubsystems, trains, components, and devices supplied by the inoperable emergency power source would niso be inoperable. This would dictato invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation. Ilowever, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable ARKANSAS - UNIT 2 B 3/4 0-Ic Amendment No.

l APPLICABILITY MSES LCDIttitmO omorgency diesel generator instead, provided the other specified conditions are satisfied. In this caso, this would mean that the corre.:ponding normal power source must be OPERABLE, and all redundant systems, subsystems, tcains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least ano norm 1". or ono emergency power sour i OPERABLE). If they are not astis fied, - is rnquired in accordance with this specification.

As a further exa.nple, Specification 3.8.1.1 requires in part that two physically independent circuits between the offsito transmission network and the onsite Class IE distribution system he OPERABLE. The ACTION statement provider a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> out-of-service timo when both required of fsite circuits are not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and 'evices supplied by the inoperable normal power sourcos, both of he c ite circuits, would also bo inoperable. This would dictate invoking in applicable ACTION statements for each of the applicchle LCOs. "0 wever. the provisiot.s of Specification 3.0.5 permit the time limits for continued c peration to be consistent with the ACTION statemunt for the inoperabic normal power sources instead, provided the other specified conditions are satisfied. In this case, this would mean that for one divisica the emergency power source must be OPERABLE (as need be the componenta supplied by the emergency power source) and all redundant systems, subsystema, trains, components and devices in the other division muat be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e., be capable of performing thr'- design functions and have an emergency power source OPERABLE). In c. ar word , both emergency powcr sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisionn must also ho OPERABLE. If these conditions are not satisfied, action is required in accordance with this specification.

In MODES 5 or 6, Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.

ARKANSAS - UNIT 2 B 3/4 0-Id Amendment No. 19

AEPLICABILIII AASIs , , , ,

4.0.1 through 4.0,5 establish the general requirements applicable to Surveillance Requirement . These requirements are based on the Surveillance Requitements stated in the Code of Federal Regulations, 10CFR 50.36(c)(3):

" Surveillance Requirements are requirements relating to test, calibration, tr inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."

4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL H0 DES or other conditions for which the requirements of the Limiting Conditions for Operation apply unicas otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and compenents and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a mode or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL HODE for which the requirements of the associated Limiting Condition for Opnration do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicabic when the Special Test Exception is used as an allowable exception to the requirements of a specification.

4.0.2 establishes the limit for which.the specified time interval for Surveillanca Requirements may be extended. Tt permita an allowable extension of the normal surveillance interval to facilitato surveillance-scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transiant conditions or other ongoing surveillance or maintenance activities. It alsa provides flexibility to accommodate the length of a fuel cycle for sutve.: lances

! that are performed at nach refueling outage and are specified with an 18-month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is based on engineering judgement.and the recognition that the most probable result of any c particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not

, ignificantly degraded beyond that obtained from the specified surveillance l Intervals.

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l l ARKANSAS - UNIT 2 B 3/4 0-2 Amendment No. Jf),

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MSES f continumn 41 0J natablishes thn failurn to perform a Survolllanco Requirement within the allowed surynlllance intnrval, defined by thn provisions of Specification 4.0.2, as a condition that constitutes a failure to mont the OpERADILITY requirements for a bimit ing Condition for Operation. Under thn provisions of this epecification, systems and components nro assumod to ho OPERABid when Survn111nnco Requirements have been satisfactorily performed within the specified timo interval. Ilowever, nothing in this provision is to be const.rund as implying'that systems or components nro OPERABLE when they are found or known to bo inoperabin although still meeting Surveillanco Roqi.irements. This specification also clariffes thas. the ACTION requirnments are applicabin when Survnillanco Requirements havo not been completed within the allowed survoillance intnrval and that the timo limits of the ACTION requirements apply from the point in tien it 18 Identified that a surveillanco has not bonn performed and not at the timo that tho allowed surveillanco int.nrval was excended. Completion of t.ho Surveillar.cn Requiremnnts within tho allownble outagn time limits of the ACTION requirements rostorns compliance with the requirements of Speci ficat ion 4.0. 3. However, this does not. negato thn fact that thn failure to havn performed the survoillanco within thn allowed surynllianco Interval, defined by the provisions of Specificat Jon 4.0.2 was a violation of the OPEdABILITY requirements of a Limiting Condit.lon for Operation that is subject to enforcement action. Furthnt, the failure to nerform a survnillanco within thn provisions of Specification 4.0.2 is a violation of a Technic.nl Specification requiremont and is, thoroforo, o report.abin event under the requirements of 10CFR 50.73(a)(2)(1)(B) becauso it is a condition prohibited by the plant's Technical Specifications.

If the allowable outagn t.imo limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION regnirements, f

'o.g., Specification 3.0.0, n 24-hour allowanco is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillanco Requironents'that havn not been performed. The purpose of this allowanco -is to permit the completion of a surveillanco before a shutdown is required to comply with ACTION

- requirnments or beforo othnr remedial measures would be rnquired that may preclude completion-of-n surveillance. The basis for this allowanco includns consideration for plant condltions, adnqunto planning,

- availability of personnnl, the timo requirnd to perform the surveillanco, ,

- and tbn safoty significanco of the delay in complot.ing thn rnquired surveillance. This' provision also providos a timo limit for the complstion of Surveillance Requirements that becomo applicabin as a consequence of modo changes imposed by ACTION requirements and for completing Survoillanco l Requirements that nro applicablo when an exception to thn rnquiremnnts of Specificat.lon 4.0.4 is allowed. If a surveillanco is not completed within the 24-hour n'llowanen, the timo limits of the ACTION requirements are applicable at that time. When a survnillanco In performed within the 24-hour allowanco and the Survnf11ance Requirements are not mot, the timo limits of the ACTION requirements are applicabin at the time that the surveillance is terminated. If the ACTION requirements are greater than 24 bout s, suf ficient t.imo exists t.o complotn the surveillance.

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ARKANSAS - UNIT 2 B 3/4 0-3 Amendment No.

BASES f cRatinucsD Survnfilanen Rnquirements do not havn to bn performed on inoperable equipment becausn the ACTION requirements dnfinn thn remedial mensurns that apply. However, the Surveillance Requirements hnyn to be mot to demonstrato thnt inopornble nquipmont has been restornd to OPERABLE status, 4.0.4 nstablishes the requirement that all app!!cablo survoillances must be met bnfore entry into an OPERATIONAb HODE or other condition of opernolon specified in the Applicability statoment . Thn purponn of this specificatJon is to ensure that system and component. OPERABib!TY requiremonts or paramotor limits arn mot beforn entry into a modo or co,dition for which thoso systems and components ensure snfo operation of '

thn facility. This provision applins to changes in Ol' ERAT 10 nab H0 DES or other specified conditions associnted with plant rhutdown as well as startup.

Under.the provisions of this specification, the applicablo Survnillanco Requiroments must bn performed within the specified survoillance intnrval to ensure that thn Limiting Conditions for Operation are mot during initial plant startup or following a pinnt outage, l When a shutdown is required to comply with ACTION requirements, thn provision of Specificat.fon 4.0.4 do not apply beconso this would delay placing the facility in a townr mmin of operation.

4.0.5 establishes the requiremont that. Inservien inspoction of ASME Codo Class 1,2, and 3 componnnts and insorvico testing of ASHE Codo Class 1,2, and 3 pumps and valvns shall be performod in accordance with n I pnriodically. updated vnraton of Section XI of the ASME Bollor and Pressurn Vessel Codo and Addenda na required by 10 CFR 50.55n, Thesn rnquirnmonts ,

apply except when relief has boon provided in writing by the Commission. 1 This specification includen a clarification of the frequencies for performing the inservico inspection and test.ing activitins required by Section XI of the ASME Bollnr and Prossurn Vessel Codo and applicabin Addenda. This clarification ja providnd to ensurn consistency in ,

survoillanen intervals throughout Tnchnical Specifications and to removn any ambiguitios relativo to the frnqunncins for performing the requirnd inservice inspection and test.ing activities.

Under the terms of this specification, the mor n rest.rictive requirements <

of the Technical Specifications take procedence over the ASME Boller and Prossurn Vessel Codo and applicabin Addonda. The rnquirements of Specification 4.0.4 to perform survotilanen activitins hoforn entry into an OPERATIONAh HODE or other specified applicability cor.dition takes

'procedence ovar the ASHE Bollnr and Pressurn Vessel Code provision which nilows pumps and valvos to be tnstad up to one wonk after rot. urn to normal ope rn t.i on . And for exnrpin, the Tnchnical Specification definition of OPERABLE dons not allow a graco period bnforn a dnv1ce, that is not capable of performing its specified function, is declared inoperablo and takes precednnce ovnr the ASME Boller and Pressure Vessnl Codo provision which allows a vnivo to bn incapahin of p- forming i ts specified funct.f on for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> beforn being declared inoperable, i

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ARKANSAS - UNIT 2 B 3/4 0-4 Amendment. No.

r-

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