ML20101R562

Amend 161 to License DPR-51,revising TS Based on Recommendations Provided in GL 87-09 Re Applicability of LCO & Surveillance Requirements of TS 3.0 & 4.0

ML20101R562
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/07/1992
From:	Larkins J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20101R566	List: ML20101R562 ML20101R568
References
GL-87-09, GL-87-9, NUDOCS 9207160084
Download: ML20101R562 (48)

Text

, _

e._.

%d M@et76$h,'Ws f M E-J

.. 1. 2 _ -

s.S 4

%n g

Vg

. L UNITED STATES

-1 MN 3:-

/ tr.

O

?

lf)

' NUCLEAR REGULATORY: COMMISSION l WA$mGioN, D.C. M66 fl}

sses*[-

g, f

JNTERGY OPERATIONS INC.

4

' MCKET NO. 50-313

~

n

1t.

6% '

ARKANSAS NUCLEAR ONE. UNIT NO. 1 m

r,, ',

7 ABENDMENT'TO FACILITY OPER8 TING LICENSE b

Amendment No.'161 o

1;c License No. DPR-51 m

a-

-'.i 110 - JThef Nuclear' Regulafory Comission l(the Commission) has 'found' that':

TA;

The application for amendment by Entergy Operations, Inc. (the

? licensee) dated June 27.--1991,- as supplemented December 20,=1991, 4~

complies with the-standards.and requirements'of the-Atomic Energy S'1 JAct of 1954, as;amendedf(the Act),- and the Commission's rules and

^

1 regulations; set'forth in-10.CFR Chapter.I; w

TB; fThe-facility will.Loperate in. conformity with the application, the

~ provisions: of the:Act, and the rules and-regulations of the-a

Co'mmi_ssion;t h

^ C[ There'is reasonableLassurance:- (i) that the activities authorized y@g byfthis: amendment can'be conducted without endangering the health ns Land-safety lof:the public, and (11)1that such activities will be o

g1

s. conducted in complianceiwith the Commission's1 regulations;

+

U

!DJ dThelissua'nce:of;this' license amendment willinot -be inimical to' the c

m 1

R T" icommon. defenseandtsecurity'or to the health and safety of the i[

'public;Landt W&'

LE.

f The fissuanceLof this. amendment isTin accordance with 10 CFR Part 51

~

g'.

of the Comission's regulations and all~' applicable requirements have if

.been~ satisfied.

't l :l9' Y

-~

iN:

m' igW

~

, &i 4 m~

t

,o oc

':t (F

p m

i f

9207160084'920707

. P DR -- ADOCK 05000313.

P:

~

PDR a

\\

tm y._

}

L *w. w

. ~. -

l.

.g :.

'}

i

.t 2.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. OPR-51 is hereby amended to read as follows:

2.

Technical Solcifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 161, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION u-

& John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects - III/lV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of Issuance:

July 7, 1992 k

r

.r..

y y:

'-)

jii w

ATTACHMENT TO LICENSE APiENDMENT NO. 161 FACILITY OPERAT]HG LICENSE NO. OPR-51 DOCKET NO. 50-313 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE PAGLS INSERT PAGES 15a 15a 15b 15b 15c 15c 15d 15e 18 18 18a 18a 450 45g 51 51 53d 53d 53f 53f 53i 531 57 57 59 59 59a 59a 66b 66b 669 66g 66n 66n 660 660 66p 66p

-66q 66q 66r 66r 66u 66u 66v 66v 66w -

66w 66x 66x 66y 66y 66r 66z 66aa 66aa 66bb 66bb 66cc 66cc 66dd 66dd 66ee 66ee 66ff 66ff 67 67 67a 67a 67b 67c 1

I

._-_--__-_--________--__________-_--______-__--_-______-_-_-_____---______--__.--______-__-_____U

7..

l.p..

3;*

==

}.,

y.

REMOVE PAGES 1]iSEBT PAGES 67d 67e 72 72 110tt 110tt 110z2 Il0zz 110bbb 110bbb b

=

D e

d

_ _ _ _ _ - - ~ _ _ - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - -

3 ly

. ;;t '

],

3.

LIMITING _ CON 0!TIntis FOR OPERATION 3.0 LIMITING CONDITION FOR OPERATION (GENERAL)

L 3.0.1 The Limiting Conditions for Operation requirements shall be applicable during the REACTOR OFERATING CONDITIONS or other conditions specified for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation within the specified time interval shall constitute compliance with the i

specification.

In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, no further actions need be taken.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associat.ed Action requirements, within one hour action shall be initiated to place the unit in an OPERATING CONDITION in which the Specification does not apply by placing it, as applicable, in:

F' 1.

At leest HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

At least HOT SHUTDOWN vithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

At least COLD SHUTDOVN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the Action requirements, the Action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications.

3.0.4 Entry into a REACTOR OPEPATING CONDITION or other specified condition shall not be made when the cond,itions of the Limiting Conditions for Operation are not met and the associated action requires a shutdown if they are not met within a specified time interval. Entry into a REACTOR OPERATING CONDITION or other specified condition may be made in accordance with Action requirements when conformance to them permits continued operation of the facility for an unlimited period of tina. This provision shall not prevent passage through or to REACTOR OPERATING CONDITIONS as required to comply with Action requirements. Exceptions to these requirementa are stated in the individual specification.

4 Amendment $7 161 154

~J,r

.n.

f.:..

gp9

.f-f, LIMITING CONQ1 TION FOR _0PERAIl01(centinued), \\ 3.0.5 When a system, subsystem, train, coeponent or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal Tower source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirementa c! its applicab'le Limiting Condition for Operation, providedi (1) its corresponding normal or ttergency power source la CPERABLE and (2) all of its redundant systems (s),~ subsystem (s), train (s), component (s) and device (s) ers OFERABLE; ct likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satis fied, withi*: 2 hours action shall be initiated to plae+. the vnit in.an OPERATING CONDITION in which the applicable Limiting Cond uion for Operation does not appif by placing it, as applicable, in : 1. At least HOT STANDBY sithin the next 6 heut*. 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTDOWN within the subsequsnt 24 hours. This Specification is not applicable in Cold Shutdown or Refuoling Shutdown. OASES 3_.0.1 through 3.0.4 Establish the general requirements applicable to Lietting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal . Regulations, 10 CFR 50.36(c)(2): " Limiting conditions for operation are the lovest functional capability or performance levels of equipment required -for safe op. ration of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shutdown the reactor or follow any remedial Accion permitted by the-Technical Specifien. tion until the condition can be met." 3,0.1 Establishes the ApplicNb111ty statement within each individual Specification at the require, ment for when (i.e., in wnich operational modes or other specified conditions) conformance to the Limiting Conditions for Operation _is required for safe operation,:1 the facility. The Action requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Liniting Condition for t Operation are not met. l There are two basic types of Action requireannu. The first specifies the l- - remedial asamures that permit continued operation of the facility which is not further restricted by the time limits of the Action requirements. In this case, conformance to the Action requirements provides an acceptable level of safety for unlimited continued operation as long am the Action requirements continue to be met. The second type of Action requirement specifies a time limit-in which conforasnce to the conditions of the Lleiting Condition for L Operation must be met. This time limit is the allowable outage time to l 1 Amendwent No. 57,161 15b .) _,A

~ ~ gr 4. s:y f-IMILLtnatimttM } restore an inepetable system or component to GPERABLE status or for restoring parameters within specified !;mits. If these Actions are not ct;mpleted within f-the allowabin outsgm time 11eits, a shutdown is required to place the facility in a mode or condition in which the Specification no longer applies. It is not intended that ths shutdown Action requirerents be used as an operational convenience which permles (routive =Nntary resoval of a system (s) or component (s) fnom sarwiev in lieu of other iternatives that would not result In redundent systees or componenta be Ng inoperable. The specifled time limits of the Action requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not est. The eles limits of the Action requirements are also applicable when a system or component is removed from service for surveillence tescing or investigation of operational problems. Individus1 Specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service. In this case, the allowable outage time limits of the Action requi*ements are applier.ble when this limit expires if the surveillance has not been completed. When a shutdown is required to coceply with Actioa requiremants, the plant say have entered a modw in which a new specification bee nes applicabl9. In this case, the time limits of the Action requirements would r.pply free the point in time that the new specification becomes applicable if the requiroents of the Limiting Condition for Operetion are not met. 3jfj Fstab'.ishes that noncompliance with a Specitication exists when the tr.quirement s of the Limiting Condition for Opera Lon are not set and the associated Action requirements hsve not been implemented within the specified cime interval. The purpose of this specificatien is to clarify that (1) implementation of the Action requires ents within the specif *ed time interval constitutes conpliance with a Specification and (2) completion of the remedial measures of the Action raquirements is not required when compliance with a Limiting Condition for Operation is restored within the time interval specified in the associated Action requirements. 3.0.3 Establishes the shutdown Action requirements that must he implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated Action requireannta. The purpose of this specif1 cation is to delineato the time limits for placing the unit in a safe shutdown mcde when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its Action requirements. It is not intended to be used as an operational convenience which persits (routine) voluntary removal of redundant systems or components fres service in lieu of other alternatives that would not result in -redundant systaus or componente being inoperable. One hour is allowed to prepare for an orderly shutdown before inittsting a change in plant operation. r This time permits the operator to coordinate the reduction in electrical generat!.on with the load dispatchsr to ensure the stability and availability r:f the electrical grid. The time limits specified to reach lower modes of operation permit the shutdown to proceed in a controlled and orderly i i L l Asendment No. J/,161 15c __.m._,

7,, -, a g? ,r -- a i. -BASES feentinu d 7*1. - eenner_ that-is wall within the specified maximun. :ooldown rate and sithin the

(.

cooldown espabilities of the facility assuming only the minimum required . equipment is OPERABLE. This reduus thermal stresses on components of the primary coolant system and tha potential for's plant. upset that could challenge safety systems under conditions for which this specification applies. If remedial stssures permitting limited cortinud operation of the facility under the provisions of the Action requirements are completed, the shutdown may.ba terminated.. The time limitr of 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 met or the time timits of the Action requireeents have not expired,' thus providing sn. allowance for the completson of the. required Actions. The time limits of-Specifiest.fon 3.0.3 allow 37 houro (or the plent to be in the' COLD SHUTD0VN condition when a shutdown is~ required during the POWER modo o! operation. If the plart is in a lower mode of operation when a shutdown is r44uired,' the time limit for reachirs ;he next lower mode of operation applies. However, if a lowee mode of operation is reached in less time than allowed, the total allowable time to each COLD SHUTDOWN, or other applicable rode, is not reduced.- For example, if HOT STANDBY is reached in 2 hours, the time allowed to rea:h HOT SHUTDGVN is the next 11 hours because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours.

Therefore,-if remedial measure *: are completed.that would permit a return to p0VER operation, a penalty is not incurred by having to reach a. lower mode of ope::ation in 'less than the total time allowed.

The same principle applies with regard te che allowable outage time limits of the Action requirements, if complie.nce with the Action requirements for one specification resulcs in entry into a mode or condition of operation for. another ipecification in which the requirements of the Limiting Condition for Operction are not met. If the new specification becomes applicable in less time than specified, ~ the difference may be added to the allowable outage time limit: of the socond specification. Ikwever, the allowable outaae time lialt8 of Action requirements for a highet mode of operation may not be used to extend the dlowable outage time that is egplicable when a Limiting Conlition for Operation is not set in a. lower mode of operation. The shutdown requirements of Specification 3.0.3 do not apply in COLD SHUTDOWN and REMELING SHUTDOWN, because the Action requirements of individual specifications define the remedial measures to be teken.

3.0.4 Establishes

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 requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in-a shutdown to comply with the Action requirements Af a change in modes were permitted. The purpose of this specification is to ensure that facility operation is not Amendment No. 161 15d ,m.

Y J y ] ]M D (conthuedl Q. 4* initiated or that higher modes of operation are not entered when corrective action is being taken to obtain compliance with a Specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with Action requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or af ter a modo charge. Therefore, in this case, if the requirements for continued operation have been met in accordance with the requireeents of the specificat ter, then entry into that mode of operation is permissible. The provisions of this specification should n: t, however, be interpreted as endorsing the failure to exercise good practice in restoria-systems or components to OPERABLE st,stus before plant startup. When a shutdown is required to comply with Action requirements the provisions of Specification 3.0.4 do not apply because th9y would delay ' cing the facility in T lower mode of cperstion. For the purpose of compliance with this specification the term ' shutdown' is defined as a required reduction in the REACTOR OPERATING CONDITION. 3.0.3 Delineates whac additieaal conditions must be satiarted to permit operation to continue when a normal or emergency power source is not OPERABLE. It specifically prohibits operatien when one division is inoperable because its normal or energoney pcwer source is $noperable and a spitem, subsystem, train, compoaent et device in another division is inoperable for another reasoG. 7ho provisions of this specification permit the Limiting Condition for Operation statementh associatei with individual systems, subsystems, traina, components or devices to be consistent with the Limiting Condition for Operation stateatuts of the associated electrical power source. It allows operation to be governed by the time limits of the Limiting Condition for Operation for the norssi or emergency power source, not the individual Limiting Coadition for Operation statements for eac*r systes, subsystem, train, componer.t or devica that is determined to be inoperable solely because of the inoperability of its normal or emergency power source. For example, Specification 3.7.2.C provides for a 2 day cut-of-service time when one emergency diesel generator in not OPERABLE. If the definition of OPERABLE were appli.d without consideeation of Specification 3.0.5., all systems, subsystems, trains, componet. 4 and devices supplied by the inoperable emergency power soutco would also bs inoperable. This would dictate invoking the applicable Action statements for wach of tbc applicable Limiting Conditions for 0,eretico. However, the provisicas of Specification 3.05 permit the tion limits for cootinued operation to Amendment No. 161 15e

g,, - - ~

p e.

+ .y s* 4,g ;,,,.*t; .t._- j-L' 3.1.2; Pressurization. Hgstuo. and Coold wn Limitations 2 Y ggeelfication 3.1.2.1 Hydro Tests lc For thermal steady state system hydro tests, the system may be l~ . pressurized to the limits set forth in Specification 2.2 when there L are fuel assemblies in the core under the provisions of 3.1.2.3, and to ASM Code limits when no fuel assemblies are present provided the reactor coolant system limits are to tha right of and below the limit line in Figure 3.1.2-1. The provisions of Sps.cification 3.0.3 are not applicable. 3.1.2.2 Leak Tests Leak tests required by Specification 4.3 shall be conducted under the provision of 3.1.2.3. The Fro 'isions of Specification 3.0.3 are not applicable. L 3.1.2.3_ The reactor coolant pressure and the systes heatup and cooldown rate, (with the exception of the pressurizer) shall be -limited in accordance with Figure 3.1.2-2 and Figure 3.1.2-3, and ..re as follows: Heatup: Allowable combinations of pressure and temperature shall be to the right of and below the limit line in Figure 3.1.2-2. The heatup p -rates shall not exceed those shown in Figure 3.1.2-2. -Cooldown: Allowable combinations of pressure and temperature for a specific cooldown shall be to the right of and-below the limit line in Figure 3.1.2-3. Cooldown rates shall not exceed =those shown in Figure 3 1.2-3. 3.1.2.4 . The secondary side of the steam generator shall not be - pressurized above 200 peig if the temperature of the steam generatet shall is below 100F, -3.1.2.5 The pressuriner'heatup and cooldown rates shall not - excesd 100F/hr.' The spray shall not be used if the. temperature -41fference between the pressurizer and the spray fluid is greaters than 430F. '3.1.2.6 With the limits of fpecifications 3,1.2.3 or 3.1.2.4 or- -3.1.2.5 enceeded, restore the t-esperature and/or pressure ' to within the limit within 30 minutes;; perfore an engineering evaluation _ to determine the effects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine that .the Reactor Coolant System remains acceptable for continued operations or be'in at least. HOT STANDBY within the nort'6 hours end reduce the RCS Tava and pressure to less than 200F and 300 psia, p respectively, within the following 30 hours. Amendeant No. 21,28, J7,161 18 e-e w+ ,e# < ee mesie=

• e eve

=, - ~ ~ e-i, -,,,em --a--- r-- e +r*

• • etw-e w d.

w et +w# ms-we es er-a e 'ew

• is w W e

-d WWW -wo-e" Tm f.

~ ~. - 3 3.- > w j qQ fiV l jy[*)<li _ -'i' L.. sw j.ff !C 3 1 2,7: Prior to reaching /fif teen ef fective full power yea:s of -operation --Figures 3.1.2-1, 3.1.2-2 and-3.1.2-3 shell be~ updated for-Oh _the next service period.in accordance with 10CTRf0, Appendix G, 7. Section V.B.: -_The service period shall be of'suf ficient duration to i permit the scheduled evaluation of a portion of the surveillance data scheduled in accordance with-Specification 4.2.7 The highest -w ' f_ predicted adjusted referenes temperature of all the Settline region ~ raterials shall be used-to determine the adjusted reference. .emperature at the end of-the service period. The basis for this prediction-shall be submitted for NRC staff review in accordance with Specification 3.1.2.8. The provisio ' of Specification 3.0.3 are not applicable. u 3.1.2.8 The updated proposed-technical specifications referred to --in,3.1.2. 7 'shall be submit ted for NRC review at least 90 days ~ prior to the end of the service period. Appropriate additional NRC review;tlee shall be allowed for proposed' technical specifications e submittod in acenrdance with 10 CTR Part 50, Appendix G. Section V.C. 3.1.2.9 Vith -the ' exception of ASME Section XI testing and when the core . flood tank is depressurized, during a plant cooldown the core flood - -tank discharge valves shall be closed and the circuit breakers for ~ the motor operators opened before depressurizing the reactor coolant-system below 600'psig. 3.1.2.10. With the ' exception of ASME Section XI testing, fill and vent of the - reacter coolant system, emergency RCS makeup and to allow maintenance of the' valves, when the reactor coolant temperature is less then 280'F, the High Pressure Injection motor operated valves shall be closed with-their opening control circuits for the motor operators disablad. -3.1.2.11 The plant:shall not-be operated in a water: solid condition when the RCS pressure _ boundary-is intactiexcept as allowed by Eeergency I Operating Procedures and during System Hydrotest. ,m s S 4 Amendment No.- J/, 3), f), JJ8, 18a ARKANSAS - UNIT 1 0 14), 161 +~,egp-- iWe +..wo-,4w. c asaw,w. e-o wf -a sgues-w --e.u mt re** e - we=4 e et-fa wr --2

• • • =uMik%=*

-4be 4

nn-3.1

,.c @ M1Q

~ 1 6gn 14g lable 3.3.1-1 (cont'd1' 7 X

23. With the number of operable Electronic. (SCR) Trip relays one ~less than the. total number of Electronic (SCR) Trip relays in'a clennel,Lrestore the' inoperable Electronic (SCR) Trip relay to operable status in

48. hours or place;the Sci 4 associated with the inoperable Electronic (SCR) Trip relay-in trip in.the next

-if hour.. With two or oo e Electronic (SCR) Trip' relays inoperable, place all Electronic (SCR) Trip ' relays associated with that enannel 'in trip In the next hour.1LThis requirement does not apply to the Electronic- ~ Trip channels associated with Group 8 Regulating Power Supply. l i 24. With the number of OPERABLE channels one less than the Total Number of Channels. STARTUP and/or POWER- -OPERATION may proceed provided the.followlsg conditions are satisfied,

a. 'Within l' hour:

'1. Place the inoperable channel in the tripped condition, or 2. Remove power supplied to. the control rod trip devien associated with the inoperable channel.. -b. One additional channel may be bypassed for up to 4 hours for surveillance testing and the operable channel above may be bypassed for up to 30 minutes in any 24-hour period when necessary-L to. test the trip breaker associated with the logic of the channel being tested. The inoperable ~! channel above shall not be bypassed to test the logic of a chernel of. the trip system 'essociated ~ witle the inoperable channel. 25. With one of the Control Rod Drive Trip Breaker diverse trip features (undervoltage or shunt trip attachment) inoperable,'reatore it to OPERABLE status in~48 hours or place the breaker in trip in the next hour. 26. Interrupts motor power to' the Safety Groups of. control rods only. 27. With one or more seismic monitoring instruments inoperable for more them 30 days, prepare end. submit a Specist Report to the Commission pursuant to Specification 6.12.2 within the nort 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status. The g provisions of Specification 3.0.3 are not applicable. l i l Amendment No. JU,J)J.161. 45g

p-N }hk s! - ^ '-.C i. -

r. +

^ * '~R -- 3.5.4 dngue instrumentation M Apolleability J Applies to the operability of the incore instrumentation system. L [ Ob leet iv.g : To specify the functional and operational requirements of the incore instrumentation system. Semelfication Above 80 percent of operating power det' ermined by the reactor' coolant-pump . combination (Table 2.3-1) at least_23 individual incore detectors shall be operable to check gross core power distribution and to assist in the periodic calibration of the out of-core detectors =in regard to the core imbalance trip lim it s ' The detectors shall be arranged as follows and may be a part of both basic arrangements. ~ ' 3. S. 4. Axial Imbalance-A.' Three detectors, one in each of three strings shall lie in the same axial plane with one plane in each axial core half. B.: The axial _ planes in each core. half shall be symmetrical about the. core mid-plane.- .- C. The detector shall not have radial symeetry. 3.5.4'.2-Radial Tilt 'A. Two' sets-of four-detectors shall lie in each core half. Each set of fov shall lis-.in the same axial plane.'fThe two sets -in the saw. ; ore half may lie in the.same axial plane. J B.

Detectors in the'same plane shall have quarter' core radial s ymme try. _-

With the incore detector system inoperable, do not use the system for the - above applicable monitoring function. -The provisions of Spscification 3.0.3 - l are not applicable. ] Basma ' A syston'of 32 incore flux detector assemblies with 7 detectors per assembly has been provided primarily-for fuel management purposes. The system 3 includes data display and record functions and.is also used for out-of-core q nuclear instrueentation calibration and for core power distribution - verification, q A.. The ont-of-core nuclear instrumentation calibration includes: 1.,

Calibration of the split detectors at initial reactor startup,

~during the power escalation program 'and periodically. 1: _ thereafter. Amendment No. J1,:161 51 - s.w 9 4 5 Vgy m 4 yp i.+, p = ggy..~ mg v

ue2,

.m,, e v- =,, w r,fy .w+w --e -ewa -~ < - ~ * - e = wm -v-

....... = J !Y t l'"i '3.5.5 Eltt_Ettu tion Instruar.nk di20 1 }$. * - Aeolic1 hill.ty $x This specification applies to fire detection instrumentation utilized within fire areas containing safety rett sd equipment or circuitry for the purposes of protecting that safety related equipment or circuitry. Oblectiv.3 To provide immediate notifle.ation of fires in areas where there exists a potential for a fire to disable safety related systees. S.itti.finitinn 3.5.5.1 A einimum of 50% of the heat / smoke detectors in tha locations specified in Table 3.5-5 shall be operable. 3.5.5.2 If less than 50% of the fire detectors in any of the locations designated in Table 3.5-5 are operable, within one hour esta= blish a fire wa ch patrol to inspect the zone (s) with the in-operable instrument (s) at least once per hour and restore the equipment to opstable status within 14 days, or prepare and submit a Special Report to the Commission pursuant to Specification 6.12.5 within the next 30 days outlining the action taken, the cause of the inoperability and the p ans and schedule for restoring the instrument (s) to operable status. The provisions of Specification l 3.0.3 are not applicable. EAA11 The various detectors provide alares that notify the operators of the existence of a fire in its early stages thus providing early initiatien of fire protection. The detectors in the main and auxili.ry control rooms also provide automatic fire protection initiation. ) The detectors required to be operable in the various areas represent one half of those installed. Operability of the fire detection instrumentation ensures that operable warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipeent. In the event tha a portion of the fire detection instrumentation is inoperable,,the satablisheent of frequent fire patrols in the affected areas (s) is required to provide detection capability until the inopetable instrumentation is restored to operability. 1 Amendment No. J#, 5), 57, lig, 161 55d l

py: - ' ~~ ^ .s' .M' r'[j s 3 c 3.5.6-Eisli2AAt.11e_Lieuid Ef flurAuntumm1Rica tf Arn11sthility: Durins releases via this pathway.

2 Chlsetivet 70 provide instrumentation for radioactive liquid releases.

Epeci.fisalinni 3.5.6.1 The radioactive liquid ef fluent monitoring instrumentation shown in Table 3.5.6-1 shall be operable with their alarm / trip setpoints set to ensure that the limits of specification 3.25.1.1 are not exceeded. 3.3.6.2 With alarm / trip setpoints less conserystive than required by the above specification, lemediately suspend the release of radioactive liquid effluents monitored by the affected channel, until the setpoint is changed to an acceptably conservative value. 3.5.6.3 With less than the minimum number of channels operable, take the action shown in Table 3.5.6-1. Return the instruments to operabis status within 30 days or, in lieu of any other report, explain in the next Sealannual Radioactive Effluent Release Report why the inoperability was not corrected. 3.5.6.4 The provisions of Specification 3.0.3 are not applicable. l Bases: The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid affluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the lielta of 10 CFR Part 20. Amendaent No. JJ, 118, 161 53f

) 3 s - + -en-.- l d - I \\7 i:. r" n 1A -

• }

l.' tv. lff 3.$.7. Radjgjetive Gasecun_ Effluent.Instrumentglign V - I = Agn11 cab 111tri As shown in Table 3.5.7-1. i D, Obiecti al To provide instrumentation for radioactive gaseous releases. t i Egecificationi i 4 3.5.7.1 The radioactive gaseous affluent monit(ring instrumentation shown in Table 3.3.7 1 shall be operable with thstr alarm / trip setpoints set to ensure that the limite of Specification 3.23.2.1 are not exceeded. SR t 3.$.7.2 With a channel alare/ trip setpoint less conservative than required, declare the channel inoperable. 3.3.7.3 With less than the minisua number of channels operable. take the action shown in Table 3.5.7+1. Return the instruments to operable status within 30 days or, in lieu of any other report, explain in the next Semlannual Radioacttve Effluent t Release Report why the inoperability was not corrected. 3.5.7.4 The provisions of Specification 3.0.3 are not _ applicable. l s Iaaasi The rcdioactive gaseous effluent instrumentation-is provided to monitor and i control, as applicable, the releases of radioactive matorists in gaseous effluents'during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with rathods in the ODCM to ensure that the alors/ trip will occur prior to exceeding the limits of to CFR Part 20.105. i P i P i I 4 b ~ l' t b i t Amendment No. 55,Lljf, 161 531 y l 9 g.4, 4 <= m eetMe6 9 e e r-M@ en '-aYd' se-e e ee.. -e---,. -,-+%,,,,--.-w+.m.rree-.m.--en--vere.wyem'e-r w e-vwnw s-y-*- 6e -,W-mu-f-wm,,~ ee : w -,,we r-4cy*ry-,egre-a.<,-- r w, wy e g ww e-rs = =g-gr e v t ,9 w, +- w-y

f a t a} 3.7.2 A. The specifications in 3.7.1 may be stodified to allow one of 5 the following canditions to exist after the reactor has been j ( heated above 200F. Escept as indicated in the following ~ l conditions, if any of these conditions are not met, a hot shutdown shall be initiated within 12 hours. If the condition is not cleared within 24 hours. the reactor shall be brought to cold shutdown within an additional 24 heurs, i-8. In the event that one of the offsite power sources specified in 3.7.1.A (1 or-2) is inoperable, ;eactor operation may continue for up to 24 hours if the availability of the-diesel generators is immediately verified. C. Elther one of the, two diesel generators may be inoperable for up to 7 days in any month provided that during such 7 days the operability of the remaining diesel generator is demonstrated.' lusediately and daily thereafter, there era no inoperable EST components associated with the operable diesel generatoe, and provided that the two sourcne ol' off site p>wer speciff eri in 3.7.1. A(1) or 3.7,1. A(2) are available. D. Any 4160V, 480V, or 120V switchgear, load center, motor control center, or distribution panoi in one of the two EST distribution systems may be inoperable for up to 8 hours, provided that the operability of the diesel generator associated with the operable ESF distribution system in demonstrated immediately and all of the components of the operable distribution systee are operable. If the ESF distribution system is not returned to service at the end of the 8 hour period, Specification 3.7.2.A shall apply. E. Two station battery chargers may be inoperable for 8 hours, after which Specification 3.7,2.A shall apply. F. One of the two station batteries and the associated distribution system may be inoperable for 8 hours provided that there'ere no inoperable safety related components associated with the remaining station battery which are redundant to the inoperable station battery and the operability of the diesel generator is verified immediately. If the battery is not returned to service at the end of the 8 hour period, Specification 3.7.2.A shall sppl/. i 0.- Two control power sources from the plant to the switchyard and the attendant distribution systen any be inoperable for 8 hours, after which Specification 3.7.2.A shall apply. II. - If the requirements of Specification 3.7.1.0 cannot be met, either: (1) lace all Startup Transformer No. 2 feeder breakers in p' pull-to-lock" within 1 hour, restore the inoperable interlocks to operable status within 30 days, or submit within 30 days a Special Report pursuant to Specification 6.12.5 outlining the cause of the failure, proposed corrective Action and schedule for implementations or (2) spply.the action requirements of Table 3.5.1-1, Note 14 Amendeont No. $f, JJp, 161 57 L w w.-si. v y -y-,- w, y-yv-m- y- ,-,---o--,

?y, t L *. j l g 3.8.6 During the handling of irradiated fuel in the reactor building, at least one door on the personnel and emergency hatches shall be 4 closed. The equipment hatch cover shall be in place with a minimum -7 of four bolts securing the cover to the soaling eurfaces. 3.8.7 1soldtion valves in lines containing automatic e.ontair.sent isolation valves shall.be operable, or at least one shall be + l closed. 3.8.8 When two irradiated fuel assemblies are being moved simultaneously by the bridges within the fuel transfer cans!, a minimum of to feet separation shall be saintained between the assemblies at all times. 3.8.9 ff any of the above specified limiting conditiens for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease Action shall be initiated to correct the conditions so that the specified limits are set, and no operations which eay increase the seactivity of the core shall be made. The provisions of Specification 3.0.3 are not applicable. l 3.8.10 The reactor building purge isolation systee, including the radiation monitorn shall be tested and verified to be operable within 7 days prior to refueling operations. The provisions of Specification 3.0.3 are not applicable. l 3.8.11 Irradiated fuel stia11 not be reeoved from the reactor until the unit has been suberitical for at least 72 hours. In the event of a complete core offload, a full core to be discharged shall be suberitical a minimum of 175 hours prior to discharge of more than 70 assemblies to the spent fuel pool. The provisions of fpecification 3.0.3 are not applicable. ] 3.8.12 All fuel handling in thei Auxiliary Building shall cease upon notification of the issuance of a tornado watch for Pope, Yo!!, Johnson, or (, ogen counties in Arkansts. Fuel handling operations in' progress will be completed to the extent necessety to place the fuel handling bridge and crane in their norant parked and locked position. The provisions of Sps:1fication 3.0.3 are not i applicable. 3.8.13 No loadwi spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmospheric dispersion conditions are equal to or better than those produced by Pesquill Type D_atability accompanied by a wind velocity of 2 s/sec. In addition, the retiroad spur door of the Turbine Building shall be. closed and the fuel handling area ventilation system shall L ~ be in operation. The-provisions of Specification 3.0.3 are not l L applicable. 3.8.14. I,oads in excese of 2000 pounds shall be prohibited from travel over Lfuel assemblies.in the storage pool. The provisions of Specification 3.0.3 are not applicable. l Amendment No. If,11 M,51,Ne 161 59

3 I i .Y. yl y 3.8.15* The spent fuel shipping cask shall not be carried by the Auxiliary 3 Building crane pending the evaluation of the spent fuel cask drop j accident and the crann design by AP&l,and NRC review and approval. The + provisions of Specificatio, 3.0.3 are not applicable. l 3.8.16 Storage in the spent fuel pool shatt be restricted to fuel assemblies j having initial enrict.eent less than or equal to 4.1 w/o U-235. The provisions of Specification 3.0.3 are not applicable. l 3.8.17 Storage in Region 2 (as shown on Figure 3.6.1) of the spent fuel pool { shall be further reJtricted by burnup and enrichstent limits specified in FJgure 3 6.2. lu the event a checkerboard storage configuration is deemed necessary for a portion of Region 2. vet.ent Spaces adjacent to the faces of any fuel assembly which does not meet the Region 2 burnup criteria (non-restrit.ted) shall be physically blocked before any such I fuel assembly may be placed in Region 2. nis will prevent inadvertent fuel assembly insertion into two adjacent storage locations. The provisions of Specification 3.0.3 are not applic.sble. l 3.8.16 The boron concentration in the spent fuel pool sht11 be maintained (at ? all times) at greater than 1600 parts per million. latta Detailed written procedures will be available for use by refueling personnel. These procedures, the above specifications, and the design of the fuel handling equipment as described in Section 9.6 of the FSAR incorporatirig built-in f interlocks and safety features, provide assurance t. hat no incident could occur during the refueling operations that would result in a hazard to public health and safety. 11 no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation. Continuovt monitoring of radiation levels and neutron flux provides immediate indicacion of an unsafe condition. S e requirement that at least one decay heat removal loop be in operation ensqres that (1) nuffielent cooling capacity is availabla to remove decay heat and maintain the water in the reactor pressure vessel at the refJeling tesperature (normally 140'F), and.(2) sufficient coolant circulation is maintainedthroughthereactorcoretosingsetheeffectsofaborondilution incident and prevent boron stn tifit.ation. The requirement to have two decay beat renoval loops operable when there is less than 23 feet of water above the core, ensures that a singla failure of the operating decay heat renovel locp will not result in a complete loss of decay heat renoval capability. With the reactor vossel head removed and 23 feat of water above the core, a large heat sink is available for core cooling, thus in the_ event of a failure of the operating decay heat removat loop, rdequate time is providwd to initiate t.sergency procedures to cool the core. The shutdown margin indicated in Specification 3.8.4 will heep tgcore suberitical, even with all control rode withdrawn from the core. Although. (' the refueling boron concentration is sufficient to maintain the core k [$ds will 5 0.99 it all the control rods were removed from the core, only a few contro1* be removed at any one time during fuel shufflin.g and [ t - Note:

• A one time exception to 3.4.15 is granted for the period of July 13, 1987 through August 12, 1987.

Amendment No. //,JJ,J/,7#,Jf/,161 39a -.,m ~

I r L.1 'l ' (5 3.12 MISCELLANEOUS RADIDACTIVE NATERIALS SOURCES ,itglicability Ap).tles to byproduct, source, and special nuclear radicar.tive material soursos. 0 blur 1Lu To assure that leakage from byproduct, source and special nuclear redlooctive meterial sources does not exceed allowable limits. _Specificat12D t 3.12.1 Tt's source lentage test perforced pursuant to Specification 4.14 shall be espable of detecting the presence of 0.00$ 901 of radioactive material on the test saeple. If the test reveals the presence of 0.00$ 901 or more of removable contamination, it shall immediately be withdrawn from use, decontaminated and repcited, or be disposed of in accordance with Commission regulations.. Sealed sources are exempt from such leak tests when the source contains 100 pC1 or less of beta and/or garm'4 voittirig material or $ pCi or less of alpha emitting material. The provisions of Specification 3.0.3 are not appitcable. l 3.12.2 A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.12.$ within 90 days if source leakage tests reveal the presence of 20.005 microcuries of removable contaniination. 3.12.3 A complete inventory of licer. sed thdioactive asterials in possession sha!! be maintained current at all times. I: l 1 Amendment No. J) JJ,J7 JJ8,161 66b l i 1

3 ,1 j.,* 3.1$ FUEt, HANDl. LNG AREA '.'ENill.ATION SYSTEM ~i i. Arnlicahilitx Applies to the operability of the fuel handling area ventilation system. f&ilc112A To ensure that the fuel handling area ventilation sy+ tem will perfore within acceptable levels of efficiency and reliability. EEicil1 GAL 1211 3.1$.1 The fuel h ndling area ventilation system shall be in operation whenever irradiated fuel handling operations are in progrenn in the fuel handling arts of the aun liary butiding and shall have the follcwing performsnee capabilities a. The results of the in-place cold DOP and halogensted hydrocarbon tests at design flows (110%) on HEPA filters and r.harcoal adsorber banks shall show 2 99% DOP removal and a 99% hategenated hydrocarbon romoval. b. The results of laboratory carbon sample analysis shall show 2 90% radioactive methyl iodide removal at a velocity within 1207, of system '.asign, 0.05 to 0.15 og/m' inlet methyl lodido concentration. 2 70% R.t!. and 2 125F. c. Fans shall be shown to operate within 110% design flow. d. The pressure drop across the combined HEPA filters and charceal adsorber banks shall be less than 6 inches of water at system design flow rate (110%). 1 s. Air distribution shall be uniform within 120% across HEPA filters and charcoal adsorbers when tested initially and af ter any malatenance or testing that could af fect the air distribution within the fuel handling area vsntilation system. 3.15.2 If the requi enents of Specification 3.15.1 cannot be met. Irradiated fuel novement shall not be started (any irradiated fuel asnembly movement in progress may be cco,pleted). The provisions of Specification 3.0.3 are not applicable. l Itama The fuel handling area ventilation system is designed to filter the auxiliary building atsosphere during fuel handling operations to limit the release of activity should a fuel handling seddent occur. The system consists of one circuit containing two exhaust fans and a filter train. Th1 isna are redundant and only one la required to be operating. The filter trein consists of a profilter, a HIPA filter and a charcoal adsorber in series. Amendment No. 19,18.31.161 66g g i l

-...~ ~ ~. - s FY. ..y) lf.' 3.18 p!RE SUPPRES$10N STRINKLER SYSTEM 14 Aeolicabilftv I 'f protecting safety related areas:This specification applies to the followi a i Each of the four reactor building cable penetration areas, a. b. Each of the four cable penetration tooes. c. Each of the two emeriency diesel g(.sarator rooms. 4 d.- Cabis spreading room. Each of the two diesel genarstor fuel vaults. e. f. Hallway El 372 (Zone 98-J). 3 Condensate desinerallror area.* t Ob tectlym To assure that fire suppa salon is available to safety related equipment located in th9 above listed a:ess. SAa.cifinatica t 3.18.1 The above-listed sprinkler systess shall be operable at all times. 3.16.2 With one or more of the above listed sprinkler systees inoperable establish a continuous fire watch (or operable smoke and/or heat detection equipment with control room alarn) with backup fire Rear.oro the system (s) to operablasuppression equipment for th status withAn 14 days, or prepare and submit a Special Report to the Commission pursuant to Specif1 ration 6.12.3 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the systan(s) to operable status. The provisions of Specification 3.0.3 are not applicable. { Easan Safety related equipment located in various areas is protected by sprinkler systems.. The operability of these systems ensures that adequate fire suppresefon capability la available to'tonfino and extinguish a fire occurring in the applicable areas. In the event a system is inoperable, alternate be made availabla until the inoperable equipment is ' re 4

• To be leptemented no later than Joly 30, 1979.

Amendment No. Jp,$J.J7,JJg, 161 66d fr . _ _.. _...., _. _ -. ~, _ _ _.

_ _ _ _-.. -- ~.-. -l 4, J.g, 3.19 CONTROL ROOH AND AUXILIARY CONTROL ROOM HALON SYSTEMS 4 :. ' Acolleability 'Y This specific.ation applies to the Halon systems utilized as the fire suppression system for the contrcl room and auxiliary control room. Obiectlys To assure that firm suppression is available to the safety related equipment in the control room and auxiliary control room. Epic),fication 3.19.1 The three control room and aux 11(ary control room Helen systent . shall be operable at all times with the storage tanks having at 1 east 95% of full chcrge weight and 90% of full charge pressure. 3.19.2 With any of_ the control room and auxiliary control room Halon systems inoperable, establish backup fire suppression equipment for the effected area within one hour, Restore the system (s) to operable status within la days, or prepare and submit a special Report to the Commission pursuant to Specification 6.12.$ within 30 days outlining the actions taken,-the cause of_the inoperability, and the plans and schedule for restoring the system to operable status. The provisions of Specification 3.0.3 are not . spplicable.- _J - h114 Safety related circuitry located in portions of the control room and aux 111ery control room is protected by the Halon systems. The operability of these systems ensures that adequate fire suppression capability is available to confino and extinguish a fire occurring la the control room or the auxiliary control room. In.:;he event that the systee(s) is inoperable, alternate backup fire fighting equipment is required to be made available in-the affected area until the inoperable equipment is restored to service. p 1 l Amendeent 'No. H U, US 161 66o t a v r ,w m-- ,-.p,g -y-.,c.,,--'troe f-.,,.,,w.-,[,.wE-, y.e w, .-r,4 m. ,r-s'-.. -w

W'. i yy + v ,Q.b.' .c. 7' 3.20 FIRE HOSE STATIONS Y. ' Aeolicability ~ This specification applies to (ire hose stations protecting areas containing safety related equipment. DhitC.tiu To assure that manual fire suppression capability is available to all saf ety related equipment. ,$nggification 3.20.1. All fire hose stations protecting areas containing safety related - equipment shall be operable whenever the equipment in thess areas is required to be operable. 3.20.2-With one or more of the fire hose stations of 3.20.1 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an operable hose station within one hour. The provisions of Specification 3.0.3 are not applicable. j' Bases i The operability of the fire hose statigas adds additions 1-assurance that ' adequate fire suppression er.pability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. In the event that portions of this systne are inoperable, backup fire hose equipment is required to be,eado available in the affected ares (s) until the inoperable equipsont. As restored to service.. r If s. le ~ L_ Amendment No. Jp,)/,.161 66p [ 7 m-

._ _.. _s s..,,...,,

.y .,,,g,, .v..,._.....,

DI \\ 4- ' 7 3 g - + 3.21 FIRE BARRIERS ] Aeolicabilite 4 This specifiestion applies to fire carriers separating safety related fire areas or redundant safe shutdown systems required in the event of a fire. s-Ob t ectln i To assure that fire barriers esparating safety related fire areas or redundant safe shutdown systees perfore their separation function. SRELiLLC&tlR3 3.21.1 All fire barriers separating safety related fire areas or redundant safe shutdown systems shall be operable at all tiees. 3.21.2 Vith one or oore of tha required fire barriers inoperable, within 1 hour, either: a. Establish a continuous fire watch on at least one side of the affected fire barrier or, b. Verify the operability of smoke and/or heat detection equipeent with control room alate on at least one side of the affected barrier and establish an hourly fire watch patrol. 3.21.3 The provisions of Specification 3.0.3 are not applicable. l ' 2ASAg The operability of the fire barriers, including fire-rated walls floors / ceilings; fire doors; fire despers and penetration seals, ensures that fires will be confined or adequately retarded free spreading to adjacent fire areas or to portions of redundant safe shuwn systems required in the event of a fire within the fire area. This valgn feature einleizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The-fire barriors are a passive element in the facility fire protection progree and are subject to periodic inspections. Safety related fire areas are the Control Room, the Switchgear Rooms, the Battery Rooms, and the Diesel Generator Roose.. fire barriers also separate lubricating oil storage areas from other areas of the plant. Fire barriers separating redundant safe shutdown systems have been defined by analysis. During periods of time when the barriers are inoperable, a continuous fire - watch or operable detection equipment with. an hourly fire watch patrol 'is required to be maintained in the vicinity of the affected barrier until the barrier is restored to operable status. j__ Amendment No._ Jp,J7,127,161 66q m~ = p-

• .ed.'

e = -"he ut>-61ms eggsese 4 1 1 f 1 w w t

==c-- s-+w-** u----++ = w------w -r-e---e e+- ^e3 v

4 E. -p t i4, ) 4 't Y 1. 31 3.22 ' REACTOR BUILDING FURGE FILTRATION SYSTEM 2* i' Aaplitability .y' This specification applies to the operability of the reactor building purge filtration systes. . Objective To assure that the reactor butiding purge flitration system will perform within acceptable levels of efficitri:y and reliability. Specification 3.22.1 The rasetor building purge filtretion system shall be operable whene"er irradiated fuel handling operations are in progress in the reactor butiding and shall have the following performance capabilitles:

a.. The results of the in place cold DOP and halogenated hydrocarbon tests at design flows (110%) on HEPA filters and charcoal adsorber banks shall show 299% DOP removal and 299%

halogensted hydrocarbon removal. b. The results of laboratory carbon sample analysis shall show 290% radioactive methyl iodide removal at a velocity within 120% of system design, 0?5 to 0.15 mg/=8 inlet methyl iodide concentration, 270% R. H. and 1125F. c. Tans shall be shown to operate within 110% design flow. d. The pressure drop scross the combined HEPA filters and r charcoal adsorber banks shall be less than 6-inches of water ,at systen design flow rate (110%).

e.. Air distribution shall be uniform within 120% across HEPA tilters and charcoal adsorbers when tested = initially and after any asintenance or' testing that could affect the air distribution within the reactor building purge flitration systes.

3.22.2 If the requirements of Specification 3.22.1 cannot be met, either: a. Irradiated furl movement shall not be started (any irradiated fuel assembly sovesent in progress say be completed); or, b. Isolate the reactor building purse system. 3.22.3 The provlsions of Specification 3.0.3 are not_ applicable. l 3AAAA The reactor building purge flitration system is designed to filter the reactor building atmosphere during normal operations for ease of personnel entry into the reactor building.' This specification la intended to require the system operable during fuel handling operations, if the system Amendment No. JJ,J1,'161 66r . + - - -_.-.i_ ._e.+ e 4 # **M e e e . m en op wesq sep .'..em 4% <,yv.. y =y p, .-e. y .-g,. _r,,y -~ ,y-4.

y;,- m d g 5 3.24 EXPLOS1VE GAS HIXTURE ? Applicshility ~ Applies to the Wasta Gas System hydrogen / oxygen analyzers. Qh.lective To prevent accumulation of explosive mixture in the waste gas system. SDEiLLCALinD 3.24.1 The concentration of hydrogen / oxygen shall be limited in the waste gas decay tanks to Region "A" of Figure 3.24 1. 3.24.2 Vhen the hydrogen / oxygen concentration in any of thu decay tanks enters Region B" of Figure 3.24-1, corrective action shall be taken to return the concentration values to Region "A" within 24 hours. 3.24.3 The provisions of Specification 3.0.3 are not applicable. { laita These hydrogen / oxygen limits provide reasonable assurance that no hydrogen / oxygen explosion could occur to allow rupture of the waste gas decay tanks. The hydrogen end oxygen limits are based on information in NUREG/CR-2726 "I.ight Water Reactor Hydrogen Manual". Amendeant No. $$,7), 161 66u -...... ~

j % ~: g, 09 g l}I ' - 3.25 RADI0 ACTIVE EFFLUENTS }- 3.25.1 Ridloaetive L1q4LEfiluents 3.25.1.1 Concentration &pJtlicAhili111 At a11 tiaes Qhlttlitti To ensure that the limits of 10 CTR 2* sta met. SPtA111AA1.11m21 3 25.1.1 A. The concentration of radioactive seterial released to the discharge canal shall be limited to the concentration specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2 x 10 ' pCi/e1. D. With the concentration of radioactive material released sxceeding the above limits, lenediately initiate action to restore concentration to within limits and provide notification s_ t Commission within 24 hours. In lieu of any other report, prepare and submit a Special Report within 30 days pursuant to Specification 6.12.5 C. The provisions of Specification 3.0.3 are not applicable. Atlan This specification is provided to ensure that the concentration of radioactive materials released in 11guld wasta effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Port 20. Appendix B, Table II. This limitation provides additional assurance that the levels of radfoactive materials in bodies of water outside the site will not result in exposures greater than the Section II A design objectivos of Appendix I,10 CTR Part 50, to c. member of the public. The concentration limit for noble gases is based upon the assumption that Xe-133 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. Asendment No. $8,JJ8, 161 J6v 4 i I

..y*; i 7 g 40 [ Radioactive Liquid Effluents "1. 3.25.1.2 Dose of. Agglicability: At all times Obiective: To ensure that the dose limits of 10 CFR 50, Appendix 1, Section IV A, are met. Seecifl ations l i 3.25.1.2 A The dose commitment to a member of the public from radioactive material in liquid effluents released from ANO-1 to the discharge canal shall be 1) During any calendar quarter less than or equal to 1.5 mann to the total body and less than or equal to 5 + stem to any orsen, and-2) During any calender year less than or equal to 3 aren to the total body and less than or equal to 10 arew to any organ. - 8. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in *ieu of any other report, prepare and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.$. C. The provisions of Specification 3.0.3 are not applicable. l ERRAE Specification 3.25.1.2 provides assurance that releases of liquid effluents will result in concantrations far below the limits of 10CTR20. The specification provides the required operating flexibility and at the same time assures that the release of radioactive material in liquid effluents will be'kept "as low as reasonably achievable". Amendeont No. #5,JJ8, 161 66w 4 9 -**"4B 6% 9 j W#$ 4%

1. e. a oe e-s-r e m'w-mm m

3 -l 9 Radioactive Uquid Ef fluents 3.25.1.3 Vaste Treatment Aralinhilltv: At a11 tises Oktrat.ly.nl To assure that the amount of radioactive material in liquid effluents will be "as low as reasonably achievable." 32tiliitAtich 3.25.1.3 A. The apptcpriate parts of the liquid radweste treatment systen shall be used to reduce the radioactive materiels in 11guld waste prior to their discharge when it is projected that tne cumulative dose during a calendar quarter due to liquid effluent releases would exceed 0.15 mres to the total body or 0.625 ares to any orgen. B. The provisions of this specification do not apply to the laundry tanks due to their incompatibility with the radwaste system. C. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report, prepare and submit a Specia* Report to the Commission within 30 days per Spncification 6.12.5. D. The provisions of Specification 3.0.3 are not applicable. PJuttii The requirements that the appropriate portions of this systes be used whea specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section !! A of Appendix I,10 CTR Part 50, for liquid e f fluer.t s. The values of 0.18 eren and 0.625 arem are approxicately 257, of the yearly design objectives on a quarterly basis. The yearly design objectives are given in 10 CFR 50, Appendix I, Section II. Amendment No. $3,JJ$e 161 66x

./ i Y. l j -= i 3* Radioactive Liquid Effluents t y 3.25.1.4 Liquid Holdup Tanks ]' AeolicatiM12t At all times. Objectivat To ensure that the limits of 10 CFR 20 are not exceeded. 3Atallinticast c 3.25.1.4 A. The quantity of radioactive caterial contained in each l unprotected

• outside temporary radioactive liquid storage l

tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. B. WJth the quantity of radioactive material exceeding the - above limit, immediately suspend all additions of radioactive material to the affected tank and within 48 hours reduce the tank contents to within the limit. C. . The provisions of Specification 3.0.3 are not applicable. [ lassai This specification is provided to ensure that in the event of an j uncontrolled rolesse of the contents of the tank

• the resulting cencentrations would be less than the lioits of 10 CFR Part 20. Appendia B. Table II, Coluan 2, at the nearest potable water supply and-the nearest surface water supply in the unrestricted area.
• Tanks included in this specification are those outdoor temporary ta k ns that 1) are not surrounded by liners,'dities, or walls capable of holding the tank contents,'and 2)' do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

s-i j 1 { Amendment No. ##, 161 66y a s . # sgw - a , wwe> wp eq e 4er er -m.g .r---, ,--c .,s,,,*v t r Ce - v W-r v-r-' =< -'Yv*e* "t's-t*'ee v e,~~ q m 1e t m te m-t-%--m+-*wh*r-=

• be=-=

+ - - - -

• =*-==-=a****'

-* * * * * - * * = -

a.i 3.25.2 EAdinattire_Esseous EfiltrnLa 1 3.25.2.1 Dose Rate Y Aeolicabilit u At all times Qbjectival To ensure that the dose rate in unrestricted areas from gaseous affluents will be within the limits of to CFR 20. Ear &ifintlicnal 3.25.2.1 A. The dose rate in unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall bei 1) For noble gases: Less than or equal to 500 arem/yr to the total body and less than or equal to 3000 mrem /yr to the skin. i 2) For iodine-131, for tritium and for all radionuclides in particulate form with half lives greater than a days: Less than or equal to 1500 aren/yr to any otgan. During perjods of reactor building purging the dose rate may be averaged over a one hour interval. B. With the dose rate (s) exceeding the above Ifmits, without delay restore the release rate to within the above limit (s) C. The provisions of Specification 3.0.3 are not applicable. l Intu This specification is provided to ensure that, at any time, the dose rate due to gaseous effluents free all units on the site will be within the limits of 10 CFR 20 for unrestricted areas. This specification applies to the release of gaseous ef fluents free all reactors at the alte. 'Anendment No. 58,JJA, 161 66: e v--. -u- ,e e

'J-Y .3 3 1.j J Radioactive Gaseous Effluents I, 3.25.2.2 Dose - Noble Gases Ata11cAh111tn At all times l Ohlan11yJti To ensure that the design objectivt dons of 10 CTR 50, Appendix I, Sect ion IV A are riot exceeded. 5AttiLira11Dn11 3.25.2.2. A. The dose due to noble gases released in gaseous ef fluerits from ANO 1 to unrestricted areas (see figure 5.1-1) shall bei 1) During any calendar quarter, less than or equel to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and 2) During any calendar year, less than or equal to 10 mrads for gamma redistion ano less than or equal to N stads for beta radiation. B. With the calculated dose from radioactive noble gases in gaceous effluents exceeding any of the above limits, in lieu of any other report, prepara and subeit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5. C. The provisions of Specification 3.0.3 are not applicable. l EAltt: Specification 3.25.2.2 implements the design guides specified in 10 CTR 50, Appendix I, Section !!, and the limiting conditJon for operation as set forth in Section IV A of Appendix 1. The specifications provide the required operating flexibility and at the same time implement the guides set fccth in Section IV A, appendix 1 to assure that the releases of radioactive materie.1 in asseous of fluents will be kept "as low as is reasonably achievable." These limita provide reasonable assurance that radioactivs material discharged in gaseous offluents will ant result in the exposure of an individual in an unrestricted area, to annual average concentrations exceeding the limits specified in Appendix 8, Table 1.1 of 10 CTR Part 20 [10 CTR Part 20.106(b)]. For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to coupensate for any increase in the atmospheric dif fusion factor above that for the excluelon area boundary. Amendment No $8,1J),161 63sa \\ l

qqds ] s I-lA ' * + 3r;.. Radioactive Gaseous Effluents ~ 3.25.2.3 Dose - Iodine-131 Tritium, and Radionuclides in Particulate Form df Ag21.icih111tY1 At all times ableetival To ensure that the dose limits of 10 CFR 50, Appendix !, Section IV A, are met. Inialticarlsesi 3 25.2.3 A. The dose to a sember of the public from lodine-131, f.*on tritium, and'from all radionuclides in particulate form with halfalives greater than 8 days in assaous effluents - released from ANO 1 to unrestricted aresa (see pigure 3.t.1) shall bn: 1) During any calendar quarter, less than or equal to 7.3 mress to sn? organ, and 2) During any calendar year, less than or equal to il e arens to any organ. B. With the calculated dose from the release of iodine 131, tricium.and radionucitdes in parti.culate fore with half lives greater than 8 days, in gaseous effluents exceerling anf of the above limits, in lieu of any other rsport, prepare and submit a $pecist Report to the Comeission within 30 days, pursuant to Specitication 6.12.3.. C. The provisions of Specification 3.0.3 are not applicable. l RAasa ' Specification 3.05.2.3 foplements the design guideo set forth in 10 CTR 50, Appendit I, Section 11 C, and the limiting condittos.a for operation as L set forth in Appendix 'I Section IV A. The specifications provide the required operating flexibility and at the snee time implement.the guides set forth in Section IV A of Appendix I to i assure that the releases of radioactive notorials in gaseous effluents l will be kept "se low as reasonably achievable". I l f l Anesdaent No.-$$,JJ), 161 66bb 4 . : se - g -4.. .e .e, 4 .g .4 - 4 3 'e e eseqi> qanse e Deer es e ~, .,w,, .-p-a v.n- +-,-n. y e ,w..-g-, +-,.n. a w-r-.-, . i- .,-s - m e w, w -. m e

y;x I. t .j$' ' 4 j Radioactive Gaseous Effluents a 3.25.2.4 Gaseous Radwnste Treatment y An1htbilityt At all times Qhiggli m To assure that the amount of radioactive material in gaseous effluents is "as low as reasonably achiosable." 4 I Sutthsthnu 3.23.2.4 A. Ventilation exhaust treatment systems shall b4 used to reduce radioactive materfats in gaseous waste prior to i discharge when the projected doses due to ghieous effluent releases from ANO-1 to unrestricted areas (see Figure i 5.1 1) would exceed 0.625 erad for gamma radiation and 1.25 mrad for heta radiation over a calender quarter; or when the projected doses due to lodine-131, tritius, and radionuelfdes in particulate form with half-lives greater than 8 asys would exceed 1.0 mrem to any organ over a calendar quarter. B. When degasifying the reactor coolant system, the gaseous r,$dweste treateent systam shall be utilized to process the dogassing effluent to reduce the concent ation of radioactive materials psior to d!scharge when the projected doses due to gaseous effluent releases f rom MO 1 to unrestricted areas (see Figure 5.1-1) would exceed 0.625 mrad for gamma radiation and 1. 25 mrad for beta radiation over a calendar quarter. C. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report, prepara and submit to the Commission within 30 days a Special Report, per Specification 6.12.5. D. The provisions of Specification 3.0.3 are not applicable. l 141t31 The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseou.s effluents will be kept "as low as reasonably achievable." The specified limits governing the use of appropriate portions of the systete were specified as a suitable fraction of the guide set forth it. Sections II B and II C of Appendix I,10 CFR Part 50, for gaseous effluents. The valuea 0.625 mrad, 1.25 arad,isnd 1.0 mrem are apprnrisately 257. of the yearly design objectives on a quarterly basis. The yearly design objectives are given in Specifications 3.25.2.2 and 3.25.2.3. l Amendment No. ##,HW, 161 66ec

l-*, Mj =.. q, Radioactive Gaseous Effluents 3.25 2.5 Gas Storage Tanks y Aen11enh111tn At all times O_b i e t t iv e : To restrict the aeount of activity in a radinactive gas + holdup tank. 3;Jtsificat!cD11 3.25.2.5 A. The quantity of radioactivity contained in each gas storage tank shall be limited to 300.000 curies noble gases (Xe-133 equivalent). B. With the quantity of radioactive wateriel in any gas storage tank exceeding the above limit, immediately suspend all additions of radiocettve seterts! to the tank and within 46 hours reduce the tank contents, to within the 11.ait. C. The provisions of Epecification 3.0.3 are,not applicable. 111211 The value of 300,000 curies is a suitable fraction of the quantity of radioactive estorial which if teleased over a 2 hour period, would result in a total body exposure to a member of the public at the exclusion area boundary of 500 aren. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981. Amendsear No. $$,161 66dd 1 ' ^ ^ ' - ' - - -

, g.- '? 1 t 3.25.3 Igial. Dong h alisabM 1121. At all timas m Oh1A111YA1 To ensure that the limits of 40 CFR 190 are not exceeded. ksallinitionti 3.25.3.1 1he calculated doses free the release of radioactive esterials in liquid or geneous effluents shall not exceed twice the limits of Specification 3.23.1.2, 3.25.2.2, or 3.2$.2.3. 3.23.2,2 Vith the calculated doses exceeding the above limits, prepare and submit a Special Report pursuant to 10CTR Part 20.40$C. 3.25.3.3 If the limits of 40CTR190 have been arcoeded, obtain a var.(ance frem the Consiscion to permit further releases in excess of 40CFR190 limits. A v'erlance in granted until staff action on the request is completed. 3.25.3.4 The provisions of Specification 3.0.3 are not oppl' cable. l 111111 This specification is provided to meet the dose limitations of 40 CTR '90 thui have now been incorporated into 10 CTR P6.t 20. Ths specification requires the preparation and sebsittal of a Special Report uheneves the - calculated doses from pinnt radioactive effluents exceed twtee the design objective doses of Appendix !. For sites containing up to 4 reactors, it is highly unlikely that the resultant done to a meeber of the public will exceed the done lients of 40 CTR 190 if the indiv.idual reactors remain within the recorting requirement level. The Special Report will describe a course of action that should result in the limitatfort of the annual dose to a member of the public to within the 40 CTR 190 limits. For the perooses of the Special Report, it any be assumed that the dose commitaunt to the sember of the public from othat uranium fuel cycle sources is negligible, with the exception that dono centributions from other nuclaar fual cycle facilities within a radius of 8 km eust be considered. If the dose to any member of the public is estiasted to exceed the requirements of 40 CTR 190, the Special Report w!th a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have ret 'stready been cor14cted), in accordance with the provisions of 40 'TR 1.90.11 and 10 CTR 20.405c, is considered to be a timely request aad fulfills the requirements of 40 CTR 190 until NRC ntaff action is completed. The variance only relates to the lialts of 40 CIT 190, and does not apply in any way to the other requiromants for dose limitation 10 CTR to, as addressed in Specifications 3.25.1 and 3.23.2. An individual is not considered to be a memb6r of the public during any period in whieb he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. "wendment No. jj,161 66ee

. I, 3;t. 1,.* L25.4 acutLtdinaty.a yaan 4 Aeolicabi h t At all times ChJsatini To ensure solid radweste is reocessed in accordance w the Trocess Control Program to meet shipping and burial ground requirements. '. s.ittifieit.icati h 23.4.1 With tbs provisions of the Process Control Program not satisfied, suspend shipments of defectively processed or defectively packaged nolid radioactive waste from the site. 3.25 4.2 The provisions of Epocification 3.0.3 are not applicable, g lits.nl This specification teolements the requirements of 10CTR$0.36a and General Design Criterion 60 of Appendix A to 10CFR$0. i\\ I d f.nendment No. Sal,JJJ,161 66ff 3 s gw .-e---

.n r - -- { ,1 ,;e: [a SURVEiMANCE_ REQUIREMENTS ye ] '4.0.1 Surveillance Requirements shall be met during the operational modes 7 or other conditions specified for individual I.latting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. ^ 3^ -

t. 0. 2 Each Surveillanco Requirement shall be performed within the specified time interval vith a assimum a!!owable extension not to exceed 25% of the surveillance interval.

'4.0.3 Teilure to perform a Surveillance Ret;uirement within the allowed surveillance interval defined by Speciffr.stion 4.0.2, shall constitute noncospitance.with the OPERADILITf requirements for a Lietting Conditien for Operation. The timo limits of the Action requirements are applicable at the time it is identified that a surveillance Requirement has not been performed.-- The time at which the Action is taken may be delayed for up to i 24 hours to permit the coepletion of the surveillance when the allowable .outJge ties limits of the Action requirements are less than 24 hours. Surveillanco Requirements do not have to be performed on inoperable equipment. ( 4.0.4 Entry fato an operational mode or other specified condition shall 1 not be sede unless the Surveillance Requirement (s) associated with the Limitit.g Condition for Operation has been performed within the ntated surveillance-intervs1 or-as otherwise specified. This provision shall not - prevent passage through or to operational modes se required to comply with Action requirements. 4.0.5 Surveillance Requirements for inservice inspection and testing of A5ME Code Class-1,2, and 3 couponents shall be' applicable as follows: Inservice = inspection of ASME Code Class 1,2, and 3 components a. and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME 2 oiler and Pressure Vessel Code and applicable Addenda as required by 10 CTR 50, Section 50.55a(s), except where specific written rettet has been granted by the Commission pucsuant to 10 ) CTR 50, Section 50.55a(g)(6)(1), m S l Aeondment No. #,n,y,J#,161 ' 67 i ,.s

l 4'~

~ , 'j %, e a.,L.., e _; e ir - U - --ev- ~

• * * ' ~ * ~ ~
• ~ ' *

" * * " " ' " ~ " ,e

w 7. d 4.1 ') 3Q!!1WCE REQUIREMENTS 1 Continued) 5 l

.f 4.0.5 (Continued) 4 h.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Ccde and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and i Pressure Yessel Code and applicable Addenda shall be applicable as I follows in these Technical Specifications: ASME Boiler and Pressure Vessel Required frequencies for Ccde and applicable Addenda performing insetvice terminology for inservice inspec tion and test ing Inspecticin and testinx activities actJvities Weekly At least once per 7 days No1thit At leest once per 31 days Quarterly or every 3 a.onths At least once per 92 days Semiannually or every 6 months At least once per 154 days Yectly or annually At least once per 366 days c. The provis'.ans of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities. d. Performen:o of the above inservice inspection and testing activities shall be in addition to other specified Murveillance Requirements. e. Nothing in tha ASME Boiler and Pressure Vessel Cede shall be construed to supersede the requirements of any Technical Spccifiestion. 4.1 OPERATIONAI. SAFETY ITEMS Applicability, Applies to items directly related to safety limits and limiting cooditions for operation. Ohlectivo To specify the sinimus frequency and type of surveillance to be applied to unit equipetat and conditions. Specification a. Tie einisua frequency and type of surveillance raquired for reactor protective system and eagineered safeguards system instrumentation when the reactor is critical shall be as stated in Table 4.1-1. Amendment No.161 67a

y. m.

>) LT l .e LO

l.,

1 'f.a OPERATIONAli SAFETY ITEMS (continuad} ] u, 4.1 (Continued) b. Equipment and sampling test shall be performed as detailed in 7 Table 4.1-2 and 4.1-3. ..? Discrepancies noted during surveillance testing will be { c. corrected and recorded. ] d. A power distribution asp shall be made to verify the expec+,ed I powet distribution at periodic intervals at least every 10 et'ective' full power days using the incere instrumentation del ctor systee. + RAKl3 4.0.1 thrsygh,,4.0.5 Establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Survelliance Requirements stated in the Code of Federal Regulations, 10CTR 50.36(c)(3): 1 "Surve111 race Requirementn are requirements relating to test. calibra.tfon, or inspection to ensure that the necessary quality of systems and componeuts is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be rat." 4.0.1 Xstablishes the requirement that surveillances must be performed during the operational modes or other conditions for which the -requirements of the Limiting Conditions for Operation apply unless otherwise stated in.an individual-Surveillance Requirement. The purpose of this specification is-to ensure that surveillances are performad to verify the operational'sta'.a e.V systems and compcnents and that parameters are within specified limits to ensure safe operat. ton-of the faellity when the plant is in a mode or other specified condition for which the' associated Limiting Conditiens for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an operational mode for which the requirements of the associated' Limiting Condition for Operation do not apply unless otherwise specified. r r u . Amendment No.- 13 161 67b 4 e e. q ret- % +aang

.. ~ - /f 1 I,. d. MEES (continued 1 3 4.0.2 Establishes the limit for which the specified time interval for Survel11snee Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance ~ scheduling and consideration of plant operating conditions that say not be suitable for conducting the surveillance; e.g., transient conditions or 1 other ongoing surveillance or esintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillaric.s that are performed at each refueling outege and are specified with an t 18n anth surveillance interval. It is not intended that this prevlolon be vseo repeatedly as a convenience to extend surveillance intervals bevond that specified for surveillances that are not performed during refueling outages. The Ifmitation of Specification 4.0.2 is based on engineering judgemetic and the recognition that the most probable result of any 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 significantly degraded beyond that obtained from the specified surveillance intervals. 4.0.3 Establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems end components are assumed to be OPERABLE when Surveillance Requirements nave been satisfactorily performed within the specified time interval. However nothing in this provision is to be construed as leplying that systeer er components are OPERABLE when they are found or known to be inoper,4. although still meeting the Surveillance Requirements. This spect son also clarifies that the Action requirseents are applicable when Surs illance Requirements have not been completed within the allowed surMilance interval and that the time limits of the' Action requirements apply from the point in time it .is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was creeeded. Completion of the Surveillance Requirement within tbs allowable outage time limits of the Action requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2 was a violation of the OPERA.81LITY requireewis of a Limiting Condition for Operation that is subject to enforcement action. Turther, the failure to perform a curve 111ance within the provisions of Spacification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10CTR 50.73(a)(2)(1)(3) because it is a condition prohibited by the plant's Technical Specifications. If the ellowable outage time limits of the Action requirements are less than 24 hours or a shutdown is required to comply with Action requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the Action requirements. This provides an adequate ties limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is. required to cosply with Action i requirements or before other remedial measures would be required that may precluds coepistion of.a surveillance. The basis for this allowance L Amendment No. 161 67c .,. _ ~.

~. - - - - .e I,, 4 '] !MES (rantinuedl ),' includes consideration for plant conditions, adequate planning, availability of personnel, the time to tred to perform the surveillance, f and the safety significance of the del.y in completing the seguired i surfaillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of mode changes imposed by Action requirements and for completing Surveillance Requirements that are applicable when an exception to the require ents of Specificatien 4.0.4 is allowed. If a surveillance is not coepleted wi.hin the 24 hour allowance, the time limits of the Action requirements are applicable at that time. When a surveillance is performed within the 24 hour allowance and the Surveillance Requirements are not net, the tino limits of the Action requirements are applicable at the time that the aurveillance is terminated. If the Action requirements are greater than 24 hours, sufficient time exists to complete the surveillance. 1 Surveillarice Requirements do not have-to be performed on inoperable i equipennt because the netion requirements define the remedial measures that apply. However, the Surveillance Requirements have to be set to demonstrate that inoperable equipment has been restored to OPERA 6LE status. 4.0.4 Establishes the requirement that all applicable surveillances oust be set before entry into an operational mode or ather condition of operation specified in the Specification. The purpose of this Spwification 1s to ensuco that systes and cosponent OPERABILITY requirements or parameter limits are met before entry into a mode or condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in operational modes or other specified conditions associated with plant shutdown as well as startup. Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Condittens for Operation are met during initial plant startup or following a plant outage. 4 Wen a shutdown is required to comply with Action requirements, the 1 :ovision of Specification 4.0.4 do not apply because this would delay piscing the faallity in a lower mode of operation. o 4_.,0_.5 Establishes the requirement that inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, l and 3 pumps and valves shall be performed in accordance with a l -periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements i apply except when relief has been provided in writi.13 by the Commission. This specification includes a clarification of the frrquencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable l Addends. This clarification is provided to ensure consistency in surveillance intervals throughout Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities. I I Amendment No. 161 67d t. I

- ~---. - _ ~.. I j

jV.

59.'- -BASES feentinued) -t Under the terms of this specification, the more restrictive requirements of the Technical specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of. Specification 4.0.4 to perform surveillance activities before entr> into y an1 operational mode or other specified condition takes precedence over the i ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification' definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its speelffed + function, is declared inoperable and trkes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours be i being declared inoperable. Check Teilures such as blown instrument fuses defective indicators, faulted amplifiers which result in "upsdale" or 'downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Turthermore, such failures are, in many cases, revealed by alarm or annunciator Action. Comparison of output and/or sr.to of independent channels measuring the same variable supplements this type of built in surveillance. Based on experience in operation of both conventional and nuclent plant systems. when the plant is in operation, the minimum checking frequency stated is deemed adequate for reactor system instrumentation. Calibration Calibration shall be performed to assure the presentation and acquisition of accurate information. The nuclear flur (power range) channels shall be calibrated at least twice weekly (during steady state operating conditions) against a heat balance standard to compensate for instrumentation drif t. During non-steady state operation, the nuclear flux channels shall be calibrated daily. to compensate for instrumentation T drift Snd changing rod patterns and core physics parameters. 4 .i ' i I Amendment No.161 67e-4 I 4 ^ c 1

.y ,,,- QQ.pjQ.f e E,4g i.1-1 (Cant.1 th anel Descrintinn Check Test. Calibrate -E==arkt. 5'

30. Decay heat removal.

'S(1)(2)' M(1)(3) R. ' (1)L Includes RCS Pressure Analog Channel sy.< ten isolation valve .; (2).. Includes CFT 1 solation Valve Position .aucestic closure and ' (3)' Sha11'also be tested during refueling interlock system shutdown prior;to repressurization at. a pressure greater than 300 but. less than 420 psig. .31. Turbine overspeed' trip NA' E NA II) The provisions of Specification 4.".4

mocksnism are not applicable.

32. ~ Diesel generator.'-

H' Q NA protective relaying starting' interlocks - and circuitry

33. Off-site power indervoltage W

R(1) R(1) (1) Shall be tested during refueling .and protective relaying shutdoen to demonstrate selective interlocks-and circuitry load shedding interlocks function during manual or automatic trans-fer of Unit 1 auxiliary load to 1 Startup Transformer No. 2.

34. Borated water storage W

NA E tack level indicator

35. Reactor trip upon loss M

PC E of main feedwater circuitry 4 i .a . I. i Amendment No. 4,37.59,49.67,92. 161 72

q* ~A M ~ ~ ' "~ ~ ~ ^ ~ ~ WA-MP ^ ~ ^ 1 s wm m QE e.. +.a,x + .3AA year: limits-_of Specifications 3.25.1.2 and 3.25;2.2. This 54 Speciel Report is not required if the measu';ed level of: !Y M radioattivity was not the result of plant' effluents,- y -however, in-such an event, tbo condition shall be. reported lC rend dercribed in the Annual Radiological Environmental %:L Report.: p s c. With milk or fresh' leafy vegetable samples unavailable from j . any of the sample locations required by Table 4.29-1, a identify locations for_ obtaining replacement samples and odd "'"~ .them to.the radiological environmental monitoring program within 30 days.= The specific. locations from which samples ~ ^ -were unavailable may -then be deleted from the monitoring a, program.1 - Identify the causes of the unavailability of samplet and identify the new location (s) for obtaining-replacement' samples in the nort Semiannual Radioactive Effluent Release Report and also include in the report a ? revised table-for the ODCM reflecting the_new location (s). -d.o The provisions =of Specification 3.0.1 are not applicable. ] 4.30d.5/Theresultsofanalysesperformedontheradiological . j envirennental monitorin samples shall be sus.marize<1 in the Annual Radiological Environmental Report. The radiologleall monitoring program required by this specification provides

measurements

of radiation and of radioactive materiala-in those. exposure r

pathways and?for those radionuclides which lead-to the highest potential ' radiation exposures of individuals resulting 'frou-the station operation.. . t This mohitoring program.thereby supplements.the radiological effluents monitoring!prorram by verifying that the measurable concentrations of tradioactivi:-aterials and levels of. radiation are _not; higher, than expected on the basis of the offluent measurements and sodaling.of the environmental zexposure< pathways. The initially.specified, monitoring program will be Leffective for at"leen the first three years of commercial operatien.

Following thistperiod, program changes may beJinitiated based on-

- ;operationalexperience. The detecticn capabilif:les: required _ by Table '4.30-2 are atate-of-the-art 'for routine-environmental measurements in industrial laboratories. The. v LLD's for ' drinking water meet. ths requirements of.40 CFR 141. ~ ' 4 .tv7 s w p2 g .h j-. + b. c, - N .[ l l l( - Amendeont No. pp,JJp,161 110tt o e ..aw.

~=

1 f F v vvww e e a-w+-r* +- m-

,&

- - -r-h-r- s ame v+-u =,

• -ser

%l +. js; o. Radiological Envie n ental Monitoring at 4.36.2 .Lani_dt.t h ug 4 Apslisabilitv Applies at all times Objectives: This speelfication will identify changes in use of the unrestricted areas. Egreifica51ons: 4.30.2.1 A land use census shall be conducted and shall identify the location of the nearest milk. animal, the nearest residence, and the neanst garden

• of greater tha 500 square feet producing fresh leafy vegetables in each of the 16 seteorological sectors within a distance of five miles from the ANO-1 reactor building.

t 4.30.2 2 ~ The bnd use census shall be condacted at least once per 12 - months between the dates of June 1 and October 1, by door-to-door survey, aerial survey..or by consulting local agricultural ~ authorities. 4.30.2.3 s. Vith a land-use census identifying a location (s) which yields a calculated dose commitment due to 1-131, tritius, and radionuclides -in particulate forra greater than the values currently heing calculated in Unit 1 Specification 4.29.3 and Unit 2 Specification 4.11.2.3 sabnit location-description in the Sewiannual Radioactive isffluent Release Report per Specification 6.12.2.6. h. With a land uso conses' identifying a location (s) which yields a esiculated dose cosmitment (vis the same exposura J ~ pathway) greater.than at a location-free which samples are corrently being obtained in accordance-with Specification '4.30.1.1, identify tbr new location'in the Semiannual Radioactive Effluent' Release Report per Specification 6.12.2.6.J The new' location shall be added to the radiological environmental monitoring program within,30 days,~if posaible. m sampling.locatfon having the:lowsst calculated dose commitment _ (via-the same exposure pathway) may be deleted frem this monitoring progran af ter October 31 ~ f the year in which this land use census was conducted. o 4.30.2.4 - The r6sults of the. land use census shall be included in the Ananel' Radiological Environmental Report. 4 30.2.5 _ ne provisione of Specification 3,0.3 are not applicable.

• Broad leaf vegetatico saspling may be performed at the site boundary la

~ the direction soctor with the highest D/Q in lieu of the garden census, f A Amendment No. $$,ll#, 161 110cz w, vow % eee ?

f.sl ~ ~ Y -_. 'g c..: u .4 1 j, Radiological Environmental Monitoring 4 4.30.3 InLttleberat ory Comi n 132n.ProgIts '3 Aeolicabilitn Applies to the of f-sito radioche,aistry laboratory. Qbiec tlyn To provide independent chectra on the accuracy of the measurements of radioactive material ha envirormental samples. EStalucktLcuns 4.30.3.1 Analyses aball be performed en radioactive materials supplied as part of Interlaboratory Comparisou Program which has been approved by NRC. 4.30.3.2 With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report. 4.30.3.3 The results of analysee performed as part of the above required Interlaboratory Comparison Program shall be included in the Ancuhl Radiological Environmental Report pursuant to Specification 6.12.2.3. 4.30.3.4 The provisions el specific'stion 3.0.3 are not applicable, g 113111 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and acc uacy of the mensarements of radioactive marerial in environmental sample matrices are performed as part of a quality assurance program for environmental sonitoring in order to demonstrate that the results are f reasonably valid. i l Amendment No. /$,JJ$,161 110bbb .}}