ML20155D739

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Proposed Tech Specs Re Applicability for Limiting Conditions for Operations & Surveillance Requirements for Control Rod Operability,Reactor Protection Sys Instrumentation & ECCS Actuation
ML20155D739
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/30/1988
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20155D727 List:
References
GL-87-09, GL-87-9, NUDOCS 8810110357
Download: ML20155D739 (63)


Text

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1 ENCLOSURE 1 l l

Proposed River Bend Station Technical Specification Changes I

for Applicability of Limiting Conditions for Operations and Surveillance Requirements Specifi-cation No. Title Revised Page i 3.0.4 Appitcability 3/4 0-1 h 4.0.3 Applicability 3/4 0-2 l 4.0.4 Applicability 3/4 0-2 t
3.1.3.1 Control Rod Operability 3/4 1-4  !

3.1.3.2 Control Rod Maximum insertion Times 3/4 1-7 r 3.1.3.3 Control Rod Scram Accumulators 3/4 1-10 -

) 3.1.3.4 Control Rod Drive Coupling 3/4 1-11 [

i 3/4 1-12 1 3.3.1 Reactor Protection System Instrumentation 3/4 3-1 1 3.3.2 Isolation Actuation Instrumentation 3/4 3-10  !

~l Table 3.3.3-1 Emergency Core Cooling System Actuation Instrumentation 3/4 3-35 Table 3.3.5-1 Reactor Core Isolation Cooling System ,

Actuation Instrumentation 3/4 3-56 L Yable 3.3.6-1 Control Rod Block Instrumentation 3/4 3-61 t 3.3.7.1 Radiation Monitoring Instrumentation 3/4 3-65 l I Table 3.3.7.1-1 Radiation Monitoring Instrumentation 3/4 3-68  !

) 3.3.7.2 3.3.7.3 Seismic Monitoring Instrumentation Meteorological Monitoring Instrumentation 3/4 3-70 '

j 3/4 3-73 l 3.3.7.8 Fire Detection Instrumentation 3/4 3-87 r

! 3.3.7.9 Loose Part Detection System 3/4 3-93 l

} 3.3.7.10 Radioactive Liquid Effluent Monitoring  !

j Ins trumenta tion 3/4 3-94 l t 3.3.7.11 Radioactive Gaseous Effluent Monitoring ,

1 Instrumentation ,3-99 I 3.3.8 Turbine Overspeed Protection System ,,; 3-106 i Table 3.3.9 1 Plant Systems Actuation Instrumentation 3/4 3-109 l 3.4.7 Main Steam Line Isolation Valves 3/4 4-26 i 3.4.8 Structural Integrity 3/4 4-27 l 3.6.1.4 Primary Containment Air Locks 3/4 6-8 3/4 6-9 3.6.2.3 Drywell Air Locks 3/4 6-20 l

3.6.4 Primary Containment and Drywell l Isolation Valves 3/4 6-31

( 3.6.5.3 Secondary Containment Automatic Isolation Dampers 3/4 6-51 3.7.6.2 Spray and/or Sprinkler Systems 3/4 7-21

) 3.7.6.3 Halon Systens 3/4 7 23

] 3.7.6.4 Fire Hose Stations 3/4 7-25 3

3.7.6.5 Yard Fire Hydrants and Hydrant Hose Houses 3/4 7-28 3.7.7 Fire Rated Assemblies 3/4 7-30 l

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Page 1 of 2 j e91o110357 890930 m DR MccK 0500g

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Specifi-cation No. Title Revised Page  :

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3.7.10 Structural Settlement 3/4 7-35 '

3.8.4.1 Primary Containment Penetration Conductor i

Overcurrent Protective Devices 3/4 8-25

3.8.4.2 Other Overcurrent Protective Devices 3/4 8-33  ;

3.11.1.2 Dose 3/4 11-4 l 3.11.1.3 Liquid Radwaste Treatment System 3/4 11-5 ,

! 3.11.2.2 Dose-Noble Gases 3/4 11-11 l l 3.11.2.3 Dose-lodine-131, lodine-133 Tritium, and  ;

Radionuclides in Particulate Form 3/4 11-12 3.11.2.4 Gaseous Radwaste Treatment 3/4 11-13 I 3.11.2.5 Ventilation Exhaust ireatment 3/4 11-14 i 3.11.3 Solid Radioactive Waste 3/4 11-17 3.11.4 Total Dose 3/4 11 18 3.12.1 Radiological Environmental Monitoring 3/4 12-2

. 3.12.2 Land Use Census 3/4 12-13 .

] 3.12.3 Interlaboratory Comparison Program 3/4 12-14 [

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3/4.0 APPLICABILITY-

, LIMITING CON 0! TION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required dLring the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be me t.

3.0.2 Noncoer11ance with a Specification shall exist when the requirements of ~

the Limiting Condition for Operation and associated ACTION requirements are not set within the specified tied intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intenals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for*0peration is not met, except as provided in the associated ACTION requirosants, action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in an OPERATIONAL CONDITION in 'vhich the Specification does not apply by placing it, as applicable, in:

1. At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
2. At lean HOT SHUTDOWN within 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 SHUTDOWN 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 seasures are completed that permit operation under the ACTION requirements, the ACTION say be taken in accordance with the specified time limits as sensured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

This Specification is not applicable in OPERATIONAL CCN0!TIONS 4 or 5.

3.0,4 Entry into an OPERATIONAL C0h0! TION or other specified condition shall insert A not be made= =1:00 the e**dit&***-fee-th*-kiMttet-4tWh fer ^;;retiere-eft 4 t0-T This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to emply with ACTION requirement:. Exceptions to these requirements are stated in the individual Specifications, insert A mhen the conditions for the Limiting Condition for Operation are not rret and the associated ACTION requires a shutdo.n if they are not met .ithin a specified time interval.

Entry into en OPERAtl0NAL CONDITION or other stecified condition may be made in accordance eith the

  • ACTION reqJ retents . hen conf ormance to tr.em permits continued operation of the faci!!ty for en unlimited period Of TIPC' -

_y_ __ __ w - _ ~

R M R BEND UNIT 1 3/4 0-1

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APPt.!CA8!LITY pLRVE!!.LANCEREQUIRENINTS 4.0.1 Surveillance Requirements shall be set during the OPERAT!0hAL CONDITICNS or other conditions spec 1Ned for individual Limiting Conditions for Operation unless otherwise st4ted in un individual Surveillance Requirement.

4.0.2 tech Surveillanca Requirement shall be performed within the specified

time interval with:
a. A saximum allowable extension not to exceed 25% of the surveillanet interval, but
b. The combined time interval for any 3 consecutive su vei' lance intervals shall not exceed 3.15 times the specified surveillance Interval-insertB]

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." m ri :rr u . r . .m a m ....oy ..,~,. e r m. . .. r...'...'furve,illance.... requirements do not have t6 5

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't O^ M 5 m d L-perforned on ~1noperable equipment.

if k-t:n- f 4.0.4 Entry into an CPERATIONAL CONDITION or other specified ecplicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limitin Condition for Operation have been performed within the '

applicable surve 11ance interval or as otherwise specified, c T

\

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 cosiponents shall be applicable as follows:

a. Inservice inseection of A5ME Code Class 1, 2. and 3 components and inservice testing of ASME Code Class 1, 2. and 3 pumps anc valves shall be performed in accordance with Section XI of the ASME toiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50. L (g), except where specific written reifef has been granted by the Coasission pursuant to 10 CFR 50, Section 50.55a(;)

(6) (1).

b. Surveillance intervels s>acified in Section XI of the ;.5ME Boiler i and Pressure 'ssel Code and appitcaele Addenca for the inservice inspection and testing activities required by the ASME Boiler and Pressure Yessel Code and applicable Addenda shall be applicable as i

follows in these Technical Specifications:

= - ~ __.

allo.ed surveillance interval defined by Specification 4.0.2. shall constitute non-cenpliance with the OPERABILITY requiremerts f or a Limiting Condition f or Operation.

The ilme limits of the ACTION requirotents are applicable at the time it is identified

, 9 hat a SURVEILLANCE REQUIREMENT has not been performed. The ACTION requirements mey be delayed f or up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the alle.able_ outage time limits of the ACTICN requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

n W_ _

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This provision shall not prevent passage through or to OPERATICUAL CONDITIONS as required to cceph with ,ACTICH requirements.

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AEACTIVITY CONTROL SYSTEMS i 1!MITING CONDITION FOR OPERATION (Continued) l l

ACTION: (Continued)

4. No "slow" control rod, "fast" control rod with individual scram  !

insertion time in excess of the limits of ACTION a.2, or other- l wise inoperable control rod occupies an a'djacent location in any direction, including the diagonal, to another such control rod,.  !

Otherwise, be in at least HOT $HUTDOWN within 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, l

b. With a "slow" control rod (s) not satisfying ACTION a.1, above:
1. Declare the "slow" control rod (s) inoperable, and
2. Perform the Surveillance Requirements of Specification 4.1.3.2.c

) at least once per 60 days when operation is continued with three or more "slow" control rods declared inoperable.

1 Otherwise, be in at least HOT $HUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. With the easimum scram insertion time of one or more control rods exceeding the maximum scram insertinn time limits of Specifica-l tion 3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue provided that: ,
1. "Slow" control rocs,'i.e., those wnich exceed the limits of  ;

$pecification 3.1.3.2, do not sake up more than 20% of the.10%

lample of control rods tested.

2. Each of these "slow" control rods satisfies the limits of ACTION a.1. ,
3. The eight adjacent control rods surrounding each "slow" control
red are
i a) Demonstrated through measurement within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> t.o sat.isfy i the maximus scran insertion time limits of Specifica-tion 3.1.3.2, and I b) OPERAALE. I l
4. The total nunoer of "slov control rods, as determined by Speci- l fication 4.1.3.2.c. when added to the sue of ACTION a.3, as l

determined by Specification 4.1.3.2.4 and D, ooes not exceed $.

Otherwise, be in at least HOT $HUTDCWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. l

! L W @M M W@RWpM i R!YERBEND-UNIT 1 3/4 1-7

REACT!V!TY CONTROL $YSTEMS CONTROL 400 SCRM ACCUMULATOR $

L!N! TING CON 0! TION FOR OPERATION ACTICN: (Continued) a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

2., With more than one withdrawn control red with the associated screa accumulator inoperable ~and with no control rod drive pump operating, tunediately place the reactor mode switch in the

Shutdown position.

d )The provisions of Specification 3.0.4 are not applicable. l 1

$URVE!LLANCE REQUIREMENTS l 4.4.3.3 Each control rod scram accumulator shall be determined CPERA8LE:

s. At least once per 7 days by verifying that the indicated pressura is greater than or equal to 1520 psig unless the control rod is inserted and disarmed of scrammed,
b. At least once per 18 months by:
1. Performance of ;;

i

) a) CHANNEL FUNCTICNAL TEST of the leak detectors, and b) CHANNEL CALIBRATION of tho pressure detectors, and verifying an alars setpoint of 11520 psig on decreasing pressure.

2. Measuring and recording the time for up to 10 minutes that each individual accumulator check valve maintains the associated accumulator pressure above the alars set point with no control rod drive pump operating.

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RIVLR 8(ND - UNIT 1 3/4 1-10

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REACTIVITY CONTROL $YSTEMS  !

l 00NTROL 200 ORIVE COUPt.!NG i

LIMITING CON 0! TION FOR OPERATION 3.1.3.4 All control rods shall be coupled to their drive mechanisms. l APPLICA81LIW: OPERATIONAL CON 0!TIONS 1, 2 and 5*.

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ACT10N:

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a. In OPERATIONAL CON 0! TION 1 and 2 with one control rod not coupled to i its associated drive mechanisa, within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
1. If permitted by the RPCS, insert the control rod drive sechanism to accomplish recoupling and verify recoup 1tng by withdrawing the control rod, and:

a) Observing any indicated response of the nuclear instrumenta-i 8

tion, and )

b) Demonstrating that the control rod will not go to the  !

1 ut,$rAvalpoJition. ~__ f= , i c) The provisions of Sreetticatien_3.0.4erenotypticeejle. l l

2. TEupTNaccomp1Ndin the first attempt or, if not .

I permitted by the RPC3, then until permitted by the APCS, declare  !

, the control rod incperable, insert the control rod and disarm the  :

] associated directional control valves ** either:  !

a) Electrically, or i

b) Hydraulically by closing the drive water and exhaust water isclation val.ves.

Otherwise, be in at least HOT $HUTDCWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

. b. In CPERATIONAL CON 0! TION 5* sith a withdrawn control rod not couplet."

) to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

I 1. Insert the control rod to accomplish recoupling and verify 1 recoup 11ng by withdrawing the control roc and comonstrating that

the control rod will not go to the overtravs1 position, or a

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I l "At least each withdrawn control rod. Not applicable to control rods removed j per $pecification 3.9.10.1 or 3.9.10.2.

    • May be rearned intermittently, under administrative control, to persit I

testing associated with restoring the control red to OPERA 8LE status, i

l RIVER BEND UNIT 1 3/4 1-11 l

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REACTIVITY CONTROL $YSTEMS ,

CONTROL 200 ORIVE COUPLING LIMITING CON 0! TION FOR OPERATION ACTION: (Continued)

2. If recoupling is not accomplished, insert the control rod and i i.

disere the associated directional control valves

  • either: -

a) Electrically, or b) Hydraulica)1y by closing the drive water and exhaust water isolation valves.

( 5 })The provisions of Specification 3.0.4 are not applicable. l SURYt!LLANCE REQUIREMENTS 4.1.3.4 Each affected control red shall be demonstrated to be coupled to its drive mechanism by observing any indicated response of the' nuclear instrumen-i tation while withdrawing the control rod'to the fu1Ty* withdrawn position and then verifying that the tontrol rod drive does not go to -the overtravel position: ,

a. Prior to reactor criticality after completing CORE ALTERAT!0NS that j could have affected the control rod drive coupling integrity,
b. Anytime the control rod is withdrawn to the "Full out" position in .

subsequent ' operation, and .

{

, c. Following maintenance on or modification to the control rod or ,

control rod drive systas which could have affected the control red I

l drive coupling integrity, i

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1 "May et rearned intersittently, under aaministrative control, to permit testing associated with restoring the control rod to OPERABLE status.

t I

3/4 1-12 I RIVER BEND - UNIT 1 l

  • . , . - - . . - . . . . . ~ .

i HOLQ[R y Q 3/4.3 INSTRUMENTATION i

AUC 7 W 3/4.3.1 REACTOR PROTECTION SYSTEN INSTRUMENTATION g , ,',, ,, ,,

LIMITING CON 0! TION FOR OPERATION Y " '_~ ~ '. .

3.3.1 As a minimum, the reactor protectiore nstes instrumentatYdl,Ms showa in Table 3.3.1-1 shall be OPERA 8LE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

, ACTION:

a. With the number of OPERABLE channels less than required by the Mint-mus OPERA 8LE Channels per Tri Systes requirement for one trip system, place the inoperable channel ystesLifL t ed condittan* te thin one hour. = r e , -
  • 9 9 _. .. . l' b.

C_iNO Y Y 9 -" -

With the number of OPERABLE channels less than required by the Minimum ,

OPERABLE Channels per Trip System requirement for both trip systees, '

1 slace at least one trip systee** in the tripped

  • condition within one wur and take the. ACTION required by Table 3.3.1-1.

_ SURVEILLANCE REQUlaEMENTS l'

! 4.3.1.1 Each reactor protection system instrumentation channel shall be demon- '

strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL l TEST and CHANNEL CALI8 RAT!0N operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1 1.

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4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic o I i all channels shall be performed at least once per 18 months.*** peration of  !

l 4.3.1.3 The REACTOR PROTECTION SYSTEM Resp 0NSE TIME of each reactor trip l functional unit shown in Table 3.3.1 2 shall be demonstrated to be within its l limit at least once per 18 months. Each test shall include at least one channel 1

per tris systes such that all channels are tested at least once every N times  ;

! 18 mont$s where N is the total number of redundant channels in a specific reactor l 1 trip systee, s .

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' *An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the ino>erable channel shall be restored to OPERA 8LE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTW4 required by i Table 3.3.1-1 for that Trip Function shall be taken. . .

! **The tri> systen need not be placed in the tripped condition if this would l cause tw Trip Function to occur. When a trip systes can be placed in the q tripped condition without causing the Trip Function to occur place the trip systemwiththemostinoperablechannelsinthetrippedcondItion;ifboth systems have the same number of inoperable channels, place either trip systen l in the tripped condition. The requirement to place a trip systes in the i' tripped condition does not apply to Functional Units 6 and 10 of Table 3.3.1-1.

      • Logic Systen Functional Test period say be extended as identified by note 'p' on Table 4.3.1.1-3.

j RECEIVED, RIVER BEND - UNIT 1 3/4 3-1 AUG 6 1987 Amendzent No. 8 SOC i

25TitMENTAT10N 3/4.3.2 150LAT!0N ACTUATION INSTRUMENTATION LIMITHs0 CONDITION FOR OPERATION 3.3.2 The 1 olation actuation instrumentation channels shown in Table 3.3.21 shall be OPflABLE with their trip setpoints set consistent with the values shown in the Trip setpoint column of Table 3.3.2 2 and with 150LAT!0N SYSTEM RESPONSE TIM as shown in Table 3.3.2 3.

APPitcA31LITY: As shown in Table 3.3.2-1.

ACT1088:

a. i
With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Yalues column I of Table 3.3.2-2, declare the channel inoperable untti the chanM1
is restored to OPERAALI status with its trip setpofnt adjusted consistent with the Trip $etpoint value, b.

With the number of CPERA8LE channels less than required by the Minfaus OPERMLE place Channelschanne the inoperable per Trip systes requirement for one trip s s.tes .

r ed e hour. - % 3 t"._ 3 M U p '. .._ 19 .

c.

With the number of OPERABLE channels less than re QPERMLE Channels per Trip systen requirement fo.'both quiredtripbysystees the Minimum 1

l place at least one trip systes" in the trtoped condition within ane, Mur and take the ACTION required by Table 3.3.2-1.

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  • An (noperable channel need not be placed in the trfpped condition where this t

would cause the Trip Function to occur. In these cases, the inoperable channel Table 3.3.21 for that Trip function shall be taken,shall be restored to i

! **The the Triptrip systes Function need not be placed in the tripped condition if this would cause to occur.

i When a trip systan can be placed in the trfpped

. condition without causing the Trte Function to occur, place the trip system witte

the most inoperable channels in tw tripped condition; if both systems have the same number of inoperable channels, place either trip systee in the tripped condition.

RINT'1 BEND - UNIT 1 3/4 3 10 l

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.g TA8LE 3.3.3-1 (Continued)

U EMERGENCY CORE COOLING $YSTEM ACTUATION INSTRLMENTAT!0N

{

ACTION  !

ACTION 30 - Wi';h the number of OPERA 8LE channels less than recuired by the Minimus OPERABLE Channels per Trip Function requirement:

i

a. With one channel inoperable, place the 'perable o channel in the tripped condition withir one hou or declare the. \

associated system inoperable,

b. With more than one channel inoperable, dec14 1 the associated systes inoperable.

i' ACTION 31 - With the nuseer of OPERA 8LE channels less than required by the Minisue OPERA 8LE Channels per Trip Function requirement, declare the associated A05 trip system or ECCS inoperable.

ACTION 32 -

With the number of CPERA8LE channels less than the Minimum CPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

ACTION 33 - With the number of OPERA 8LE channels less than required by the Min'imum OPERA 8LE Channels par Tri4 Function requiremont, restore i

the inoperable channel to CPERA3LE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or

~

declare the associated ADS valve or ECCS inoperable.

, ACTION 34 - With the nunee' of CPERABLE channels less than required by the '

4 Minimus CPERA',LE Channels per Trip Function requirement:

a. For one trip systes, plag '

condition within one hou $jorthat trip systes declare the NPCS in the trippec system inoper- l able, i

b. For both trip systems, declare the HPCS system inoperacle.
ACTION 35 - Vith the number of CPERABLE channels less than required by the
Minteue OPERA 8LE Channels per Trip Funct. ion roovirement, place ,

l at leas hone inoperable channel in tha tripped condition within

one hou@or declare the HPC5 system inoperable.

l <

l Action 36 - With the nuster of OPERA 8LE channels one less than the Total  !

Mumber of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> *; operation say then continue untti per-1 forwnce of the next required CMANNEL FUNCTIONAL TEST. Othen i s e , i declare the associated energency diesel generator inoperable and )

l take the ACTION required by $pecification 3.8.1.1 or 3.8.1.2, as i

appropriate.  ;

ACT10N 37 - With the number of CPERA8LE channels less than the Total Number l of Channels, declare the associated eeergency diese) generator l l inoperable and take the ACTION required by Specification 3.8.L 1 l or 3.8.1.2, as appropriate, l

"The provisions of Specification 3.0.4 are not applicable.

1 t!VER BEND - UNIT 1 3/4 3-35

l t

I TA8LI 3.3.5-1 (continued) ,.

,- .6 ,

REACTOR CORC 1501.ATFON C00 CNG SYSTEM M

ACTUA"!0N IN5"Rt*ENTA"!CN ACTION 50 - With the number of CPERASLE rhannels less than required by the Minimum CPERASLE Channels per Trip Function requirements

a. For one trip systee, pla that trip systee in the tripped a condition within one hou er declare the RCIC systee l insperable. .

I b. For both trip systems, declare the RCIC syntes inoperable.

ACTION 51 - With the number of CPERASLE channels less than required by the l Minteue OPERA 4LE channels per Trip Function requirement, declare the RCIC systes inoperable.

ACTICH 52 - With the number of CFtRA8LE channels 1410 than required by the Minimue OPERABLE Channwls per Trip Function requirement, place at least one inoperable chan.741 in the tripped condition within one hour nr declare the RC!t system inoperable.

ACTION 53 - With the numbe of CPERABLE channels less than required by the l

Minimus CPERASLE Channels per Trip Function requiremeat, restorg ,

the inoperable channel to CPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or  !

declare the RCIC system inoperable.

i

[  !

l i

l l

l i

1 l ;

i \

l 1

l

"'h: ;r::tet:n: :? 5;::tfie:t!:n 3.0 ' :& net 1;;t! 0510. ' f' RIVER BEND - UNIT 1 3/4 3 56

l t

TABLE 3.3.6-1 (Continued)

- CONTROL R00 BLOCK INSTRUMENTATION ACTION ACTION 60 - Declare the RPCS inoperable and take ths ACTION required by Specification 3.1.4.2.

ACTION 61 -

With the number of OPERABLE Channels: .

a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inopera channel in the tripped condition within the next hou
b. Two or more less than required L' the Minimum OPERABLE Channels per Trip Function reouirement, place at least one inop ble channel in the tripped condition within one hour ACTION 62 - With the number of OPERABLE channels less than required by the

- Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the, tripped condition within one,hou NOTES

  • With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.20.1 or 3.9.10.2.
    • OFERABLE channels must be assnciated with SRM required OPERABLE per l Specification 3.5.2. . l 5E $Mi kUh (a) This function shall be automatically bypassed i? detector count rate is

> 100 eps or the IRM channels are on range 3 or higher.

(b) This function shall be automatically bypassed when the associcted IRM channels are on range 8 or higher.

(c) This function shall be automatically bypassed when the IRM channels are on range 3 or higher. ,

1 (d) This function shall be automatically bypassed when the IRM channels are l on range 1. .

(

l e

4 1

RIVER BENO - UNIT 1 3/4 3-61 l

N. -

.. INSTRUMENTATION

%n, , .L 3/4.3.7 MONITORING INSTRUMENTATION RA0!ATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERA 8LE with their alkra/ trip setpoints within the specified limits. ,

APPLICABILITY: As shown in Table 3.3.7.1-1.

ACTION:

a, With a radiation monitoring instrumentation channel alarm / trip setpoint exceeding the value st.own in Taole 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable. .

b. With one or sort radiati.on monitoring channels inoperable, take the ACTION required,by Table 3.3.7.1-1.
c. TheprovisionsofSpecificatioh3.0.3 re not applicable. l SURVEILLANCE REQUIREMENTS l

4.3.7.1 Each of the above required radiation monitoring instrumentation  !

channels shall be demonstrated OPERABLE by the perforncnce of the CHANNEL CHECX, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1.

RIVER BEND - UNIT 1 ,

3/4 3-65

_ . _ _ '*- . - _ _ _ - _ . . . . - - _ _ . _ _ _ -._,_.i___ --

i l

TABLE 3.3.7.1-1 (Continued)

.I RADIATION MONITORING INSTRUMENTATION ACTION ACTION 70 -

a. With one of the required monitors inoperable, .a*

operable channel to OPERABLE status within 7 dayshor,:w.n ithinin . l the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the control roos air conditioning system in the emergency mode of operation,

b. With both of the required monitors inoperable, initiate and maintain operation of the contre,1 room air conditioning system in the emergency mode of operation within one hour.

ACTION 71 - With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 72 - With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, effluent raleases via this pathway may continue for up to 30 days provided grab sam- .g ples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a g these samples are analyzed for gross activity within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sW. -

l ACTION 73 - With the number of channels OPERABLE less than required by the

)

. Minimum Channels OPERABLE requirement, releasea ma to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided h y continue l

a. The offgas system is not bypassed, and
b. At least one post treat. ment noble gas activity effluent monitor is OPERABLE; ,

Otherwise, be in at least{ itnin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l STARTUP i

l 1

l The provisions of Specification 3.0.4 are not applica6le. l l RIVER BEND - UNIT 1 3/4 3-68 l

I INSTRUMENTATION 3

SEISMIC MONITORING INSTRUMENTATION "

LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 sna11 l be OPERABLE. '

~

APPLICA8ILITY: At all times.

ACTION:

a. With one or more of the above required seismic monitoring instruments l inoperable for more than 30 days, prepare and submit within the next 10 days a Special Report to the Commission, pursuant to Specifica-tion 6.9.2, outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status,
b. are not applicable.

TheprovisionsofSpecificatio[3.0.3 l dI '

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL FUNC-TIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1. s l

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated

  • during a seismic event greater than or equal to 0.01g shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be retrieved'from actuated instrueents and analyzed to determine the magnitude of the vibratory ground motion. Within 10 days, a Special Report shall be prepared and submitted to the Commission, pursuant to Specification 6.9.2, describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety, i

l l

RIVER BEND - UNIT 1 1/4 3-70

I g

. . , I INSTRUMENTATION

[,-l:i..

.c; ,

METEOROLOGICAL HONITORING INSTRUNENTATION LIMITING CON 0! TION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERA 8LE. .

APPLICABILITY: At all times.

ACTION:

a. With one or more meteorological monitoring instrumentation channels inoperable for more than 7 days, prepare and submit within the next 10 days a Special Report to the Commission, pursuant to Specifica-tion 6.9.2, outlining the cause of the sa1 function and the plans for restoring the instrumentation to OPERABLE status.
b. TheprovisionsofSpecificatich3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies 'shown in Table 4.3.7.3-1.

e a* aena . amov S gfg g,7g

_ "aa_- -- . ._ __ - ._. .

INSTRUMENTATION l

(

FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION ,

3.3.7.8 As a minimus, the fire detection instrumentation for each fire detection zone shown in Table 3.3.7.8-1 shall be OPERABLE.

APPLICA8ILITY: Whenever equipment protected by the fire detection instrument i is required'~to be OPERABLE. .  ;

l i

ACTION:

a. With any, but no more than one-half the total in any fire zone, Func-tion A fire detection instruments shown in Table 3.3.7.8-1 inoperable, restore the inoperable Function A instrument (s) to OPERABLE status within 14 days or, within the next hour, establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour. If the instrument (s) is located inside the contain-sent, inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.8 and 4.6.2.6.
b. With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3.7.8-1 inoperable, or with any '

Function B fire detection instruments shown in Table 3.3.7.8-1 inoperable, or with any two or more adjacent. instruments shown in Table 3.3.7.8-1 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the' inoperable instrument (s) at least once per hour. If the instrument (s) is located inside the con-tainment, inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> gr monitor the containmant air temperature at least once per hour at the locations listed in Specification 4.6.1.8 and 4.6.2.6.

c. TheprovisionsofSpecificatiof3.0.3 re not apolicable. l SURVEILLANCE REOUIRENENTS 4.3.7.8.1 Each of the above requ' ired fire detection instruments which are ,

accessible during unit operation shall be demonstrated CPERABLE at least once 1 per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors wnich l are not accessible during unit operation shall be demonstrated OPERABLE by the  :

performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding j 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

4.3.7.8.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alares of each of the above required fire detection instru-ments shall be demonstrated OPERABLE at least once per 6 months.

I RIVER BEND - UNIT 1 3/4 3-87

i - l 1

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1

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i g

INSTRUMENTATION

(.i. '.

LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.9 The loose part detection system shall be OPERABLE.

APPLICA8ILITY: OPERATIONAL CONDITIONS 1 and 2. ,

ACTION: ,

a. With cne or more loose part detection system channels inoperable for more than 30. days, prepare and submit within the next 10 days a l Special Report to the Commission, pursuant to Specification 6.9.2, outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status. i
b. TheprovisionsofSpecificatiof3.0.3 jarenotapplicable.

SURVEILLANCE REQUIREMENTS '

4.3.7.9 Each cMannel of the loose pari detection system shall be demonstrated OPERABLE by performance of a:

. a. CHANNEL CHECK at least'once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, I l

b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
c. CHANNEL CALIBRATION at least once per 18 months.

RIVER BEND - UNIT 1 3/4 3-93

INSTRUMENTATION fQ. , N,

'Q

  • RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.10 The radioactive liquid effluent monitor!ng instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints o'f these channels shaly be determined and adjusted in accordance with the methodology and parameters in the OFFSITC DOSE CALCULATION MANUAL (00CM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive liquid effluents monitoreo by the affected channel, or declare the channel inoperable.
h. With less than the minimum number of radioactive , liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown

, in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERA 8LE status within the time specified in ACTION or explain in the next Semiannu'al Radioactive Effluent Release Report why this inoperability n the time s e i fed.

The DFOVi S i Onyt _ Spec i f I cet l et L O.4 mnot m icable.

c. e r s ons oT 5pecificatfo g 3.0. Q are not appilcable.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel sna11 be demonstrated OPERABLE by performance of the CHANNEL CHECX SOURCE CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operati'ns o at the frequencies shown in Table 4.3.7.10-1.

, v e-V.

RIVER BENO - UNIT 1 3/4 3-94

I

< INSTRUMENTATION ,

V: .

1 RADI0 ACTIVE GASECUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION __

3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their clarm/ trip

  • setpoints  !

set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The '

alars/ trip setpoints of these channels shall be determined and adjusted in -

accordance with the methodology and parameters in the CDCM. 1 I

APPLICABILITY: As shown in Table 3.3.7.11-1. i l

ACTI0I.:

a. With a radioactive gaseous efflucnt monitoring instrumentation channel alars/ trip asetpoint less conservative than required by the above Specification, imediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b.* With less than the minimum numb'er of radioactive gaseous effluent monitoring instrumentat' ion channels OPERABLE, take,the ACTION shown in Table 3.3.7.11-1. Restore the inopercble instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next Semiannual Radioactive Effluent Releast Report why this hability was_not torfected within the ti_me_ speci_f_ied.

  • Dhg p_ rov i_s l ons ot Jpec i f i cat i on_LO ._4 are notmpl icab D

~

c. TTie provisions of SpecRTeatieg3.0.3QQ.gare not applicable.

SUREVEILLANCE RE0VIREMENTS 1

4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel ,

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHE0X, '

CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencie*  !

shown in Taole 4.3.7.11-1.

l "The alann/ trip setpoints for the Explosive Gas Mixture in the Main Concenser l Offgas Treatment System are set in accordance with Specifiestion 3.11.2.6.

RIVER BEND - UNIT 1 . 3/4 3-99

t' .

1 MSTRUMENTATION f,

)r._ :,.3, ,

3/4.3.8 TUR8INE OVERSPEED PROTECTION SYSTEN l

LIMITING CONDITION FOR OPERATION 3.3.8 At least one turbine overspeed protection systes shall be OPERA 8LE.

~

APPLICA8ILITY: OPERATIONAL CONDITIONS 1 and 2. ,

ACTION:

a. With one turbine control valve or one turbine stop valve per high pressure turbine steam lead inoperable and/or with one turbine intercept valve or one Wrbine intermediate stop valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to OPERA 8LE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 houra.
b. With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

I[pb

  • Ib b Ut kib. _
  • _ l, SURVEILU NCC REQUIREMENTS .

4 4.3.8.1 The provisions of Specification 4.0.4 are not applicable.

4.3.8.2 The above required turbine overspeed protection systes shall be densonstrated OPERA 8LE: .

a. At least once per 7 days by cycling each of the following valves through at least one complete cycle from the running position: l
1) Four high pressure turbine stop valves,
2) Four low pressure turbine intermediate stop valves,
3) Four high pressure turbine control valves, and
4) Four low pressure turbine intercept valves,
b. At least once per 18 months by performance of a CHANNEL CALIBRATION of the turbine overspeed protection system. .
c. At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of all valve seats, disks and stems and verifying no unacceptable flaws or excessive corrosion. If unacceptable flaws or excessive corrosion .

are found, all other valves of that type shall be inspected. .

t .

l RIVER BEND - UNIT 1 3/4 3 106

1 l

I C .

l

, TABLE 3.3.9-1 (Continued) l C. . '

ACTION 150 - a. With one channel inoperable, place the i erable channel in the tripped condition # within one hou or declare the ll associated system inoperable,

b. With more than one channel inoperable, declare the associated system inoperthle.

ACTION 151 - a. With the number of OPEkA8LE cbsnnels one less than required

. by the Minimum OPERA 8LE Channels requirement, restore the inoperable channel to OPERABLE status within 7 dtyr or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

. b. 'With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

~

ACTION 152 - Declare the associated Containment Ventilation. System inoperable.

ACTION 153 - a. With the number of OPERABLE channels one less than required

  • by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days,or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the number of OPERABLE channels two less than required by the Minimum OPERA 8LE Channels requirement, restore at least onc of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

I

  1. Provided this does not actuate the system.

1 1

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4 0

RIVER BEND - UNIT 1 3/,4.3-109

e a .

REACTOR COOLANT SYSTEM 3/4.'4.7 MAIN STEAM LINE ISOLATION VALVES /

l LIMITING CONDITION FOR OPERATION __

3.4.7 Two main steam line isolation valves (MSIVs) per main steam line siis11 be OPERABLE with closing times greater than or equal to 3 seconds and less thre or

  • equal to 5 seconds. ,

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. l ACTION:

WithoneormoreMSIVsinoperable:p l

/ Mitia n a n at least one MSIV OPERABLE in each affected main steam line _that is_ open and, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, eitier: ,

- ~ ,

estore the inoperable' valve (s) to CPERABLE status, or Jrf U. solate the affected main steam line by use of a deacti- l vated MSIV in the closed position. l Otherwise, be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> M i

- and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -

SURVEILLANCE REOUIREMENTS 4.4.7 At least once per 18 months, each of the above reautred k'SlVs shall be demonstrated OPERAB!.E by terifying full closure between 3 and 5 seconcs when tested pursuant to Specification 4.0.5. i 4

e G

RIVER BEND - UNIT 1 3/4 4-26

\ . .

REACTOR COOLANT SYSTEM 3/4,4.8 STRUCTURAL INTEGRITY LIMITING CON 0! TION FOR OPERATION 3.4.8 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICASILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5.

ACTION:

a. With the structural integrity of any ASME Code Class I component not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component prior to increasing % Reactor Coolant System temperature more than 50*F above the minimum temperature required by NOT considerations,
b. With the structural integrity of any ASME Code Class 2 component not conforC ng to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component prior to increasing the Reactor C'oolant Systent temperature above 200'F. ,

l

c. With the. structural integrity of any ASME Cgde Class 3 component not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.

EY SURVEILLANCE REQUIREMENTS 4.4.8 No requirements othe- than Specification 4.0.5.

l S

RIVER BEND - UNIT 1 3/4 4-27

. l CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCXS 1

I LIMITING CONDITION FOR OPERATION l

3. 6.1. 4 Each primary containment air lock shall be OPERABLE with: -

l I

a. Both doors closed, axcept at least one air lock door shall be closed '

when the air lock is being used for normal transit entry and exit - i through the containment, and  !

b. An overall air lock leakage rate in compliance with the limits of l Specification 3.6.1.3.d when pressurized to Pa, 7.6 psig, and
c. The inflatable seal system air flask pressure > 90 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 28, 3, and f.

3 ACTION:

a. With one primary containment air lock door in one or both air locks inoperable:

1.. Maintain at least the OPERABLE air lock door' closed and either restore the inoperable air

  • 1.ock door to OPERA 8LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed except* as provided in a.3.

.N

2. With an air lock door in only one air lock inoperable, operation may then continue unt performance of the next required overall air lock leakage tes ovided that the OPERABLE air lock door I l is verified to be locked closed at least once per 31 days.
3. air lock door in each air lock inoperable, operation With one' continue with entry and exit permitted for up to 7 dayM l may then '

previoed that an OPERABLE air lock door is verified to be locked closed after each entry or exit and an individual is dedicated to assure that two doors in an air lock are not opened simultaneously.

4 Otherwise, in OPERATIONAL CONDITIONS 1, 2, or 3 be in at least i HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5. Otherwise, in Operational Condition #, suspend all operations involving handling of irradiated fuel in the containment, CORE 1 ALTERATIONS, and operations with a potential for draining the is s e_1 ns of Specifica g _3.0.4 are not a l

"See special Test Exception 3.10.1. .

g

  1. When irradiated fuel is being handled in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vesss

. l 1

RIVER BEND - UNIT 1

  • 3/4 6-8 l l

l

3 CONTAIM4ENT SYSTEMS b'h LIMITING CONDITION FOR OPERATION (Continued)

e. With the interlock sechanism inoperable:
1. Maintain at least one OPERA 8LE air lock door closed and either return the interlock to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock one OPERA 8LE air lock door closed.
2. Personnel e'ntry and exit through the air lock is permitted pro-vided one OPERABLE air lock door remains locked at all times and an individual is dedicated to assure that two doors are not open simultaneousl .

5 ;r f:f re e' 5;erf'!:etf _e-_ _11'. t :P f eiM e.

2. -

l

c. With a primary containment air lock inoperable, except as a result of an inoperable air lock door or an inoperable interlock sechanism, maintai, at least one air lock door closed; restore the inoperable air locn to OPERA 8LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or:
1. In OPERATIONAL CONDITIONS 1, 2, or 3, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2. .In Operational Condition 7, suspend all operations involving handling of irradiated fuel in the containment, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel.
d. With one primary containment air lock door inflatable seal system air flask prossure instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 7 days or verify, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, air flask pressures to be > 90 psig. ,

SURVEILLANCE RE0VIREMENTS 4.6.1.4 Each primary containannt air lock shall be demonstrated OPERABLE:

a. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ** following each closing, except at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ** whea the air lock is being used for multiple entries, by verifying seal leakage rate is in compliance with the limits in Specification 3.6.1.3.d when the gap between the door seals is pressurized to Pa, 7.6 psig.
b. By conducting an overall air lock leakage test at Pa, 7.6 psig, ano verifying that the overall air lock leakage rate is within its limit:
1. At least once per 6 months,"a When irradiated fuel is being handled in the primary containment and during CORE K 2 RATIONS and operations with a potential for draining the reactor vessel.

"*The provisio'ns of Specification 4.0.2 are not applicable.

RIVER BEND - UNIT 1 . 3/4 6-9

_ - - - _ . _ . . - . , , . _ _ _ - _ . _ . _ . _ . _ _ _ _ . . _ . . _ . - - _ - , , _ . _ .__ -.___._.__.__,______._-m._,.,.- _ _ _ .

1 CONTAINMENT SYSTEMS .

DRWELL AIR LOCKS

. LIN! TING CONDITION FOR OPERATION 3.6.2.3 The drywell air lock shall be OPERA 8LE with: l 1

a. Both doors closed except that, when the air lock is being used for normal  ;

transit entry end exit through the drywe11, at least one air lock door shaS1 be closed, and b .' An overall air lock leakage rate of less thr.n or equal to 11.85 scf per hour at 3.0 p*1d, and i

~

c. The inflatable seal system air flask pressure 1 75 psig.

APPLICA81t!TY: CPERATIONAL CONDITIONS 1, 28, and 3. j ACTION: , ,

I

a. With one drywell air lock door inoperableff, . ,

. n at least the CPERA8LE air lock door closed and either

[ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERA 8LE air lock door closed.restors Operation may the inoperabl '

then continue provided that the OPERA 8LE air lock door is verified 5

to be locked closed at least once per 31 days. Otherwise, be in at

  • i least HOT SHUT 00W within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SMITDOWN thin t 11owi 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. f __

-L  ?? _^ ( Nf*' H"** "_? * '

b. With the drywell air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the .

inoperable air lock to CPERA8LE' status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least j HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHVTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

.c. With one inoperable drywell air lock door inflatable seal systee air flask pressure instroentation channel, restore the inoperable channel to OPERABLE status within 7 days or verify air flask pressure to be 175 psig at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

  • see special Test Exception 3.10.1. ,

RIVER SEND - UKIT 1 3/4 6-20

I Qi.S J Ttz, g J O HototR I h CONTAINMENT SYSTEMS AUG 21 1987 3/4.6.4 PRIMARY CONTAINMENT AND DRWELL ISOLATION VALVES LIMITING CONDITION FOR OPERATION

/* a'" $'~ [

%g'3.6. -#

3.6.4 The primary ,ontainment and drywell isolation valves in T n shall be OPERA 8LE with isolation times less than or equal to those shown Table 3.6.4-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one or more of the primary containment or drywell isclation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either:

a. Restore the inoperable valve (s) to OPERABLE status, or  ;
b. Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated positiog
  • or c l
c. Isolate each affected pang,tra ion by use of at least one cTased manual valve or blind flangs" ("lNSERT" a w. . ~4,4.-, . .., n,.+4.. 2 n e ; c . i , G M ,.,,u q

~

. G.'.E;'H i.;. D Z : ..Si:Z i. 7 . b L ', V_~.7'_ax__ _. m w m u w'"' .'. ';' !il',I " '.L ' 2 '..'l I ' 3"* L " . ' !C ' '".; " .'" ' ; "' " " U" _'_ U "" u .

i. Si,i; ;L'i;; ;;;wf;'.;"iw'"!' !";.i;;;'ii'u!!!!' .;;,'5;;'!';.

g,, nz a --- -.-: ..r.K. . . _ D. - - . ' ~ ' " ' ' _~ ~ ~ ' " _ ' ' - ' - ~ ' ' ' ~ ~ ~ ~ - -

Otherwise, be in at least HOT SHUT 00VN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in

  • COLD SHUTOOWN within the M11owing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.4.1 Each isolation valve shown in Table 3.6.4-1 shall be demonstrated OPERABLE prior to returning the valve to service, after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit, by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

4.6.4.2 Each automatic isolation valve shown in Table 3.6.4-1 shall be demon-strated OPERA 8LE during COLD SHUTDOWh or REFUELING at least once per 18 month ,

by verifying that, on an isolation test signal, each automatic isolation valve actuates to its isolation position.

  • Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative controls.
  1. The specified 18 month interval during the first operating cycle may be sxtended to coincide with completion of the first refueling outage scheduled '

to begin 9-15 87 for those items noted on Table 3.6.4-1.

3/4 6-31 RECElVED Amendment No. 9 RIVER BEND - UNIT 1 AUG 191987 snc

"lNSERT" for page 3/4 6-31

_ _e +-

~

and declare the associated system inoperable, if applicable, and perform the associated ACTION statements for that system, _- _

_ _ _ - v -_ _~_ - - - _ _ ~ -

'I

'. 'j l

[' tsNurg,,\

woi.oca ,, 9 CONTAINMENT SYSTEMS A% M GU I SECONDARY .CONTAI MENT AUTOMATIC ISOLATION DAMPER $ '%. ...- ... . . ~ . . .

. ,,.., eb )

LINITING CONDITION FOR OPERATION  %

m ~ .

J ,

m -

3.6.5.3 The secondary containment ventilation systee automatic isolation  !

dampers shown in Table 3.6.5.3-1 shall be OPERABLE with isolation times less

! than or equal to the times shown in Table 3.6.5.3-1.

APPLICA8ILITY: As shown in Table 3.6.5.s-1.

l

.A,gTJ,g:T i

tfith one or more of the secondary containment ventilation system automatic  ;

Isolation dampers shown in Table 3.6.5.3-1 incperable, saintain at least one isolation damper OPERA 8LE in each affected penetration that is open and, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either:

a. Restore the inoperable damper (s) t3 OPERA 8LE itatur, or

, b. Isolate each affected penetration by use of at least one deactivated l automatic damper secured in the isolation posittor g l )

. c. Isolata each affected penatration by use of at least one closed sanual I

  • i valve or blind flang Q g g __

i f

Tka minau l a l an a af $ nas= I d I r at_4 mm__ 'l fh 1 m.. ,m me il m pia ==^*j j-j g g d_ _ _

-the t"teted ; --tratien it iceut-d 'r :::: u*- rent: d**'l---'*- ^.CTI^^' ^' b . :: : .

et" , e-d --au ' ded + k =

  • t %.v e ~ ' a+ -d t m r:d 'nerere' ^.CR ^" :t:t:: nt; n r t.tt .

set th: 2;;r:;rk'

. . . . ,. m l

.,m.._.

Othemise, in OPERATIOML CONDITION 1, 2 or 3, be in at least HOT SHUTDOW within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD 3HUTDOW within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Othemise, in Operational Condition N, suspano handling of irradiated fuel in the Fuel Building. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS _ _.

4.3.5.3, Each secondary containment ves.tilation systes automatic isolation l damper shown in Table 3.6.5.3-1 shall be demonstrated 0PERABLE:

a. Prior to returning the damper to service after saintenance, repair or i replacement worA is perforced on the damper er its associated 6ctuator. -

l control or power circuit, by cycling the damper through at least one complete cycle of full travel and verifying the specified isolation i time.

'fWhen i irradiated fuel is being handled in the Fuel 8uilding.

RIVER BEND - UNIT 1 3/4 6-51

I

, l "lNSERT" for page 3/4 6-51 l and declare the associated system inoperable, if applicabis, and perform the associated ACTION statements for that system, l

d

, PLANT SYSTEMS .

~

SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7,6.2 The following spray and sprinkler systems shall be OPERA 8LE:

SYSTEM LOCATION ELEVATION IDENTITY

a. Control Bldg. Cable Chases 116'0" AS-6A 98'0" AS-68 70'0" 45-6C, WS-6A, WS-68, WS-6C 115'0" WS-7A, WS-78
b. Cable Tunnels 67'6"/70'0" WS-80, WS-8E, WS-8F, 67'6"/70'0" WS-8G, WS 8H, WS-8K, 67'6"/70'0" WS-8L, WS-8M, WS-8N
c. Auxiliary B1dg., RCIC 70'0" PS-1, WS-19 i Pump Room ,

141'0" WS-4A, WS-48, WS-20, AS'12

d. Diesel Generator B1dg. 98'0" PS-2A, PS-28, PS-2C
e. Fuel Bldg. 95'0" AS-5 148'0" WS-5A, WS APPLICABILITY: Whenever equipment protected by the spray or sprinkler systems is required to be OPERA 8LE.

ACTION:

a. With one or more of the above required spray cr sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol,
b. The provisions of Specification 3.0.3 re not applicable.

G S

RIVER BEND - UNIT 1 3/4 7-21

  • i l

1 l

l PLANT SYSTEMS l I

. HALON SYSTEMS LIMITING CONDITION FOR OPERATION l

3.7.6.3 The following main control room Power Generation Control Complex (PGCC)

Halan systems shall be OPERA 8LE with the storage tanks having at least 95% of full charge weight and 90% of full charge pressure: ,

PGCC Panel Module U701 PGCC Panel Module U730 PGCC Panel Module U702 PGCC Panel Module U731 PGCC Panel Module U703 PGCC Panel Module U732 PGCC Panel Module U704 PGCC Panel Module U740 PGCC Panel Module U71U PGCC Panel Module U741 PGCC Panel Module U711 PGCC Panel Module U742 PGCC Panel Module U712 PGCC Panel Module U743 PGCC Panel Module U715 PGCC Panel Module U744 PGCC Panel Module U714 PGCC Panel Module U745 PGCC Panel Module U715 PGCC Panel Module U146 PGCC Panel Module U717 PGCC Panel Module U747 PGCC Panel Module U720 ~PGCC Panel Module U748 PGCC Panel Module U721 PGCC Panel Module U799 PGCC Panel Module U723 .PGCC Panel Module U750 APPLICABILITY: Whenever ecuipment protected by the Halon systems is required "

to be OP,ERABLE.

. ACTION:

a. With one or more of the above required Halon systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fira suppression equipment for those areas in which redundant systems or components could be damaged; for other areas establish an hourly fire watch patrol.
b. TheprovisionsofSpecificatiof3.0.3 are not applicable.

l l

SURVEILLANCE REQUIRENENTS 4.7.6.3 The above required Halon system shall be demonstra'sd OPERABLE

a. At least once per 31 days by verifying that each Halon system storage i tank is pressurized to at least 280 psig. '

1

b. At least once per 6 months by verifying Halon storage tank weight and pressure. l

.'~ .

l RIVER BEND - UNIT 1 3/4 7423

l l

l l

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.6.4 The fire hose stations shown in Table 3.7.6.4-1 shall be OPERABLE.

APPLICA8ILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERA 8LE. .

ACTION:

l

a. With one or wre of the fire hose stations shown in Table 3.7.6.4-1 inoperable, provide gated wye (s) on the nearest OPERA 8LE hose station (s). One outlet of the wye shall be connected to the standard length of hose provided for the hose station. The second <

outlet of the wye shall be. connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station. Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to operating technicians, plant equipment, or the hose itself, the fire hose shall be stored in a roll at the outlet of the OPERABLE hose station. Signs

.shall be mounted above the gated wye (s) to identify the proper hose to use. The above ACTION shall be accomplished within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire hose 1.s the primary means of fire suppression; other-wise route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. TheprovisionsofSpecificatio[3.0.'3 are not applicable. l

$URVEILLANCE REQUIREMENTS 4.7.6.4 Each of the fire hnse stations shown in Table 3.7.6.4-1 shall be demonstrated CPERABLE:

a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operation to assure a.11 required equipment is at the station, l i
b. At least once per 18 months by:
1. Visual inspection of the fire hose stations not accessible during plant operation to assure all required equipment is at the station,
2. Removing the hose for inspection and re-racking, and
3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.

RIVER BEND - UNIT 1 3/4 7-25

PLANT SYSTEMS c

P g

YARD FIRE HYDRANTS AND HYORANT H0SE HOUSES LIMITING CONDITION FOR OPERATION j 3.7.6.6 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7.6.5-1 shall be OPERABLE.

1 APPLICABILITY: Whenever equipment in the areas protected by the yard fire -

{

hydrants is required to be OPERABLE. -

ACTION:

a. With one or more of the yard fire hydrante or associated hydrant hose houses shown in Table 3.7.6.5-1 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> have i sufficient additional lengths of 2 1/2 inch diameter hose located in an adjacent OPERA 8LE hydrant hose house to provide service to l the unprotected area (s) if the inoperable fire hydrant or associated hydrant hose house is the primary seens of fire suppression; otherwise provide the additional home within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. The provisions of Specificatiof 3.0.3 are not applicable. l SURVEILLANCE REQUIRENENTS 4.7.6.5 Each of the yard fire hydrants and associated hydrant hose houses shewn ,io Table 3.7.6.5-1 shall be demonstrated OPERABLE:.
a. At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house.

D. At least once per 6 months, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.

c. At least once per 12 months by:
1. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire sain operating pressure, whichever is greater.
2. Replacement of all degraded gaskets in couplings.
3. Performing a flow check of each hydrant.

d 4

RIVER 8END - UNIT 1 3/4 7-28

  • PLANT SYSTEMS g ,

3/4.7.7 FIRE-RATED ASSEMBLIES -

l LIMITING CONDITION FOR OPERATION l l

3.7.7 All fire barrier assemblies shall be OPERABLE. Fire barrier assemblies l include: l

a. Walls, floors / ceilings, cable tray enclosures, and other fire barriers that separate safety-related fire areas or that separata portions of redundant systems, important to safe shutdown, within a fire area, and
b. All sealing devices in fire-rated assembly penetrations, including fire doors and fire dampers and cable, piping and ventilation duet )

penetration seals, and ventilation seals.

APPLICABILITY: At all times. ,

ACTION:

a. With one or more of the above required fire-rated assemblies or sealing devices inoperable, within I hour establish a continuous  ;

fire watch on at least one side of the affected assembly and/or ,

sealing device or verify the OPERABILITY of fire detectors on at i least one side of the inoperable assembly or sealing device, and l establish an hourly fire watch patrol. *

b. The provisions of Specificatiof 3.0.3 are not applicable. )

l SURVEILLANCE REQUIREMENTS 4.7.7.1 Each of the above required fire-rated assemblies and penetration sealing devices shall be verified OPERABLE at least once per 18 months by

  • performing a visual inspection of:
a. The exposed surfaces of each fire-rated assembly.
b. Each fire damper and associated hardware,
c. At least 10 percent of each type of sealed penetration. If changes in appearance or abnormal degradations are found, a visus) inspection of an additional 10 parcent of each type of sealed penetration shall be made. This inspection process shall continue until a 10 percent sample is found with no apparent changes in appearance or abnormal I degradation. Samples shall be gelected such that each penetration l seal will be inspected at least once per 15 years. l i

1 1

i RIVER BEND - UNIT 1 3/4 7-30 4

--- - - - - - - -, .,- - - - . , . _ . . - _ - _ . . .- - - - . - , , - - . . - - , --,-..-.-i

,, PLANT SYSTEMS i

3/4.7.10 STRUCTURAt. SETTLEMENT LIMITING CONDITION FOR OPERATION 3.7.10 Structural settlement shall be within'the predicted values as shown in Table 3.7.10-1 and calculated differential settlements shall be within the allowable ranges shown in Table 3.7.10-2 for the following structures: .

a. Reactor Building
b. Auxiliary Building
c. Fuel Building
d. Control Building
e. Diesel Generator Building
f. Standby Cooling Tower, Basin and Pump House
g. BF Tunnel
h. Main Steam Tunnel
1. E Tunnel
j. G Tunnel APPLICABILITY: At all times.

.. ACTION: ,

With the measured structual settlement of any of the above required structures outside of the limits of Tabits 3.7.10-1 and 3.7.10-2, prepare and. submit, within the next'30 days, a Special Report to the Commission, pursuant to Specification 6.9.2, providing a record of the settlement sensurements and the predicted settlement, an analysis to demonstrate the continued structural integrity of the affected structure (s), and plans to monitor the settlement of the affected structure (s) in the future. The provisions of Specification 3.0.3 are not applicable to the limits established in Table 3.7.10-1. l

$URVEILLANCE REQUIREMENTS w 4.7.10 The structural settlement of the above required structures shall be demonstrated to be within the limits of Tables 3.7.10-1 and 3.7.10-2:

a. At least once per 92 days, until there is essentially no movement during those 92 days.
b. At least once per 24 months, for at least 10 years,
c. Following any seismic event equal to or greater than an Operational Bisis Earthquake (CBE).

RIVER BEND - UNIT 1 3/4 7-35

ELECTRICAL POWER SYSTEMS -

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES PRIMARY CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CON 0! TION FOR OPERATION l 3.8.4.1 All primary containment penetration conductor overcurrent protective ~

devices shown in Table 3.8.4.1-1 shall be OPERA 8LE.

APPLICABILITY: OPERATIONAL CONDITIO"51, 2, and 3.

ACTION:

With one or more of the primary containment penetration conductor overcurrent l t protective devices shown in Table 3.8.4.1-1 inoperable, declare the affected system or component inoperable and apply the appropriate ACTION statement for the affected system and: j For 4.16 kV circuit breakers, de-energize the 4.16 kV circuit (s) by l l tripping the associated redundant circuit breaker (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verifying, at least ones.per 7 days thereaf ter, the redundant circuit breaker to be tripped, or 480 volt circuit breakers, remove the inoperable circuit breaker (s) l from service by racking out the breaker 'within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verifying, at least once per'7 days thereafter, the inoperable breaker (s) to be racked out.

or 480 volt MCC circuit breaker / fuse combination starters, remove the inoperable starter (s) from service by locking the breakers open l and removing the control power fuse within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verifying, at least once per 7 days thereafter, the inoperable starter (s) cir-  ;

cult breaker to be locked open with the control power fuse removed. '

~

h er 120/140 volt solded case circuit breakers, remove the inoparable l circuit breakar(s) from service by tripping both 120/140 volt breakers open and locking the upstream 440 volt MCC breaker open within  !

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verifying, at least once per 7 days thereafter, the {

440 volt MCC breaker (s) to be locked open.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00VN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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RIVER BEND - UNIT 1 3/4 8-25

, ELECTRICAL POWER SYSTEMS OTHER OVERCURRENT PROTECTIVE DEVICES 6!MITING CONDITION FOR OPERATION 3.8.4.2 The overcurrent protection devices shown in Table 3.8.4.2-1 shall be OPERA 8LE.

APPLICA8ILITY: At all times. ,

ACTION:

With one or more of the overcurrent protective devices shown in Table 3.8.4.2-1 i inoperable, remove the circuit breaker (s) feeding the control room lighting and/or alternate RPS supply as appropriate from service by opening the breaker (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and raturn the overcurrent protection devices to OPERABLE status wttbin 7 da s f he anoronr<3te bgomanalleast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*

h41s: 34.E?@ spw I, SURVE!LLANCE REQUIREMENTS 4.8.4.2 The overcurrent protective devices shall be demonstrated OPERABLE at least once per 18 months by selecting and testing one+ half of each type of .

, circuit breaker en a rotating basis. Testing of these circuit breakers shall l consist of injecting currents in excess of the breaker's nominal *setpoint and measuring the response time of the long time and short time delay elements and the setpoint of the instantaneous element, as appropriate. The measured data shall be compared to the manufacturer's data to ensure that it is less than or equal to a value specified by the manufacturer.

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"Except at least once per 31 days if locked, seeled, or otherwise secured in the open position.

1 RIVER SEND - UNIT 1 3/4 8 33

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RADI0 ACTIVE EFFLUENTS .

00$E '

LIMITING CONDITION FOR OPERAfl0N l

3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC froe radio- l active materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited: .

a. During any calendar quartar to less than or equal to 1.5 artes to the total body and to less than or equal to 5 areas to any organ, and
b. During any calendar year to less than or equal to 3 areas to the 1 total body and to less than or equal to 10 areas tc any organ.

APPLICA8!LITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents, exceeding any of the above limits, prepare and

. submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that identifies the cause(s) for exceedir thi limit (s) and defines the corrective, actions that ha'ev been taken \

to reduce the releases and the proposed corrective actions to be

  • taken to assure that subsequent releases will be in compliance with the above limits,
b. The provisions of Specificatiof 3.0.3 are not applicable.

$URVEILLANCE RE0UIREMENTS ,

4.11.1.2 Cumulative dose contributions from liquid effluents"for the current .

calendar quarter and the current calendar year shall be determined, at least  !

once por 31 days, in accordance with the methodology and parameters in the CDCM. 1 i

RIVER BEND - UN!? 1 3/4 11-4

o RADICACTIVE EFFLUENTS LIQUID RADWASTE TREATNENT SYSTEM LIMITING CON 0! TION FOR OPERATION 3.11.1.3 The liquid radwaste treatment systen shall be used to reduce the radioactive natarials in liquid wastes prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS (see Figure 5.1.3-1) would e.xceed 0.06 area to the total body or 0.2 mrom to any

  • organ in a 31 day period. .

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within J0 days, pursuant to Specification 6.9.2, a Special Report that includes the following informatton:
1. Explanation of why liquid raewaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
2. Action (s) taken to restore the inoperable equipment to 0PERA8LE

- - status, and

3. Summary description of ac. tion (s) taken to prevent a recurrence.
b. The provisions of Specificattojf 3.0.3{}f [f j 3)are 'not applicable. l ,

SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses due to liquid releases to UNRESTp!CTED AREAS shall be projected '

at least once per 31 days in accordance with the methocology and parameters in l the 00CM.

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RIVER BEND - UNIT 1 3/4 11-5

__ __ - - . _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ ______________1._______. ___ __

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j RADICACTT (FFLUENTS DOSE - N08tf GASES LIMITING CONDITIOh FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous affluents to areas at and beyond the SITE 800NOARY (see Figures 5.1.1-1 and 5.1.J-1) shall be limited to the following: .

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,
b. During any calendar year: Less. than or equal to 10 mrads for gamma radiation and less than or equal to 20 mracs for beta radiation. .

APPLICABILITY: At all times. i ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the
  • . limit (s).and defines the corrective actions that have been taken to reduce the , releases and the proposed corrective actions to be taken '

to assure that subsequent releas,es,will be in compliance with the above limits. ,  :

b. ,The' provisions of Specificatio 3.0.3 are not applicable. l

$URVEILLANCE REQUIREMENTS

\

i 4.11.2.2 At least once per 31 days, cumulative dose contributions for the cur-  ;

I rent calendar quarter and current calendar year for noble gases shall be ceter-eined in accordance with the methodology and parameters in the 00CM.-

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RIVER BEND - UNIT 1 3/4 11-11 9

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t RADICACTIVE EFFLUENTS .

DOSE - 100!NE-131.100!NE-133. TRITIUM AND RADIONUCLIOES IN PARTICULATE FO ,

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from todine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous ef fluents released to areas at and beyond the SITE SOUNOARY (see Figures 5.1.1-1 and 5.1.3-1), shall be limited to the fol)owing:

a. During any calendar quarter: Less than or equal to 7.5 areas to any organ and,
b. During any calendar year: Less than or equal to 15 areas to any organ. ,.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release, in gaseous affluents, of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days, exceeding ar.y of the above

- . limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a special Report that identifies the cause(s) jgg

- 'for exceeding the limit and defines the corrective actions that have ,

been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will ba'in compliance , -

with the above limits.

b. TheprovisionsofSpecification3.0.3/53~)[l[5)arenotapplicable. l SURVEILLANCE REQUIREMENTS l

4.11.2.3 At least once per 31 days, cumulative dose contributions for the cur- l rent calendar quarter and current calendar year for todine-131, iodine-133, 1

  • ritium, and radionuclides in particulate form with half lives greater than 8 days, shall be determined in accordance with the methodology and parameters in the 00CM.

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I RIVER BEND - UNIT 1 3/4 11-12

. . s

t RADI0 ACTIVE EFFLUENTS ,

t GASEOUS RADWASTE TREATMENT LIMITING CON 0! TION TOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATF.4NT (0FFGAS) SYSTEM shall be in operation.

APPLICA8!LITY: Whenever the sain condenser air ejector system is in operation.

ACTION:

a. With GASEOUS RADWASTE TREATMENT (0FFGAS) SYSTEM inoperable for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
1. Identification of the inoperable equipment or subsystems and  ;

the reason for inoperability,

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2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.' Summary description of action (s) taken to prevent recurrence. ,
b. TheprovisionsofSpecificatiof3.0. a.re not applicable.

SURVEILLANCE REQUIREMENTS l t 4.11.2.4 The instruments specified in the 00CM shall be checked every l j

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, whenever the main condenser air ejector is in operation, to ensure i that the GASE0US oADWASTE TREATMENT (OFFGAS) SYSTEM is functioning.

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i RIVER BEND - UNIT 1 3/4 11-13

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RADICACTIVR EFFLUENTS . .

VENTILATION EXHAUST TREATMENT LIMITING CON 0! TION FOR OPERATION 3.11.2.5. The VENTILATION. EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Figures 5.1.1-1 and 5.1.3-1), would exceed 0.3 aram to any organ in a 31 day period.

APPLICA8!LITY: At all times other than when the VENTILATION EXHAUST TREATMENT system is undergoing routine asintenance. , j ACTION:

a. With gaseous waste being discharged from the ventilation exhaust ducts without treatment and in excess of the above limits, prepare and submit to the Consission within 30 days, pursuant to Specir1ca- I tion 6.9.2, a Special Report that includes the following informatien* '

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1. Explanation of why gaseous radwaste was being discharged without i treatment, identification of any inoperable equipment or sub- '

systems, and th'e reason for the inoperability, . . dII ]

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2. Action (s) taken to restore the in6perable equipment to OPERABLE i status, and i
3. Susaary description of action (s) taken to prevent a recurrence. )
b. The provisions of Specificatief 3.0.3 are not applicable. l

$URVEILLANCE REQUIREMENTS 4.11.2.5 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM.

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RIVER BEND - UNIT 1 3/4 11-14

Q

  • RADI0 ACTIVE r"~LUENTS .

3/4.11.3 SOLIO RADI0 ACTIVE WASTE LIMTTING CONOTTION FOR OPERATION 3.11.3 The solid radwaste systes shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requireteents. .

APPt,!CAOILITY: At all times.

ACTION:

a. With the previsions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site,
b. The provisions of Specificatio 3.0.3r; ? f.0. " are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.3 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one rtpresentative test specimen from at least every tenth batch- ,

of each type of wet radioactive waste (e.g. , filter sludges, spent. resins, i evaporator bottoms, sodium sul. fate solutions),

a. If 'any test specimen f ails to verify SOLIDIFICATION .the SOLIDIFICA-TION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CCNTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICA-J TION of the batch may then be resumed using the alternative SOLIDIFI- l

' CATION parameters determined by the PROCESS CONTROL PROGRAM. l

b. If the initial test specimen frca a batch of, waste fails to verify SOLIDIFILATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet wasta until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as required, as provided I in Specification 6.13, to assurs SOLIDIFICATION of subsequent batches of waste.

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1 RIVER BEND - UNIT 1 3/4 11-17

I RADI0 ACTIVE EFFLUENTS ,

3/4.11.4 TOTAL DOSE l

LIMITING CON 0! TION FOR OPERATION l

3.11.4 The annual (calendar yea.') dose or dose consitment to any MEM6ER OF 1 THE PU'lLIC, due to releases of radioactivity and to radiation'from uranius fuel cycle sources, shall be limited to less than or equal to 25 areas to the total body or any organ, except the thyroid, which shall be liatted to less than or equal to 75 areas. .

APPLICA8ILITY: At all times.

ACTION:

3. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.11.1.2.a. 3.11.1.2.b. 3.11.2.2.a. 3.11.2.2.b 3.11.2.3.a. or 3.11.2.3.b, calculations should be made, including direct radiation contributions from the reactor units and from outside storage tanks, to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the cor,rective action to be taken to reduce subsequent releasestopreventrecurrenceofexceedingttyeabovelimitsandthat.S includes the schedule for achieving conformance with the above limits This Special Report; as defined in 10 CFR Part 20.405c, shall include <

an analysis that estimates the radiation exposure (dose) to a MEMBER 0F THE PUBLIC from uranica fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the rolesse(s) covered by this report. It shall also describe levels i

of radiation and concentrations of radioactive material involved, j and the cause of the exposure levels or concentrations. If the estimated dese(s) exceeds the above limits and, if the release condi-tien resulting in violation of 40 CFR Part 190 has not already been i

corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of i the report is considered a timely request, ano a variance is granteo until staff action on the request,is complete, j

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b. The provisions of Spect fica!1of 3.0.3 are not applicable. l SURVEILLANCE REQUIRENENTS 2

4.11.4.1 Cumulative dose contributions from liquid and gaseous offluents shall l be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3 l and in accordance with the methodology and parameters in the 00CM.

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4. 11.4. 2 Cumulative dose contributions from direct radiation from the reactor unit and from any unprotected outdoor storage tanks shall be determined in accordance with the methodology and parameters in the 00CM. This requirement s i is applicable only under conditions set forth in Specification 3.11.4, Action a, RIVER BEND - UNIT 1 3/4 11-18 I

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RADIOLOGICAL ENVIRONMENTAL MONITORING .

LIMITING CON 0! TION FOR OPERATION (Continued) ,

ACTION: (Continued) specific locations from which samples wre unavailabTe say then be deleted from the monitoring program. Pursuant to Specification 6.9.1.8,

. identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semi-annual Radioactive Effluent Release Report and include in the report '

a revised figure (s) and table for the 00CM reflecting the new location (s),

d. The provisions of Specificatto 3.0.3 are not applicable. l

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SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figure (s) in the 00CM, and sha)1 be analyzed pursuant to the requirements of .

Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

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1 RIVER BEND - UNIT 1 3/4 12-2 o y ~

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i RADIOLOGICAL ENVIR0

  • ENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal, 8the nearest residence and the nearest garden" of greater than 50,a (500 ft ) producing broad leaf vegetation. .

App (!CA811,ITY: *At all times, ,

ACTION: .

I a. With a larid use census identifying a location (s) that yields a calculated being calculated dose orindose commitment Specification greateridentify 4.11.2.3, than thethe values new currently location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b. With land use census identifytr.g a location (s) that yields a calculated

- dose or dose commitment (via the same exposure pathway) 20 percent i.

greater than at a location from which samples are currently being i.

obtained in accordance with Spec.ification 3.12.1, add the new loca-tion (s) to the radiological environmental sonitoring pro ~ gram within 30 days 'The sampling location (s), excluding the control station location.,having the lowest calculated dose or dose ' commitment (s).

l via the same exposure pathway, may tie deleted from this monitoring 1 program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.8, identify the new location (s) in the next Semiannual Radioactive Effluent Release j

Report and include in the report a revised figure (s) and table

> for the 00CM reflecting the new location (s),

c. The provisions of Specificatic 3.0.3F Q 'are not applicable. l j SURVEILLANCE REQUIREMENTS 4.12.2 At least once per 12 months, the land use census shall be conducted during the growing season, using that information that will provide the best i

! results, such as by a door-to-door survey or aerial survey or by consulting local agriculture authorities. The results of the land use census shall be l included in the Annual Radiological Environmental Operating. Report pursuant to j Specification 6.9.1.7. .

j of the garden census, broad leaf vegetation sampling of at least three "In differen kinds of vegetation say be performed at the site boundary in each of Iteu Y.

two different direction sectors with the highest predicted D/Qs, Specifications i for broad leaf vegetation sampling in Table 3.12.1-1, 4c shall be followed, including analysis of' control samples.

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! RIVER BEM - UNIT 1 3/4 12-13 I -

! o RAD!t.0GICAL ENVIRONMENTAL MONITORING ,

d 3/4.12.3 INTERLA80RATORY COMPARISON PROGRAM ,,

LIMITING CON 0! TION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials, that correspond to samples required by Table 3.12.1-1, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission. .

APPLICA81LITY: At all times.

ACTION:

a. With analyses not being performed as required above, report to the Commission, in the Annual Radiological Environmental Operating Report pursuaat to Specification 6.9.1.7, the corrective actions taken to prevent a recurrence.
b. TheprovisionsofSpecificatiof3.0.3 are not applicable. l

. SURVIILLANCE REQUIREMENTS

.m 4.12.3 the Interlaboratory Comparison Program shall be described in the 00CM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be .inciude'd in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

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RIVER EEND - UNIT 1 3/4 12-14 9 9 09 ' I E g.g $g

,-y . - - _ _ . . - - . _ _ . - . - . . - --m.- -.

. 'o ENCLOSURE 2 Changes to River Bend Station Technical Specification Bases for Applicability of limiting Conditions for Operations and Surveir.ance Requuirements t

Specifi-cation No. Title Revised Page Bases 3.0.1 Applicability B 3/4 0-1 Bases 3.0.2 Applicability B 3/4 0-1 l Bases 3.0.3 Applicability B 3/4 0-1 Bases 3.0.4 Applicability B 3/4 0-1 Bases 4.0.1 Applicability B 3/4 0-2 t Bases 4.0.2 Applicability B 3/4 0-2 Bases 4.0.2 Applicability B 3/4 0-2 Bases 4.0.3 Applicability B 3/4 0-2

! Bases 4.0.4 Applicability B 3/4 0-2 i Bases 4.0.5 Applicability B 3/4 0-3 I

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3/4.0 APPLICABILITY BASES

(^nsWt - D The specifications of this section provice the general requirements app able to each of the Limiting Conditions for Operation and Surveill e Requi ents within Section 3/4. -

3.0.1 This specification states the applicability of each sp fication in terms of fined OPERATIONAL CONDITION or other specified app ability condition and provided te delineate specifically when each cification is applicable.

3.0.2 This spe fication defines those conditions cessary to constitute compliance with the te s of an individual Limiting Co tion for Operation and associated ACTION re irement. ,

3.0.3 This specificatio delineates the me ures to be taken for those circumstarices not directly prov ed for in the TION statements and whose occurrence would violate the inte of the s cification. For, example, Specifi-cation 3.7.2 requires two main cont I roo air conditioning subsystems to be <

OPERABLE and provides explic'it ACTION e irements if one subsystem is inoperable.

Under the requirements of Specificatio .0.3, if both of.the required subsystems are inoperable, measures must be int ate within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in at least STARTUP within the next 6 ours, i t least HOT SHUT 00WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SH OWN within o subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0.4 This specificati provides that ent nto an OPERATIONAL CON 0! TION must be made with (a) the 11 complement of require systems, equipment or components OPERA 3LE and ) all other parameters, as s cified in the Limiting Conditions for Operati , being met without regard for a owable deviations anc cut-of-service provi ons contained in the ACTION statemen ,

The intent this provision is to ensure that tnit opera on is not initiated wit ither required equipment or systea: inoperable o other limits being excee ,

Ex tions to this provision have been provided for a limited nume of l speci cations when startup with inoperable equipment would not affect p t saf . These exceptions are stated in the ACTION statements of the appro-p ate specifications. l i

1 RIVER BEND - UNIT 1 8.3/4 0-1

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4 APPLICABILITY '

BASES i

4.0.1 This specification provides that surv6111ance activities, necessa to sure the Limiting Conditions for Operation are met, will be performed l durin the OPERATIONAL CONDITIONS or other conditions for which the Limiti j Conditi s for Operation are applicable. Provisions for additional surv lance activitie to be parfurmed without regard to the applicable OPERATIO CONDI-TIONS or o r conditions, are provided in the individual Surve111anc Require-sents. Surv 11ance Requirements for Special Test Exceptions need 1y be performed when he Special Test Exception is being utilized as an xception to an individual sp ification.

4.0.2 The pro fons of this specification provide all able tolerances for performing survei ance activities beyond those specif d in the nominal surveillance interval, hese tolerances are necessary t provide operational flexibility because of se duling and performance consi rations. Tha phrase "at least" associated with surveillance frequency d s not negate this allowable tolerance; instead, it permits the more f quent performance of surveillance activities.

The tolerance values, taken a her indivi ally or consecutively over three test intervals, are.sufficiently res ictive o ensure that the reliability associated with the surveillance activ ty not significantly degraded beyond II that obtained from the nominal speciffe nterval. '

4.D.3 The provisions of this sp ific ion set forth the criteria for determination of compliance with.th OPERABIL TY requirements of the Limiting Conditions for Operation. Under ese criteri equipment, systems or components are assumed to be OPERABLE if t associated sur 111ance activities have been satisfactorily performed withi the specified time nterval. Nothing in this provision is to be construed s defining equipment, stems or components OPERABLE, when such items e found or known to be in4 erable although still meeting the Surveillance equirements.

4.0.4 This spec ication ensures that survatilance ac vities associated with a Limiting Con tion for Operation have been performed thin the specifies time interval pri to entry into an applicable OPERATIONAL CO IT;0N or other specified appli 111ty condition. The intent of this provision s to ensure that surveill ce activities have been satisfactorily demonstrate n a current basis as re red to meet the OPERABILITY requirements of the Limit Condition for Operat n. i U er the terms of this specification, for example, during initial p nt l star or following extended plant outage, the applicable surveillance acJv-iti eust be performed within the stated surveillance intarval prior to pla ng o returning the system or equipment into OPERABLE status.

RIVER BEND - UNIT 1 8 3/4 0-2 9 #

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APPLICA8!!.ITY 8ASES

.0.5 This specification ensures that inservice inspection of ASME C Class 2 and 3 components and inservice testing of ASME Code Class 1, and 3 pumps an alves will be performed in accordance with a periodically dated version of tion XI of the ASME Boiler and Pressure Vessel Code Addenda, as required by CFR 50, Section 50.55a. Relief from any of above require-ments has been p ided in writing by the Comission and is n a part of these 1 Technical Specifica ns.

This specification ludes a clarification of frequencies of perform-ing the inservice inspectio nd testing activitie required by Section XI of cable Addenda. This clarifi-the ASME Boiler and Pressure el Code and ap cation is provided to ensure cons tency in veillance intervals throughout these Technical Specifications and remo any ambiguities relative to the  ;

frequencies for performing the require service inspection and testing activ-ities.

Under the terms of this sp fication, th ore restrictive requirements oftheTechnicalSpecificati take precedence o e the ASME Boiler and Pressure Vessel Code and applicabl ddenda. For exa.mple, t requirements of Specifi-

. cation 4.0.4, to perfor surveillance activities prior entry into an OPERATIONAL CONDITION or other s cified applicability condition, tak precedence over the ASME Boiler and P sure Vessel Code provision which allows 'mps to be tested up to one week ter return to nomal operation. And, for exa e, the Technical Specificatio definition of OPERABLE does not grant a grace perio before a device th is not capable of performing its specified function is lared

.e. and takes prece'dence over the ASME Boiler and Pressure Ves inoper code prov ton which allows a valve to be incapable of performing its specifie func-n for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable, a

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RIVER BEND - UNIT 1 B 3/4 0-3

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INSERT D l

Specifications 3.0.1 through 3.0.4 establish the general reouirements l applicable to Limiting Conditions for Operation. These requirements are based

, on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10CFR50.36(c)(2): ,

"Limiting conditions for operation are the lowest functional capability or i performance levels of equipment required for safe operation of the facility. ,

When a limiting condition for operation of a nuclear reactor is not met, the e licenste shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

]

l Specification 3.0.1 establishes the Applicability statement within each I individual specification as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the ,

, facility. The ACTION requirements establish those remedial measures that must l

be taken within specified time limits when the requirements of a Limiting  !

Condition for Operation are not met. It is not intended that the shutdown i ACTION requirements be used as an operational convenience which permits i (routine) voluntary removal of a system (s) or component (s) from service in  !

lieu of other alternatives that would not result in redundant systems or ,

components being inoperable. l

. t There are two basic types of ACTION requirements. The first specifies the remedial measures 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 l safety for unlimited continued operation as long as the ACTION requirements

~

4 continue to be met. The second type of ACTION requirement specifies a time I i

limit in which conformance to the conditions of the Limiting Condition for  !

Operation must be met. This time limit is the allowable outage time to i I

restore an inoperable system or component to OPERABLE status or for restoring I

. parameters within specified limits. If these actions are not completed within I

the allowable outage time limits, a shutdown is required to place the facility l in an OPERATIONAL CONDITION or other specified condition in which the '

specification no longer applies, i

The specified time limits of the ACTION requirements are applicable from the 1

point ' t time it is identified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a

, system or component is removed from service for surveillance testing or

investigation of operational problems. Individual specifications may include j a specified time limit for the completion of a Surveillance Requirement when

, equipment is removed from service. In this case, the allowable outage time J limits of the ACTION requirements are applicable when this limit expires if

{ the surveillance has not been complete 6 When a shutdown is required to

! comply with ACTION requirements, the plant m, uve entered an OPERATIONAL i CONDITION in which a new specification becon. plicable. In this case, the i time limits of the ACTION requirements would app./ from the point in time that l the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

I Page 1 of 6

Saecification 3.0.2 establishes that noncompliance with a specification exists w1en the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown CONCITION 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 permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces themal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a limiting Condition for Opera tion. The re fore , the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER OPERATION. If the plant is in d lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies.

However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable tine to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced. For example, if STARTUP is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed that would permit a return to POWER OPERATION, a penalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

Page 2 of 6

The same nrinciple applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL CONDITION or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable outage time tha t is applicable when a Limiting Condition for Operation is not met in a lower CONDITION of operation.

The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications def f ne the remedial measures to be taken.

Specification 3.0.4 establishes limitations on a change in OPERATIONAL CCNDIT:0NS when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher CONDITION 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 teh ACTION requirements if a change in CONDITIONS were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher CONDITIONS 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 spectiled 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 after a change in OPERATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL ,

CONDITION or other specified condition may be made provided the ACTION requirements are being complied with exclusive of the allowable outage time limits. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in rettoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower CONDITION of operation.

Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10CFR50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components 1 I

is maintained, that facility operation will be withir. safety limits, and that )

the limiting conditions of operation will be me+ " '

Specification 4.0.1 establishes the requirement that surveillances must be l pe rfo rved during the OPERATIONAL CONDIT!0h or other conditions for which the i

requirerents of the Limiting Conditio".s for Operation apply unless otherwise j stated in an individual Surveillance Requirement. The purpose of this Page 3 of 6 l

l l

specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended. Item a. permitt an al?owable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not 60 suitable for conducting the surveillance; e.g., transient conditiont or other ongoing surveillance or maintenance activities. Item b.

limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the i

recognition that the most probable result of any particular surveillance being performed is the verification of confonnance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Specification 4.0.3 establishes the failure to perform a Surveillance I Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure tu meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, syscems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance 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 exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

The failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, constitutes a failure to reet the OPERABILITY requirements for a Limiting Condition for ,

Operation and any reports required by 10 CFR 50.73 shall be detennined based I on the length of time the surveillance interval has been exceeded, and the corresponding Limiting Conditions for Operation ACTION time requirements, as discussed in HUREG 1022. Supplement 1.

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

Page 4 of 6 l l

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, ,e .

Specification 3.0.3., a 24-hour allowance is provided to pennit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to penni t the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for i completing Surveillance Requirements that are applicable when an exception to '

the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24-hour alluwance, the time limits of the ACTION i requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the  !

surveillance is terminated.

! Surveillance Requirements do not have to be performed on inoperable equipment l l

because the ACTION requirements define the remedial measures that apply, t

, However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

d Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other [

J condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system .ind component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components  !

ensure safe operation of the facility. This provision applies to changes in  ;

OPERATIONAL CONDITIONS or other specified corditions associated with plant  !

shutdowi, as well as startup.

l Under the provisions of this specification, the applicable Surveillance I l

Requirements must be performed within the specified surveillance interval to I

assume that the Limiting Conditions for Operation are met during initial plant i

, startup or following a plant cutage. '

l When a shutdown is required to comply with ACTION requirements, the provisions

! of Specification 4.0.4 do not apply because this would delay placing the i

facility in a lower CONDITION of operation.

I Specification 4.0.5 establishes the requirement that inservice inspection of l ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code I Class 1, 2, and 3 pumps and valves shall be perfonned in accordance with a periodically updated version of Section XI of the ASME Boiler and Pre',sure Vessel Code and Addenda as required by 10C/R50.55a. These requirements spply

except when relief has been provided in writing by the Comission.

l This specification includes a clarification of the frequencies for perfonning the inservice inspection and testing activities required by Section XI of the l ASME Boiler and Pressure Vessel Code and applicable Addenda. This 1

Page 5 of 6

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I I

clarification is provided to ensure consistency in surveillance intervals i throughout the Technical Specifications and to remove any ambiguities relative l to the frequencies for perfoming the required inservice inspection and '

testing activities.

Under the tems of this specification, the more restrictive requirements of l the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 .

to perfom surveillance activities before entry into an OPERATIONAL CONDITION '

or other specified condition takes precedence over the ASVE Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to one week after return to nortnal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable i and takes precedence over the ASME Boilee and Pressure Vessel Code provision  !

that allows a valve to be incapable of performing its specified function for  !

up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable. '

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f l

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