ML20043F986
ML20043F986 | |
Person / Time | |
---|---|
Site: | River Bend |
Issue date: | 06/06/1990 |
From: | GULF STATES UTILITIES CO. |
To: | |
Shared Package | |
ML20043F981 | List: |
References | |
NUDOCS 9006180386 | |
Download: ML20043F986 (52) | |
Text
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c DCmstRE 1 F1W River Bend Station Todnical Specification manges for Applicahility of Limiting conditions for Operations and Surveillance Haguirunents Specification No. Title Revised Pace 3.0.4 Applicability 3/4 0-1 4.0.3 Qplicability 3/4 0-2 4.0.4 Applicabil.ty 3/4 0-2 3.1.3.1 Control Rod Operability 3/4 1-4 3.1.3.2 Control Rod Maximum Insertion Times 3/4 1-7 3.1.3.3 Control Rod Scram Accumulators 3/4 1-10 3.1.3.4 Control Rod Drive Coupling 3/4 1-11 3/4 1-12 3.1.3.5 Control Rod Position Indication 3/4 1-13 3.3.- Reactor Protection System Instrumentation 3/4 3-1 3.3.2 Isolation Actuation Instmmentation 3/4 3-10 Table 3.3.6-1 Control Rod Block Instrumntation 3/4 3-61 3.3.7.1 Radiation Monitoring Instrumentation 3/4 3-65 1 Table 3.3.7.1-1 Radiation Monitoring Instrumentation 3/4 3-68 !
3.3.7.2 Seismic Monitoring Instrunentation 3/4 3-70 l 3.3.7.3 Meteorological Monitoring Instrumentation 3/4 3-73 3.3.7.0 Fire Detection Instrumentation 3/4 3-87 3.3.7.9 Icose Part Detection Systcm 3/4 3-93 3.3.7.10 Radioactive Liquid Effluent Monitoring L Instrumentation 3/4 3-94 3.3.7.11 Radioactive Gaseous Effluent hbnitoring Instrumentation 3/4 3-99 Table 3.3.9-1 Plant Systems Actuation Instrumentation 3/4 3-109 ,
3.4.7 Main Steam Line Isolation valves 3/4 4-26 3.4.0 Structural Integrity 3/4 4-27 3.4.9.2 Cold Shutdown 3/4 4-29 3.5.3 Suppression Pool 3/4 5-9 3.6.1.4 Primary Containment Air Iocks 3/4 6-8 3/4 6-9 3.6.2.3 Drywell Air Incks 3/4 6-20 3.6.4 Primary Containment and Drywell Isolation Valves 3/4 6-31 3.6.5.3 Secondary containment Autcmatic I Isolation Dampers 3/4 6-51 l 3.7.6.2 Spray and/or Sprinkler Systems 3/4 7-21 3.7.6.3 Halon Systcms 3/4 7-23 3.7.6.4 Fire Hose Stations 3/4 7-25 3.7.6.5 Yard Fire Hydrants and Ilydrant Hose Houses 3/4 7-28 3.7.7 rire Rated Assemblies 3/4 7-30 Page 1 of 2 61gh hk[$ B P
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Title,- 1 Revised Page-
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3.7.10. '
Strtetural Settlenent -
3/4 7-35.- ,;-
3.8.4;1 Primary Contairstent Penetration Conductor i Overcurrent Protective Devices . -3/4~8-25 ;
3.8.4.2- other overcurrent Protection Devices 3/4 8-33 l 3.9.11.2 Iow Water IcVel 3/4 9-18: !
3.11.1.2 Dose- 3/4'11 ;
- 3.11.1.3. Liquid Radwaste Treat 2nent System. 3/4 11 :
' 3.11.2.2 Dose-Noble Gases .
.. 3/4 11-11 .
- 3.11.2.3- . Dose-Iodine-131, Iodine-133, Trititan, and _
Radionuclides in Particulate Form 3/4 11-12 '
3.11.2.4 Gaseous Radwaste Treatment 3/4'11-13-' .
3.11.2.5: Ventilation Dchaust Treatanent' 3/4 11-14:. 1 3.11.3- Solid Radioactive Waste 3/4 11 1 1 3.11,4: . ' Ibtal Dose ' , 3/4 11-18 ;i 4' - 3.12.1 Radiological Environmental Monitoring. 3/4 12-2: 1
. 3.12.2' land Use Census- .
. 3/4'12 0 3.12.3 Interlaboratory Ccznparison Program 3/4 12-14 9
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a 3/4.0 AP't! cat!LITY- l
' LIMITING CONDITION FOR OPERATION L
i 3.0.1 Compliance with the Lietting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Lietting Conditions for Operation, the associated ACTION requirements shall be set.
3.0.2
' Moncompliance with a Specification shall exist when the requirements of ~
the Limiting Condition for Operation and associated ACTION requirements are not est within the specified time intervals. If the Lietting Condition for Operation is restored prior to expiration of the specified time intervals, I
complation of the ACTION requirements is not required.
1 3.0.3 When a Limiting Condition for Operation is not met, except es.provided in the associated ACTION requirements, action shall be initiated within i hout to place the unit in an CPERATIONAL CON 0! TION in which 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 least MT SHUTD0WN 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 SNUTOOWN within the subseque,nt 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as esasured 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 CON 0!TIONS 4 or 5.
t l
3.0.4 Entry into an OPERATIONAL CON 0! TION or other specified condition shall nsert A not be Sa3M C u n th: OZIituZ U 04 Li;'tiTi CZditIZ 5 0?ietin eie n t d th a t re u x , m prn u u n ; n ni n : e ra tO I = 7.wi x = ;. This provision shall not prevent passage through or to OPERATIONAL CON 0!TIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications.
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when the conditions for the Limiting Condition for Operation are not met and the associated specified ACTION requires a shutdown if they are not met within a time interval.
Entry into en OPERATIONAL CON 0tTION or other specified condition may be made in accordance with the ' ACTION reqdroments when conf ormance to time.
of them permits Continued operation of the facility for an unlimited period i
l RIVER REND - UNIT 1 3/4 0 1
- l Appl!CABILITY 4
!i SURVE!LLANCE REQUIREMENT 5 1
i
- 4. 0.1 Surveillance Rewirements shall be ses during the OPERATIONAL CONDIT!CN$ j
- or other conditions specified for individual Lietting Conditions for Operation l
unless otherwise stated in an individual Surveillance Requirement, i 4.0.2 Each Surveillance Requirement shall be perfereed within the specified 1
stee interval with:
- a. A annimum allowable extension not to saceed 255 of the surveillanct l interval, but
- b. The combined time interval for any 3 consecutive suneillance intervals ,
' shall not exceed 3,25 times the specified surveillance Internt-- l Mifsert B]
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Jahce riiq@ resents do not have te we
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!- performed en Tn6perab' e equ' peiint.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated Condition for Operation have been performed within tha -
with the Limiting applicable surve 11ance interval or as othemise specified. e
/
l 4.0.5 Surveiilance Requirements for insarvice inspection and testing of ASME l
CodeClass1,2,&3componentsshallbeapplicableasfoIlows: .
l !
Inservice inspection of ASME Code Class 1, 2, and 3 components and a.
inservice testing of ASME Code Class 1, 2, and 3 pumps and valves l shall be performed in accordance with Section XI of the ASME toiler ,
and Pressure Vessel Code and applicable Addenda as required by 10 I CFR 50, Section 50.lle(g), except where specific written relief hs: !
been granted by the Consission pursuant to 10 CFR 50, Section 50.55a(g)
(6) (1).
i
- b. Surveillance intervals specified in Section XI of the ASME toller and Pressure Vessel Code and applicable Addenda for the inservice f inspection and testing activities required by the ASME Boiler and
=c Preaavre Vessel Code and applicable Addenda shc11 be applicable as
'"8 * '" " "
insert -
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l allowed surveillance interval, defined by Specification 4.0.2. shall constitute l- non-compliance with the OPERABILITY requirements for_a Limiting Condition for Operation.
l The time limits of the ACTION requirements are applicable at the time it is identified i that a SURVEILLANCE REQUIREMENT has not been performed. The ACTION requirements may I bo delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the lloweble_ 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 />.
[This In~ serf C < -
I = ' L i [ ( N Y P K = X E- A N^
provision shall not prevent passage through or to OPERATIONAL CONDITIONS as
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i RECrivro REACTIv!TY CONTROL $Y$TEMS 1 SEP 0 S 1988 LIMITING COSIT!0N FOR OPERATION (Continued) IOC gTjg (Continued)
Otherwise, insert the inoperable withdrawn control red (s) and disate the assectated directional control valves
- either:
a) Electrically, or b) Hydraulically by closing the drive unter and exhaust water isolation valves.
- 2. If the inoperable control red (s) is inserted wi I disaretheassociateddirectionalcentrolvalves*thinonehour either: I a) Electrically, or b) Hydraulically by closing the drive water and exhaust water 1 isolation valves. ;
_ Otherwise, be in at least MOT $MUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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With more than 8 conteel rods inoperable, be in at least HDT SWTDOWN
- DEsD -
l within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- d. With one scram discharge volume vent valve and/or one scran discharge volme drain valve inoperable and open, restore the inoperable valve (s) to OPERABLE 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 MOT $MUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- e. With two scras discharge volume vent valves and/or two scram discharge volume drain valves inoperable and open, restore one valve in the vent line and one valve in the drain line to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and restore all valves to OPERABLE status within the next 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> or close at least one ' vent valve and one drain valve and be in at least MOT litlTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- f. With any scram discharge volme vent valve (s) and/or any scras ,
discharge vol es drain valve (s) inoperable and closed ascept when J required by ACTION statement e. above restore all valves to OPERABLEetetuswithin8hoursorbeInatleastWT.$ NUT 90WNwithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SGGILL=* ~ ~ 'Insumers-4.1.3.1.1 The stres discharge volme drain and vent valves shall be demonstrated OPERABLE ty: -
- a. At least once per 31 days verifying each valve to be open,** and ,
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under s eintstrative control, to permit
'9ter be rearned testing associated with rester intermittently,ing the control red te OPERABLE status. i
- These valves may be closed intermittently for testing under administrative i controls. !
RIVtt BEW - UNIT 1 3/4 1-4 Asentent No. 26 l
4' ttACTIv!TY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) g: (Cetinued)
- 4. No " slow" control rod, " fast" control rod with individual scram insertion ties in excess of the limits of ACTION a.2, or other-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 MOT $HUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. With a " slow" control red (s) not satisfying ACTION 4.1, above:
L 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.
Otherwise, be in at least HOT $HUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c. With the maximum scram insertion time of one or more control rods exceeding the maximum scram insertion time limits of Specifica-tion 3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue provided that:
- 1. " Slow" control rods,'i.e. , those whien exceed the limits of Specification 3.1.3.2, do not sake up avers than 205 of the.105 sample of control rods tested..
- 2. Each of these " slow" control rods satisfies the limits of ACTION a.1,
- 3. The eight adjacent control rods surrounding each " slow" control rod are:
a) Demonstrated through measurement within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to satisfy the maximum screa insartion time limits of Specifica-tion 3.1.3.2, and i
b)
- 4. The total number of " slow" control rods, as determined by Speci-l fication 4.1.3.2.c. when added to the sum of ACTION a.3, as
! determined by Specification 4.1.3.2.a and D, ooes not exceed 5.
. Otherwise, be in at least HOT SHLTTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
e= nn :: == =
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1 RI ER BEND - UNIT 1 3/4 1-7
- t s REAeT!vffY CONTRDL SYSTEMS 1=
CSNTRDL M SCRAM W P_U T045 LIMITIM COWITION FOR OPERATION i
M: (Continued) a) Electrically, or b)
Myeraulically by closing the drive water and exhaust water isolation valves.
- 2. i i
With more than one withdrawn cotitrel red with the associated stres accumulator inoperable 'a'N1 with no control red drive pump operating, Shutdown position, tamediately place tne reacter mode switch in the he provisions of Specificattor) 3.0.4 are not applicable.
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$URVEILLANCE REQUIREMENTS 4.1.3.3 Each control rod scram accumulator shall be determined OPERA 8LE:
s.
At least once per 7 days by verifying that the indicated pressura is greater than or equal to 1520 psig unless the control red is inserted and disamed or scrammed.
- b. At least once per 18 months by:
- 1. Performance of a:
a) CHANNEL. FUNCTIONAL TEST of the leak detectors, and Q
CHANNEL CALIBRATION of tho pressure detectors, and verif an alam setpoint of 11520 psig on decreasing pressure.ying 2.
Measuring and recording the time for up to 10 minutes that each individual accumulator check valve maintains the associated escumulater pressure above the alare set point with no conteel red drive pump operating.
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RIVER BEND - UNIT 1 3/4 1*10
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REACT!v!TY CDNTROL $YSTEMS l CONTROL RE_DRM COUPUNG l i LINITING CONDITION FOR OPERATION l
3.1.3.4 All control rods shall be coupled to their drive mechanisms.
APPLICA81LITY: OPERATIONAL CONDITIONS 1, 2 and 5".
ACTION:
- a. In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its associated drive mechanise, 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 RPC5, insert the control rod drive sechanism to cecomplish recoupling and verify recoupling by withdrawing the .
control rod, and:
a) Observing any indicated response of the nuclear instrumenta-
- tion, and I b) Demonstrating that the control rod will not go to the I avartrava13 onition. __
) ll c) The_ provisions e+ Specification 3.0.4 are no* eJolicable l
- 2. P_rocFupung*Ts not'accompHshed on the first. attempt or, IT not .
permitted by the RPC3, then until permitted by the RPC5, declare the control rod inoperable, insert the control rod and disarm the !
associated directional control valves ** either: I e) Electrically, or i b) Hydraulically by closing the drive water and exhaust water I isclation val.ves.
1 Otherwise, be in at least NOT $NUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
- b. In OPERATIONAL CON 0! TION 5" with a withdrawn control rod not coupiec.*
to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:-
- 1. Insert the control rod to accomplea recoup 11ng and verify recoupling by withdrawing the control rod and demonstrg,ing that the control rod will not go to the overtravel positionTor g l
l- "At least each withdrawn control rod Not applicable to control rods removed .
j- per Specification 3.9.10.1 or 3.9.10.2.
- May be reamed intermittently, under administrative control, to pemit testi associated with restoring the control rod to OPERA 8LE status..
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l RIVER BEND - UNIT 1 3/4 1-11 l
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REACTIVITY CONTROL SYSTDIS CONTRO M CDUPUNG i I
LIMITING C00SITION FOR OPERATION ACTION: (Continued)
- 2. If recoupling is not accomplished, insert the control rod and disere the associated directional control valves
- either: -
a) Electrically, or l
b) Hydraulicall by closing the drive water and exhaust water !
isolation va ves.
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$URVEILLANCE REQUIREMENTS 4.1'. 3. 4 Each affected control rod shall be demonstrated to be coupled to its
. drive mechanism by observing any indicated response of the nuclear instrune.n- ]
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: j l
- a. Prior to reactor criticality after completing CORE ALTERATION 5 that s could have affected the control rod drive coup)ing 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 'l control rod drive system which could have affected the control rod drive coupling integrity.
My be rearsed intermittently, under adeintstrative control, to permit testing associated with restoring the control rod to OPERABLE status.
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RIVER BENO - UNIT 1 3/a 1-12 l- .
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4 REACTIVITY CONTROL SYSTEMS CONTROL R00 POSITION INDICR ION LIMITING CONDITION FOR OPERATION 3.1.3.5 The control rod position indication system shall be OPEr.A8LE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 58 ACTION: *
- a. In OPERATIONAL CONDITION 1 or 2 with one er more control rod position indicators inoperable, within one hour: ,
- 1. Determine the position of the control rod by an alternate control rod position indicator, or '
- 2. Move the control rod to a position with an OPERA 8LE position indicator, or
- 3. When THERMAL POWER is:
l a) Within 'the low power setpoint of the RPCS:
- 1) Declare the control rod inoperable, and
( .,
- 2) Verify the position and bypassing of. control rods with inoperable " Full-in" and/or " Full-out" position indicators by a second licensed operator or other technically qualified members of the unit technical staff.
b) Greater than the low power setpoint of the RPCS,-declare the control rod inoperable, insert the control rod and disarm the associated directional control valves ** either: ,
- 1) Electrically, or
- 2) Hydraulically by closing the drive w W and exhaust water isolation valves.
Otherwise, be in at least NOT SHUTDOWN 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 CONDITION $* with no position indicators of a with-drawn control rod OPERA 8LE, move the control rod to a position with *
.n.; . m,,. . .an DPERABLE, position ., indicator.or, insert the. control arod..,. .. -,
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"At least each withdrawn control rod. Not applicable to control rods removed
~. per Specification 3.9.10.1 or 3.9.10.2.
d **Mey be rearmed intermittently, under administrative conthl, to permit testing asweisted with restoring the control rod to CPERA8LE status.
I RIVER BEND - UNIT 1 3/4 1-13
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- c, L . 3/4.3 INSTRLMENTATION
- AUC 7 1987 3/4.3.1 REACTOR PROTECTION $Y$ TEM INSTRLMENTATION
%e a......
LIMITING C0 e ! TION FOR OPERATION k
...... Y. w 3.3.1 As a sinimum the reactor orotection systes instrument 4tMMs j
shown in Table 3.3.I-1 shall be OPERABLE'with the REACTOR PROTECTIO RESPONSE TIE as, shown in Table 3.3.12.
l APPLICABILITY: As shown in Table 3.3.1-1, 1
kWE:
- s. With t % number of OPERABLE channels less than required by the Mint-eum OPl'RABLE Channels place the inoperable e per Trip)_$ystes sanne1(s requirement andler_thattr for onethe_t n_ systaa_in trip s stem, d candtitan* wd t.hin one hour. ( -'^^l-";=:7: ~"' Y' ::=:556 P. .
L b.
C_15^M@$9 -
' With the number of OPERABLE channels less than retvired by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, I l place at least one trip systes** in the tripped
- condition witsin one i sour and take the. ACTION required by Table 3.3.1-1.
)
$URVEILLANCE REQUIREMENT $
1 4.3.1.1 Each reactor protection system instrumentation channel shall be demon- l strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL ,
TEST and CHANNEL CALIBRATION operations for the OPERATIONAL C02 1 TION $ and at '
the frequencies shown in Table 4.3.1.1-1. ..
l 4.3.1.2 LOGIC $YSTEM FUNCTIONAL TEST $ and staulated automatic o all channels shall be performed at least once per 18 months.*** peration of i
4.3.1.3 The REACTOR PROTECTION SYSTEM Resp 0NSE TIE of each reactor trip 4 functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per la months. Each test shall include at least one channel per tri:p system such that all channels are tested at least once every N times
- 18 montss where N is the total number of redundant channels in a specific reactor
! trip systee. ..
"An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored ta OPERABLE 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 ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.
' +
- The triin systes need not be placed in the tripped condition if tht'swould cause tse Trip Function to occur. men a trip systes can be placed in the Function to occur lace the trip tripped condition system with the mostwithout causing inoperable channelsthe Trikn the tripped condIt on; if both systems have the same number of inoperable channels, place either trip systes ,
in the tripped condition. The requirement to place a trip systes in the tripped condition does not apply to Fuactional Units 6 and 10 of Table 3.3.1-1.
- *** Logic $ sten Functional Test period say be extended as identified by note 'p' on Tabl 4.3.1.1-1. '
. RECEIVED, RIVER BEND - UNIT 1 3/4 3-1 AUG 6 1987 Amend nt No. :
__.______._..___.._..__.m,,.m,.;. 7 IMS NTATION 3/d. 3. 2 180LATION ACTUATION INSTRUMENTATIM LIMITING C021T10N FOR OPERATION
- 3. 3. 2 ^
i The isoletten actuetten instrumentation channels shown in Table 3 shall be OPERABLE with their trip setpoints set consistent with the values shown fa the Trip setpoint column of Table 3.3.2 2 and with !$0LAT10N SYSTEM RESPONSE T18E as shown in Table 3.3.2-3.
Appt1CABILITY: As shown in Table 3.3.t-1.
El.S a.
W1th an iseletion ettuatien iastementatfen channel trip setpoint less of conservative Table thanthe 3.3.t-2 declare thechannel value inoperable shown inuntilthe the Allowablechannel Values co is restored to OftnABLE status with its trip setpefnt adjusted consistent with the Trip setpoint value.
- b. '
With the number of OPERABLE channels less than required by the Minfaus OPERABLE Channels per Trip System requirement for one ,
place
- the inograble channelfa) madar that Ma ava*= in *trip s s,tes E
f h**'* T = $ $ 5 ? $ $ $ 5 $ 5 L = ~ pod
- c. With the number of OPERABLE channels less than required the Nintaus j OPERA 8LE Channels per Trip Systes requireesnt for both te p systems, place at least one tefp systes** fa the tetpped condition within one l
hour and take the ACTION required by Table 3.3.2-1.
l l
l 1 i l j
- *An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel Table 3.3.2-1 for that Trip Function shall be taken.shall be restored l i
amThe the Trip tefpFunction systes need not be placed in the telpped conditten if this would cause to occur.
conditten without caustne the Trip Function to occurWhen a tete systes can be 1
-the most inoperable channele la tW telpped condition,; place if both systems the trip system have the with l l
same number of inoperable channels, place either tefp systen in the trfpped conditten. ;
)
RIYtt DEND = U'N IT 1 3/4 3-10
1 1
TABLE 3.3.5-1 (Continued)
\ . .. v E!ER0LR00llLOCKINSTRUMENTATION l
ACTION 60 - Declare the RpCS inoparable and take the ACTION required by Specification 3.1.4.2.
I ACTION 61 -
With the number of OPERABLE Channels: .
- a. One less than req 6tred by the Minine OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days er place the inoper channel in the tripped condition within the next hou
- b. Two er. acre less than required by the Minimum CPERABLE Channels per Trip Function requirement, place at'least one inopgable channel in the tripped condition within onehourg ACTION 62 - With the n eber of C*EP).SLE channels less than required by the
- Minism CPERA8LE Channels par Trip Function requirement, piece the inoperable channel in the, tripped condition within one hou E. .
- With more than one control rod withdrawn. Not applicable to control roos*
removed per Specification 3.5.10.1 or 3.9.10.2.
.. Specification 3.9.2. .
[ l% h I'dhNUNE$1%a.J. U Ue kh (a) This function shall be automatically Dypassed if detector count rate is l 3,100 cps or the IRM channels are on range 3 or higher.
(b) This function shall be automatically bypassed when the associated IRM channels are on range 4 or higher.
(c) This function shall be automatically bypassed when the IRM channels are I
)
on range 3 er higher. ,
(d) This function shall be automatically bypassed when the IRM channels are on range 1. . ,
9 1
a l
l RIVER BEND - UNIT 1 3/4 3-61 i
L
J
-K- . .. l tmTuennon N.;. .* f l 1/4.3.7-- WNITORING INSTtLMENTATION ]
@!ATION %N!T0t!NG INSTEMENTAT!9N ,
LIMITING CONDITION FOR OPERATION ,
l
\
3.3.7.1 The radiation monitoring instrumentation channels shown in Table l 3.3.7.1-1 shaill be OPERA 8LE with their alarm / trip setpoints within the i specified limits. ,
AppLICASILITY: As shown in Table 3.3.7.1-1.
- l M:
- a. Wi'.h a radiation monitoring instrumentation channel alara/ trip satp61nt exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel
- b. With one er more radiati.on monitoring channels inoperable, take the ACTION required,by Table 3.3.7.1-1.
. c. Theprovisionsof$pecificatichi.0.3 re not applicable. l
$URVEILLANC'E REQUIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANN(L
. CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1.
i 1 .
I l
t RIVER BEND - UNIT 1 ,
3/4 3-65 t l
. . _ _.-- ..__ _ .-... --.-. - -- ..-- - .. - - - --.-. - ~
TA8LE 3.3.7.1-1 (Continued)
RADIATION MONITORING INSTR l MENTATION MTIQN l ACTIch ic -
a.. With one of the required monitors inoperable, resgre the in .
operable channel ta OPERABLE status within 7 days 9'or, within l the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,. initiate and esintain operation of the control rose air conditioning systes in the energency mode of operation. ,
- b. With both of the required monitors inoperable, initiate and maintain operation of the control room air conditioning system in the emergency mode of operation within one hour.
ACTION 71 - With the required monitor inoperable, perfore area surveys of the sonitored area with portable sonitoring 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 />.
ACT10N 72 - With the number of channels OPERABLE less than required by the .
Minimum Channels OPERABLE requirement, effluent releases via
.. this pathway say continue for up to 30 days provided Grab sas-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 these samples are g
analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l;
ACTION 73 - With the number of channels OPERA 8LE less than required by the
. Minimum Channels CPERABLE requi meent, release ussy continue 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 /> providedS) l The offgas systes is not bypassed, and a.
- b. At least one post treatment noble gas activity effluent monitor .
is CPEAABLE; .
Otherwise, be in at less Q5."[$itnin12 hours. [q
'O l
I e
,n .-
_ , - ,n , _,
L tc. ggt.re me .,,nc.e2) L L RIVER SEND - UNIT 1 3/4 3-64
4 '
INTEL M NTATION
. 3
$E!$MIC WNITORI4 INSTRLMENTATION "#
LINITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instroentation shown in Table 3.3.7.2-1 shall be OPERA 8LE.
APPLICABILITY: At all times.
M
- a. With one or more of the above required seismic monitoring instrJoents 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 selfunction and the plans for restaring the instrument (s) to OPERABLE status,
- b. The provisions of Specificatio[3.0.3@ A(3are not applicable. - - -
[
48
$URVEILLANCE REQUIREMENTS . . .
4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPEAASLE by the performance of the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in-Table 4.3.7.2-1. .
4.3.7.2.2 Each of the above required seismic monitoring instruments actuatec during a seismic event greater than or equal to 0.01g shall be restored 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 /> and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be retrieved'from actuated instruments and analyzed to determine the segnitude of the vibratory ground motion. Within 10 days, a special Report shall be prepared and submitted to the Commission, pursuant to $pecification 6.9.2, describing the segnitude, frequency spectrue and resultant effect upon unit features important to safety.
e t
l L RIVER SEND - UNIT 1 3/4 3-70 9
~-sw - ~ , - -----------------v -------------J-- --- - - - - - - - - - - - - - - - - - - - - - - - -
- _ . - . . ~ - . _ - _ - . - _ - - _ . - . - - -. . - . - _ - . . .. - --. .- -
l 1
pi{
w . ..
INSTRWENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION
- 3.3.7.3 The esteorological sonitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE. ,
APPLICA8!LITY: At all times.
ACTION:
- a. With one or more meteorological monitorin*g instrumentation channels inoperable for scre than 7 days, prepare and submit within the next ,
10 days a Special Report to the Commission, pursua s to specifica-tion 6.9.2, outlining the cause of the malfunction and the plans for restoring the instrumentation to CPERABLE status.
- b. The provisions of Specificatioh3.0.3h" ware not applicable. l l
. l i
SURVEILLANCE REQUIREMENTS l 4.3.7.3 Each of the above required meteorological sonitoring instrumentation channels shall be demonstrated 0PERA8LE by the perforer.nce of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.
l .
...........mn, ifa g.n
. INSTRtMEWTATION
[ FIREDETECTIONIN$TRUM{NTATION LIMITING CON 0! TION FOR OPERATION
! 3.3.7.8 As a sinious, the fire detection instrumentation for each fire detection zone shown in T ele 3.3.7.8-1 shall be OPERAfLE.
APPLICA8!LITY: Whenever equipment protected by the fire detection instrument is requires to be OPERA 8LE.
AF,Jg!:
- a. but ne more than one-half the total in any fire zone Func-With tion A anyire f detection instruments shown in Table 3.3.7.8-1 inoperable, restore the inoperable Function A instrument (s) to OPERA 8LE status within 14 days or, within the next hour, establish a fire watch patrol r 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 location 4 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 i in any f're zone shown in Table 3.3.7.8-1 inoperable, or with any Functica 8 fire detection instruments shown in Table 3.3.7.8-1 inoperable, or with any two or more adjacent. instruments shown in t
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 /> o'stablish a fire watch patrol to inspect the zone (s) with the'inopera61e instrument (s) at '
least once per hour. If the instrument (s) is located inside the cond 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 containment air temperaturA R 1 east once per hour at toe i
locations listed in Specification 4.Gd i and 4.6.2.6. ,
- c. The provisions of Specificatio.f 3.0.3 f[pM5Mre not apolicable. l
$URVEILLANCE REQUIRENENTs 4.3.7.8.1 fach of the above requ' ired fire detection instruments which are accessible during unit operation shall be demonstrated OPERA 8LE at least once per 5 months by performance of a CHANNEL FUNCT!0NAL TEST. Fire detectors wnica are not accessible during unit operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed 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-sents shall be demonstrated CPERA8LE at least once per 6 months.
s RIVER BEND - UNIT 1 3/4 3-87 i
, , - - . . - , - , -.1,-- . . , n-.m -
e w
p4TRIAIENTATION
- W.
LOC $t-PART DETECTION $YSTEN LIMITING CON 0! TION FOR OPERATION
).
3.3.7.V The loose part detection systas shall be OPERA 8LE.
APPLICA8.' E : OPERATIONAL CONDITIONS 1 and 2. .
M: ,
t
- a. With one er more loose part detection systas channels inverable for more than 30. days, prepare and submit within the next 10 days a Special Report to the Commission, pursuant to Specification 4.9.2, .
outlining the cause of the selfunction and the plans for restoring )
the channel (s) to OPERA 8LE status.
_ _ _ _ 1
- b. The provisions of $pecificatio f 3.0.3 6 j Q are not applicable.
SURVEILLANCE REQUIREMENTS' 4.3.7.9 Each eMannel of the loose part detection systes shall be demonstrated 4
' 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 />,
- b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
- c. CHANNEL CALIBRATION at least once per 18 months.
1 e
i e
RIVER SEND - UNIT 1 3/4 3-93 .
-,-. , .- --a -
e .--- - , - , . - - - , .-,n- em-- .,
4 INSTRUMENTATION
(, , y 4
- .u; . . '. \
RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION '
1 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alare/ trip setpoints ;
set to. ensure that the limita of 5,ecification 3.11.1.1 are not exceeded. The i
alare/ trip setpoints o'f these char Sels shall' be determined and adjusted in {
accordance with the methodology and parameters in the OFF5ITE DOSE CALCULATION MANUAL (00CM).
! APPLICABILITY: At all times.
ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel t
alann/ trip setpoint less conservative than required by the above I Specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel
! inoperable.
I -
- b. With less than the minimum number of radioactive , liquid effluent monitoring instrumentation channels CPERA8LE, take the ACTION sitown
, in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERA 8LE status within the time specified in ACTION or explain in l- the next Sesiannu'al Radioactive Effluent Release Report why this inoperahility was not3erreited withLn the ti_se spetjlied.
(Tiie3rovisions of Joaci t lentic K4 qQ6L TtooTicablel
- c. Th~e provTsfons oT 5pec1Ticatiop3.0.3(g4fjare not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liovid effluent monitoring instrumentation channel snail be demonstested CPERABLE by performance of the CHANNEL CHECK. SOURCE CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operati'ns o at the frequencies shown in Table 4.3.7.10-1.
P$ e
. R RIVER BEND - UNIT 1 3/4 3-94 i
., INSTRUMENTATION ,
C' .
RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION j 3.3.7.u The radioactive gaseous affluent monitoring instrumentation channels j shown in Table 3.3.7.u-1 shall be OPERABLE with their alare/ trip" setpoints set to ensure that the Itaits of Specification 3.u.2.1 are not exceeded. The i alarm / trip setpoints of these channels shall be determined and adjusted in
- i accordance with the methodology and parameters in the 00CM.
APPLICA81LITY: As shown in Table 3.3.7. u-1. i l
ACTION: )
- a. With a radioactive gaseous affluent monitoring instrumentation channel l alare/ trip" setpoint less conservative than required by the above '
$pecification, flunediately suspend the release of radioactive gaseous l effluents monitored by the affected channel, or declare the channel !
inoperable. !
b.' With less than the mini, mum numb'er of radioactive gaseous effluent l conitoring instrumentation channels OPERABLE, take,the ACTION shown in Table 3.3.7.11-1. Restore the inoperable instrumentation to CPERA8LE status within the time specified in the ACTION or explain ,
in the next Sesiannual Radioactive Effluent Release Report why this l (Jnenarabuity wasMt catracted within the _ time ospecified.The arqvtsions et
- c. The pFovisions of rpecifnatlog3.0.3Q.;3.".gare not applicable.
SUREVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by g-erformance of the CHANNEL CHECK, SOURCE CHECK.
CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7. u-1.
"The alars/ trip setpoints for the Explosive Gas Mixture in the Main Condenser l Offgas Treatment System are set in accordance with Specification 3. u.2.6.
1 l
1 l
- j l RIVER BEND - UNIT 1 .
3/4 3-99 l
L i
1 i TABLE 3.3.9-1 (Continued) ,
I .
I
'..., )
ACTION 150 - a. With one channel inoperable, place the taaperable channel in the tripped conditionf within one hou$or declare the l associated systas inoperele.
- b. With more than one channel inoperable, declare the associatec systas inoperable.
ACTION 151
- a. With the neer of OPERABLE channels one less than requind
. by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be
$ in at least MOT 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 />.
- b. 'With the number of OPERABLE channels two less than required by the Minimum CPERA8LE Channels requirement, restore at ,
least one of the inoperable channels to OPERA 8LE status i 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 M0T 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 />.
l ~
ACTION 152 - Declare the associated Containment Ventilation,5ystes .
i.,e ral e.
ACTION 153 - a. With the number of OPERABLE channels one less than eequired
- by the Minisua 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 Minious 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 STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
~~v, _
W= M,.%1=2 i=i=ML = =w= =IO
- Provided this does not actuate the systas.
4
- ^.
G
(
RIVER BEND UNIT 1 3/,4 .3-109
_ __~ _ ._ ._.... ,
. t REACTOR C00LANT SYSTEM 3 /4.'4. 7 MRIN STEAM LINE !$0LATION VALVf5 ,,
LIMITING CON 0! TION FOR OPERATION _ _ _ _
3.4.7 Two main steam line isolation valves (MSIVs) per main steam line shall te OPERABLE with closing times greater than or equal to 3 seconds and less than or 1 equal to 5 seconds.
APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2 and 3. ,
ACTION:
With one or more MSIVs inoperable:j
__v- -
/ yMaint
_ain at least one MSIV OPERA 8LE 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 />, _either-estore the inoperable' valve (s) to OPERABLE status, or
- o. solate the affected main steam line by use of a deacti-vated MSIV in the closed position. ,
Og otherwise, be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> I, 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 />. -
=
- FG% .
L i
i .
l SURVEILLANCE RE0VIREMENTS l
' 4.4.7 At least once per 18 months, each of the above recuired MSIVs sna11 de demonstratec OPERA 8LE by terifying full closure between 3 and 5 secones wnen tested pursuant to Specification 4.0.5. ,
RIVER BEND UNIT 1 3/4 4 26
REACTOR COOLANT $Y$ TEM i
3/4.4.8 STRUCTURAL INTEGRITY LINITING COS ITION FOR OPERATION 3.4.C The structural integrity of ASME Code Class 1, 2 and 3 components sna11
! be maintained in accordance with Specification 4.4.8.
APPLICA8!LITY: OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5.
i ACTION:
- a. With the structural integrity of any ASME Code class 1 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 the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.
- b. With the structural integrity of any ASME Code class 2 component i 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 the Reactor C'oolant System temperature above 200'F.
- c. With the. structural integrity of any ASME Cgde Class 3 component not conforming to the above esquirements, restore the structural integrity of the affected component to within its limit or isolate I -the affected component froe service. - r
! - := _ ~ ;m ; _ c,__,
l
- d. 'h: ; = i:f = cf !;::1'f::tf:n 3.0.t = ::t ::;?f: d :.
\
= __=_~ _
~_
j SURVEILLANCE REQUIREMENTS l
I
( 4.4.8 No requirements other than Specification 4.0.5.
RIVER BEND - UNIT 1 3/4 4-27
REACTOR COOLANT SYSTEN RECEIVED
. COLD SHUTDOWN M 14 S LINITING CON 0! TION FOR OPERATION SDC I
3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation",N with each loop consisting of at least:
- b. Two OPERA 8LE RHR heat exchangers.
APPLICABILITY: OPERATIONAL CONDITION 4.
ACTION:
- a. With less than the above required RHR shutdown coolifeg mode loops OPERA 8LE, within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter demonstrate the operability of at least one alternate method capable ,
of decay heat removal for each inoperable RHR shutdown cooling mode loop.
- b. With no RHR shutdown cooling mode loop or recirculation pump in opera-tion, within one hour establish reactor coolant circulation by an -
alternate method and monitor reactor coolant temperature and pressure at,,11ast once per hour. _
/' c - y- s
/ cr--Thews 4 ens ** Wi'iP i-- * ^
- aat =f=aljcable **-_ g l
' h -A .. .. m a , _ _ .. A A.-
SVRVEILLANCE REQUIRENENTS ' -
l 4.4.9.2 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, at least one shutdown cooling mode loop of the residual heat removal system, one recirculation pump or alternate method shall be determined to be in operaticn and circulating reactor coolant. '
l
- 0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other loop is OPERA 8LE and in operation or at least one recirculation pump is in operation.
- The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided the other loop is OPERABLE.
NThe shutdown cooling mode loop may be removed from operation during hydyostatictestingj
, -- gp_ m l **Tsi; ;bti;3J ;;11:31: =til ; tuts fr.; the,secone-Mfvelir.g outag A f -A- 2--.. + -
RIVER SEND - UNIT 1 3/4 4-29 Amendment No. 36 -
l
_ _ ___.__ ____ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ , _ --,......-h . .~-----,._.,ww- .e...- - -e
m
, EMERGENCY CORE COOLING SYSTEMS ACTION (Continued) i i
- c. With one SPPS subsystem inoperable, restore the SPPS subsystem to I OPERABLE status within 31 days or demonstrate the OPERABILITY of the remaining SPPS subsystem at least once per 31 days by:
- 1. A functional test of the crescent area sump pump, and
- 2. Demonstrating that the associated flow path can be aligned to the suppression pool. _
3.
T h h isien M.+ Q [ g 4 ML li:b
- d. With both SPPS subsystems inoperable, restore one SPPS subsystem to OPERABLE status within 7 days or: I
- 1. In OPERATIONAL CONDITION 1, 2, or 3 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 /> and COLD SHUTDOWN within the following l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j
- 2. In OPERATIONAL CONDITION 4 or 5* provide at least one alternate .
pumpback method and demonstrate the OPERABILITY of an alternate l
method within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, otherwise suspend CORE ALTERATIONS and all '
operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the shutdown position. Establish PRIMARY CONTAINMENT INTEGRITY - FUEL j HANDLING within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. -
i SURVEILLANCE REQUIREMENTS i
- 4. 5. 3.1 The suppression pool shall be determined OPERABLE by verifying the I water level to be greater than or equal to, as applicable:
- a. 19'6", at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, in OPERATIONAL CONDITION 1, 2 and 3. -
- b. 13'3", at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, in OPERATIONAL CONDITION 4 and 5. '
4.5.3.2 With the suppression pool level less than the above limit or drained in OPERATIONAL CONDITION 4 or 58, at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
- a. Verify the required conditions of Specification 3.5.3.b to be satisfied, or "
- b. Verify footnote conditions
- to be satisfied. '
4.5.3.3 At least once per 92 days, the SPPS shall be demonstrated OPERABLE by:
- a. Verifying each crescent area sump pump develops 50 gps, and
- b. Verifying the flow path can be aligned to the suppression pool.
- The suppression pool is not required to be OPERABLE in OPERATIONAL CONDITION 5 provided that the reactor vessel head is removed, the cavity is flooded, the upper containment fuel pool gate is open, and the water level is maintained within the limits of Specifications 3.9.8 and 3.9.9. RECEIVE D '
RIVER BEND - UNIT 1 3/4 5-9 Amendment No.38 ML 191369 c: m. e
-)
i
'W
+ -
4
<.J CC#ffAIWENT SYSTEMS PRIMARY CONTAISIENT AIR LOCKS .
J.!MITINGCONDITIONFOROPERATION 6
3.6.1.4 Each primary containment air lock shall be OPERABLE with: - I 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 -
through the containment, and
- b. An overall air lock leakage rate in compliance with the limits of Specification 3.6.1.3.d when pressurized to Pa, 7.6 psig, and
- c. The inflatable seal systes air flask pressure > 90 psig.
APPLICABILITY: OPERATIONAL CON 0!TIONS 1. 28, 3, and 8.
ACTION:
- a. With one primary containment air lock door in one or both' air locks inoperable:
1.. Maintain at least the OPERA 8LE air lock door closed and either restore the inoperable air' 1pck door to CPERABLE 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 . M,
. provided in a.3.
- 2. With an air lock door in only one air lock inoperable, operation may then continue un performance of the.next required overall
. air lock leakage tes - ovided that the OPERABLE air lock coor I' is verified to be lockee closed at least once per.31 days.
3.
With one, air lock door in each air lock inoperable, operationmay then co previoed that an OPERA 8LE air lock door is verified to be lecked closed after each entry or exit and an individual is dedicatec to assure that two doors in an air lock are not opened simultaneously.
4 Otherwise, in OPERATIONAL CON 0!TIONS 1, 2, or 3 be in at least HDT 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 SHUTDOWN 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 irrediated fuel in the containment, CORE ALTERATIONS, and operations with a potential for draining the
, _ _reac ytoissal. _
&Wl he oravisfoasWa 8 0 4 ar* act **Pli@
- ]
"5ee special-Test Exception 3.10.1. *
. en irradiated fuel is being handled in the primary containment and during -
CORE ALTERATIONS and operations with a octnntial ter draining the reactor vessi RIVER BEND - UNIT 1 3/4 6-8
a: gggf_AMELTEEDS e . ..: . ,
=
4{,$
LIMITIN8 C0e! TION PGA OPERATION (Continued) !
i
- b. - With tho' interlock mechanism inoperable:
- 1. Maintain at least one OPERA 8LE air lock door closed and either l 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 OPERABLE air lock door closed.
- 2. Personnel o'ntry and exit through the air lock is permitted pre-vided one OPERA 8LE air lock door remains locked at all times and ,
an individual is dedicated to assure that two doors are not open
- c. With a primary containment air lock inoperable, except as a result of an inoperable air lock door or an inoperable interlock mechanism, maintain at least ens air lock door closed; restore the ihoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or:
- 1. InOPERATIONALCONDITIONS1,2,or3,beinatleastHOTSHUTDOWN l 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 # suspend all operations involvin I handlingofirradiatedfuelinthecontainment,COREALTERAk!0NS, '
and operations with a potential for draining the reactor vessel, i
- d. With one primary containment air lock door inflatable seal system air
' flask pressure instrumentation channel inoperable. restore the inoperable channel to CPERABLE 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 > to oaig.
SURVEILLANCE REQUIREMENTS
- 4. 6.1. 4 Each . primary containaient air lock shall be demonstrated OPERABLE:
i
- 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 />"* when the-air lock is being used for sultiple entries, by j verifying seal leakage rate is in compliance with the limits in l
$pecification 3.6.1.3.d when the gap between the door seels is pressurized to Pa, 7.6 psig.
anc
- b. By coeducting an overall air lock leakage tact at Pa, 7.6 psig, limit:
verifying that-the overall air lock leakage rate is within its
- 1. At least once per 6 months,"*
- f. : .
,' #When irradiated fuel is being handled in the primary contaissent and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
- The provisto'ns of Specification 4.0.2 are not applicable.
RIVER SEND - UNIT 1 .
3/4 6a9
i r;
CONTA1884 TNT SYSTDtl ,
DayWELL AIR Letts
, LIMITING CONDITION FOR OPERATION _
3.8.2.3 The depe11 air lock shall be OPERA 8LE with:
- a. Seth doors closed eacept that, when the air lock is being used for neraal-transit entry and emit threegh the drywell, at least one air lock door shail be eleses, and bl An evere11 air lock leakage rate of less than er equal to 11.88 scf per
, hour at 3.0 paid, and i 4 e.- The inflatable seal systes air flask pressure g,78 psig.
I APPLICA81LITY: OPERATIONAL CONDITIONS 1. 28 and 3.
$filj.9t!: ,
With_ ene drywell air lock door inoperableff
- e. .
/ -
- - _ d (Natatain at least the OPERABLE air lock door closed and either f - resters the inoperable air lock door to OPERABLE status w12in 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 dose closed. Operation may
, then sentinue provided that the OPERA 8LE air lock door is verified ,
5 to be locked closed at least once par 31 days. / Otherwise, be in at
.3 east NOT $NLR00W 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 SMUT 00W the fe110winsLt4pp -- a
- Q' i
_ = v 510 7maM. . Arli...;-G y...
_-_ -_=_
1
- b. With the drywell. air 10th topperable, eacept as a result of an inoperable air lock door, maintain at toast one air lock door closed;- restore the-inoperable air lock to OPERA 4LE' status within 24 hoves or be in at least NOT $ NUT 00WN wtDin 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 SHUTDOW v12in the following 24 homes. .
.s. W12 ene inoperable drytell air lock door' inflatable seal systes air flask pressges instrumentation channel, restore the inoperable channel to OPERABLE status w12in 7 day $ er verify air flask pressure to be g,78 psig at least once per la hours.
"See Special Test faception 3.10.1. ,
AlvtR BEND - 48GT 1- 3/4 6-29
'*9, ' k* -
g
406 vrq a Y
Q "0'0" o - 4
.
- CONTA!W4ENTSYSTEM1 3/4.6.4 Pt! MARY CONTAIMENT AND DRYWELL !$0LAT10N VALVE 5 AUG 21 H7 LIMITING M ITION FOR OPERATION q U" 'N 8~ [
3.6.4 The rimary containment and drywell isolation valves in .4. !
shall be OP RABLE with isolation times less than or equal to those shown ' n s
Table 3.6.4 1.
APPLICA81LITY: OPERATIONAL CONDITIONS 1, 2, and 3.
I .
M:
With one or more of the primary containment or drywell isolation valves shown. y 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: l
- 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 ("dERD I'
-1
- c. Isolate each affected l
L valve or blind flang@NSERD pena 1 ration by use of at least one cl
- .. . ..a. a .=^v,=raa . .. _ n i ..: _. :_, . .u . ._ u.a e
.a U lillE EEII.'i.l lii.a'.3 ii T l i-- '5ak am* T Aas
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f aE a aEi.ad .
C; '.' ri'-:_5'i~_ :.IZTa Ca ' C' ':_17 :zC "m"'U:a,.
- 1. ' . :Y a :1 ~.hT.'uY' : 'v' ::.7:G'LMM,'G:iL::.'Z. 'Gr *
. - ~ ~
~~~ ~ ~- '~ ~~ ~ --
- .. z;
- . - . ;,1 z ' -
. ~~ -
~~ ^
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p Otherwise, be in at least HOT $HUTDOWN 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 />.
SURVEILLANCE REQUIREMENTS 1
4.6.4.1 Each isolation valve shown in Table 3.6.4-1 shall be demonstrated CPERA8LE prior to returning the valve to service, after maintenance, repair or 1
- 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 verifyin0 the specified isolation time.
4.6.4.2 Each automatic isolation valve shown in Table 3.6.4-1 shall be demon-strated OPERABLE during COLD SHUTDOWN or REFUELING at least once per ;
by verifying that, en an isolation test signal, each automatic isolation valve actuates to its isolation position.
n! solation valves closed to satisfy these requirements asy be reopened on an '
intamittent basis under administrative controls.
8The specified 18 month interval during the first operating cycle may be extended 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 RECEIVED g ndment yo, ,
RIVER SE E - UNIT 1 AUG 191987 l
'~ .
$ O r.
V . . .
. . . . ______. ~ . -. - - - .
- ;*- lNSERT" for Dani 3/4 6-31
)
~
_ y and deciare the-associated system inoperable, if applicable, and perform the associatedp__
ACTION statements for that system,
< l
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I CONfAlls p T_ $YSTEMS ggc g3 in, sEM*Y CollTAlleENT AUTOMATIC !$0LAT!0ll DAWERS (g. ... s............g ,... g
.. . . .o.,
LIMIT! IIB M IT10Il FOR OPERAT1000 h J .
3.6.5.3 The secondary containment ventilation systes automatic isolation dampers shown .in Table 3.6.5.3-1 shall be OPERA 8LE with isolation times less than er equal to the times shown in Table 3.6.5.3-1.
APPLICA81LITY: As shown in Table 3.6.5.3-1.
g7_1011:
tiith one or more of the secondary containment ventilation systes automatic (seletion despers shown in Table 3.6.5.3-1 inoperable, enintain at .least one isolation desper OPERA 8LE in each affacted penetration that is open and, within l
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) to OPERA 8LE dtatus, or
- b. Isolate each affected penetration by use of at least one deactivated automatic damper secured in the isolation positio g{g l
- c. Isolate each affected penetration by use of at least one closed manual valve or blind flag;y3g
- - - - ~- - _ .
L 1 m -
- e ' r -- -*
- r- d 'i --*
- e-
- a ' 2 r
re'.m:;;..' 'm?6'
- :;'d: 'a t m ,- & .. .
.m. .,, . a ......... .. ......a4. ....
x .r' TJ;i 42;1 K;. RJ;;G;i;.5 ;;;;ri; ri ' ;x;'" E -
53i5f:f!5-5-di5125 't :;j-55fid'5 dd"':^^^5M ^57d'^jlt
~
. . . . . . . . ~
_ 3; Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, be in at least HDT $HUTDOWN 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 $ HUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Otherwise, in Operational Condition N, suspend handling of ~ irradiated -
f
' tuel in the Fuel Building. The provisions of Specification 3.0.3 are not applicable.
SUird!LL*M REQUIREBENTS 4.6.S.3.. Each secoedary containment ventilation system automatic isolation-deeper shown la Table 3.6.5.3-1 shall be demonstrated OPERABLE:
o
- e. prior to returning the damper to service after esintenance, repair or
' replacement work is performed on the desper er its associated actuator,
' .- control er power circuit, by cycling the desper through at least one complete cycle of full travel and verifying the specified isolation time, i NWhen irradiated fuel is being handled in the Fuel Building.
RIVER SEND - UNIT 1 3/4 6 51 l
l
4 I j'i 'D ' " lNSERT" for pac 7 3/4 6-51 N
and declare.t e associated system inoperable, if applicable, and' perform the associated ACTION-' statements for that system. .!
- v_ _
- 1 1
1 1
i-i t -- y l .' ,
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Y 6
. 1 PLMit $YSTEMS , ,
K SPRAY AN0/OR SPRIN'LER $YSTEMS I LINITING CONDITION FOR OPERATION 3.7.8.2 The following spray and sprinkler systems shall be OPERABLE:
SYSTEM l LOCATION ELEVATIQN IDENTITY I
\
- a. Control Bldg. Cable Chases 116'0" AS-6A '
98'0" AS-68 70'0" AS-6C, WS 6A, WS-48, WS-6C 115'0" WS-7A, WS-78
- b. Cable Tunnels 67'6"no'0" WS-80, W5-4E, WS 8F, 67'6"n0'0" WS 8G, WS SH, WS-8K, ,
67'6"/70'0" WS-SL, W5-SM, WS 8N '
j
- c. Auxiliary Bldg., RCIC 70'0" PS-1, WS-19 Pump Room 141'0"' WS-4A, WS 48 WS-20, A5-12 l
- d. Diese1' Generator B1dg. 98'0" PS 2A,'35-28, PS-2C .
I
- e. F.uel B1dg. 95'0" A5-5 .
148'0" WS.-5A, WS-58 APPLICABILITY: Wheneverequipmentprotectedbythesprayorsprinkler . I systems is required to be OPERA 8LE.
ACTION: q
- a. With one or more of the above required spray or sprinkler systems . ,
inoperable, within one hour establish a continuous fire watch with l 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.
1
- l RIVFR BEND - UNIT 1 3/4 7-21
_ = _ _ _ _ . .- . - -
- l l
PLAN 7 $YSTEMS J. . HALON SYSTEMS LIMITI% CONDITION POR OPERATION 3.7.8.3 The fellowing main control room Power, Generation Control Complex (PGCC)
Halon systems shall be OPERABLE with the storage tanks having at least 955 of full charge weight and 905 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 U710 PGCC Panel Module U741 PGCC Panel Module U711 PGCC Panel Module U742
-PGCC Panel Module U712 PGCC Panel Module U743 PGCC Panel Module U713- PGCC Panel Module U744 PGCC Panel Module U714 PGCC Panel Module U745 PGCC Panel Module U715 PGCC Panel Module U748 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 AppLICA8ILITY: Whenever equipment protected by the Halon systems is required '
to De OPERA 8LE.
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 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 provis1oris of Specificatio 3.0.3 [jharenotapplicable.
SVRVEILLANCE REQUIREMENTS A,7 $,3 The above etquired Halon system shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each Halon systes storag tank is pressurized to at least 280 psig.,
- b. At least once per 6 months by verifying Halon storage tank weight and pressure.
l- .
L RIVER SEND - UNIT 1 3/4 7-23 I
- _L _ _ __ - ____ _ _ _ . ._ - . . . . . .. -..
4 PL#ff $YSTEMS
+
FIRE HO$E STATIONS LIMITING CON 0! TION FOR OPERATION
'3.7.6.4 The fire hose stations shown in Table 3.7.8.4-1 shall be OPERABLE.
APPL l:CA81LITY: Whenever equipment in the areas protected by the fire hose stat' ons is required to be OPERABLE.
ACTION: .
- a. With one or more 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 OPERA 8LE hose station. Signs shall be sounted 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 is the primary means of fire suppression; other-wise route the additic'nal hose within 24 houts,
- b. TheprovisionsofSpecificatio[3.0.'3 are not applicable.
SURVEILLANCE REQUIRE.MENTS 4.7.6.4 Each of.the fire hose stations shown in Table 3.7.6.4-1 shall be demonstrated OPERABLE: q
- a. At least once parli days by a visual inspection of the fire hose stations eccessible during plant operation to assure a.11: required- l equipment is at the station. 1 l
- 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 he'se for inspection and re-racking, and
3/4 7-25 RIVER SEND - UNIT 1
PLANT SYSTDIS ,..-
YARD FIRE WYDRANTS AND NYORANT HOSE HOUSE 5- D LIMITING CONDITION FOR OPERATION i 3.7.6.5 The yard fire hydrants and associated hydrant hose houses shown in i Table 3.7.6.5-1 shall be OPERA 8LE.
APPLICA8!I,ITY: . Whenever equipment in the areas protected by the yard fire -
hydrants is requir'ed to be OPERABLE. -
3 M: '
- a. With one or more of the yard fire hydrants or associated hydrant j 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 sufficient additional lengths of 2 1/2 inch diameter hose located in an adjacent CPERABLE hydrant hose house to provide service to the unprotected area (s) if the inoperable fire hydrant or associated ,
hydrant hose house is the primary means of fire suppression; !
otherwise provide 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. - TheprovisionsofSpecificattof3.0.3 F are not applicable. l4 i
SURVEILLANCE REQUIREMENTS ,"
4.7.6.5 Each of the yard fire hydrants and associated hydrant hose houses i shown ,io Table'3.7.6.5-1 shall be demonstrated OPERA 8LE:.
- a. At least once per 31 days by visual bspection of the hydrant hose house to assure all required equipment is at the hose house,
- b. At least once per 6 months, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and '
that the hycrant is not damaged.
c.- At least once per 12 months by:
1.- Conducting a hose hydrostatic test at a pressure of 150 psig er at least 50 psig above the maximum fire main operating pressure, whichever is greater. .
- 3. Performing a flow check of each hydrant, i
e G
RIVER BEND - UNIT 1 3/4 7-28
. l PLANT SYSTEMS ,.. ;
3/4.7.7 FIRE-RATED A$$DeLIES ,
"! LIMITING CONDITION FOR OPERATION 3.7.7 All fire barrier assemblies shall be OPERA 8LE. Fire barrier assemblies include: <
- a. Walls, floors / ceilings, cable tray enclosures, and other fire barriers j that separate safety-related fire areas or that separate 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..
APPLICA8ILITY: At-all times.
ACTION:'
- a. With one or more of the above required fire-rated assembifes or '
sealing devices 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 on at least one side of the affected assembly and/or sealing device or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly or sealing device, and establish an hourly fire watch patrol. -
- b. TheprovisionsofSpecificatiof3.0.3OfC.33arenotapplicable.
I SURVEILLANCE 1EQUIREMENTS 4.7.7.1 'Each of-the above required fire-rated assemblies and penetration l sealing devices shall be verified OPERABLE at least once per 18 months by
- i- 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 pentration. If changes in appearance or abnormal degradations are found, a visual inspection-of an additional 10 percent of each type of sealed penetration shall '
i be made. This inspection process shall continue until a 10 percent sample is found with no apparent changes in appearance or abnormal degradation. Samples shall be,qelected such that each penetration l seal will be inspected at least once per 15 years. .
1 l
1 RIVER BEND - UNIT 1 3/4 7-30
. i
L 1 .
f pL4;dT SYSTEMS E
y 3/4.7.10 STRUCTURAt SETTLEMENT g LIMITING CONDIT!fW 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 l b. Auxiliary Building p c. Fuel Building L
- d. Control Building
- e. Diesel Generator Building s
- f. Standby Cooling Tower, Basin and Pump House !
- g. .BF Tunnel l
- h. '
Main Steam Tunnel
- i. E Tunnel
- j. -G Tunnel !
l l APPLICA8ILITY: At aT1 times. ,
L '
l ., ACTION: ,
With the measured structual settlement of any of the above required structures outside of the ,imits 1 of Tables 3.7.10-1 and 3.7.10-2, prepare and submit, within the next 30 days, a Special Report to the Commissipn, pursuant to Specification 6.9.2, providing a record of the settlement measurements-and the .
predicted settlement, an analysis to demonstrate the continued structural integrity of the affected structure (s), and plans to monitor the settlement of the1affected 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.
SURVEILLANCE 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:
l
- a. At least once per 92 days. until there is essentially no movement during those 92 days.
- b. At ,1 east once per 24 months, for at least 10 years.
- c. Following any seismic event equal to or greater than an Operational Basis Earthquake (08E).
l -' . .
RIVER BEND - UNIT 1 3/4 7-35
I ELECTRICAL POWER SYSTEMS- .
3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES PRIMARY CONTAIMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LINITING CONDITION FOR OPERATION e l 3.8.4.1- All primary containment penetration conductor overcurrent protective m
devices shown in Table 3.8.4.1-1 shall be OPERABLE.
i APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
l h With one or more of the primary containment penetration conductor overcurrent l protective devices shown in Table 3.8.4.1-1 inoperable, declare the affected l system or component inoperable and apply the appropriate ACTION statement for the a*fected systes and:
For 4.16 kV circuit breakers, de-energize the 4.18 kV circuit (s) by .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 'serifying, at least once.per 7 days thereafter, the redundant cirr.uit breaker to be tripped. ]
or 480 volt circuit breakers, remove the inoperable circuit breaker (s) l 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 l
1 racked out.
or 480 volt MCC circuit breaker / fuse combination starters, remova-l' the inoperable starter (s) from service by locking the breakers open 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- 1 cuit breaker to be locked open with she control power fuse removed.
~ h er 120/140 volt solded case circuit breakers, remove the inoperable l' circuit breaker (s) from service by. tripping both 120/140 volt breakers open and locking the upst eam 480 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 L 400 volt MCC breaker (s) to be locked open.-
l-Othemise, be in at least HDT 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 SHUTDOWN 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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s RIVER BEND - UNIT 1 3/4 8-25
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i ELECTRICAL POWER SYSTEMS ,
OTHER OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION
- 3. 4. 4. 2 The overcurrent protection devices shown in Table 3.8.4.2-1-shall be OPERABLE.
E APPLICA8!LITY: At all times. .
ACTION:
With one or more of the overcurrent protective devicec shown in Table 3.8.4.2-1 l-o 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 return the overcurrent protection devices to 0PERA8LE status within
.m..m_7 days. ee_,,=._,.__m warify 1he,maarone:. __.am ate
_ brea_ktrs aaan _alleast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />." :
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SURVEILLANCE REQUIREMENTS 4.8.4.2 The overcurrent protective devices shall be demonstrated OPERA 8Lt at least-on:e per 18 months by selecting and testing one-half of each type of- .
, circuit breaker on a rotating basis. Testing of these circuit breakers shall
. consist of in,jecting currents in excess-of the breaker's nominal *setpoint '
and sensuring the response time-of the long time and short time delay elements and the setpoint of the instantaneous element, as a.spropriate. The sensured -
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.
p i
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% cept at least once per 31 days if locked, sealed, or otherwise secured in the open position.
RIVER 8END - UNIT 1 3/4 8 33 1_ .. .
REFUELING OPERATIONS RECEIVED l IIAR 141989 :
LIMITING CONDITTON FOR OPERATION 3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation," with each train consisting of at least:
- a. One OPERA 8LE RHR pump, and
APPLICABILITY: OPERATIONAL CON 0! TION 5, when irradiated fuel is in the reactor vesseT ~and the water level is less than 23 feet above the top of the reactor pressure vessel flange.
ACTION:
- a. With less than the above required shutdown cooling mode loops of the RHR system OPERABLE.- within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least one alternate method capable of-decay heat removal for each inoperable RHR shutdown cooling mode train,
- b. With no RNR shutdown cooling mode loop in operation, within one hour establish reactor coolant c' rculation by an alternate method, and monitor -
reactor coolant temperature at least once per hour.
of-Spec- tion 3.
s Arovisi x SURVEILLANCE u gUIREMENTS
> x-mt ]
.4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal systee or alternate method shall be verified, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, to be ,!
in operation and circulating reactor coolant.
l 1
Ine shutdown cooling pump mRy be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> lh t!' the-seco
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h l RIVER BEND - UNIT 1 3/4 9-18 Amendment No. 36 l
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e 4A010 ACTIVE EFFLUENT $' ,
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LIMITING CONDITION FOR OPERATION 3.11.1.1 The dose or dose commitment to a MDSER OF THE PUBLIC free radio-active materials,in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 areas to the total;botty and to less than or equal to 5 ereas to any organ, I and R
.1
- b. During any calendar year to less than or equal to 3 ocess to the I total body and to less than or equal to 10 areas to any organ. )
APPLICA8ILITY:. At all times, j ACTION:
a .' With.the calculated dose,from the release of radioactive materials I in ligvid effluents, exceeding any of the above limits. prepare and I
. submit to the Commission within 30 days, pursuant to Specifica- !
tion 6.9.2, a Special Report that identifies the cause(s) for exceedir '
, the limit (s) and defines the corrective, actions that have been taken ,
to reduce the releases and the proposed corrective actions to be
- '-1 taken to assure that subsequent releases will be in compli'ance with the above limits.
- b. The' provisions of Specificatiof3.0.3Q * ^ ")are not applicable.
$URVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents *for the current calendar quarter and the current calendar year shall be determined, at least once per 31 days. in accordance with the methodology and parameters in the 00CM.
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4 RIVER SEND - UNIT 1 3/4 11-4
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RADICACTIVE EFFWENTS -
LIQUID RADWASTE TREATMENT SY$ TEM LIMITING CONDITION FOR OPERATION l .
3.11.1.3 The liquid radweste treatment system shall be used to reduce the radioactive materials in liquid wastas prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS (see
' Figure 5.1.3-1) would exceed 0.06 aren to the. total body or 0.2 ares.to any
- k organ in a 31 day period. .
I' APPLICA8ILITY: At all times.
ACTION:
- a. With radioactive liquid waste being discharged without treatment.and in excess of the above lisits, prepare and subeit to the Commission within J0 days, pursuant to Specification 6.9.2 'a Special Report'tnat includes the following inforsation:
- 1. Explanation of why liquid radwaste 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 OPERA 8LE-status, and 3.
Summary description of ac, tion (s) taken to prevent a recurrence. i l
- b. Theprovisions'ofSpecificatief3.0.3{- hare'notapplicable. l;I SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses due 'to liquid releases to UNRESTRICTED AREAS shall be projected I at least once per 31 days in accordance with the methodology and parameters in tr.e P CM.
- 6 9
RIVER SEND - UNIT 1 3/4 11-5 1
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l L _RADI0AfriVE EFFLUENTS q
oost - NQRL[4A$($
LIMITING CONDITION FOR OPERATION l
3.11.2.2 The air de'se due to noble gases released in gaseous effluents to areas at and neyond the SITE SOUNDARY (see Figures 5.1.1-1 and 5.1.3-1) shall be limited to the fellowing: ,
- s. During any calendar quarter: Less than or equal to 5 erads for gamma radiation and less than or equal to 10 mrads for beta radiation and,.
p b. During any calendar year: Less.than or equal to 10 erads for gamma radiation and less than or equal to 20,arads for beta radiation.
APPLICABILITY: At all times. l
-l l
ACTION:
- a. With the calculated air dose from radioactive noble gases in gaseous.
effluents exceeding any of the above limits, prepare and submit to I 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 releases,will be in compliance with tho'
- above limits,
- b. ,The' provisions of Specificatio 3.0.3 are not applicable, j
- . SURYEILLANCE REQUIRENENTS 4.11.2.2 At least once per 31 days, cumulative dose contributions for the cut-rent calendar quarter and current calendar year for noble gases shall be ceter-eined in accoroance with the methodology and parameters in the 00CM.-
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b RIVER BEND - UNIT 1 3/4 11-11 e
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RADIDACTIVE EFFLUENTS .-
00st - 100!NE-131.100!NE-133. TRITfuM. AMD RADIONUCLIOES IN PARTICULATE FORN l 4
1 LIMITING CON 0! TION FOR OPERATION 3.11.2.3 The dose to a MDGER OF THE PUBLIC free iodine-131, iodine-133, trittua, and all radionuclides in particulate fore with half-lives greater than 8 days, in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Figures 5.1.1-1 and 5.1.31), shall be 11mitad to the.following:
_a. During any calendar quarter: Less than or equal to 7.5 areas to any J
organ and.
. i
- b. During any calendar year: Less than or equal to 15 areas to any -j o rgan. ,, !
i APPLICASILITY:' At all times.
ACTION:
- a. With the calculated dose from the release, in gaseous effluents, of iodine-131, iodine-133, tritius, and radionuclides in particulate .
fore with half lives greater than 8 days, exceeding any of the above
- )
. limits, prepare and submit to the Commission within 30 days, pursuant g to Specffication 6.g.2, a Special Report that identifies the cause(s)_
s Tor 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 be'in compliance .
with the above limits.
- b. TheprovisionsofSpecification3.0.3lf[l[j[j(f)arenotapplicable. l SURVIILLANCE REQUIREMENTS 4.11.2.3 At least once per 31 days, cumulative dose contributions for. the cur-rent calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives gMater than 8 days.'shall be determined in accordance with the methodology and parameters in the 00CN.
RivtR SEND - UNIT 1 3/4 11-12
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- RADICACTIVE EFFLUENTS ,
. GASE005 RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION
- 3. u.2.4 The GASEQUS RADWASTE TREATMENT (QFFGAS) SYSTEM shall be in operation.
. APPLICABILITY: Whenever the sain condenser air ejector system is in-operation.
ACTION:
. a. With GASE005 RADWASTE TREATMENT (0FFGAS) SYSTEM inoperante for more than 7 days, prepare and submit to the' Cornission within 30 days,.
pursuant to Specification 6.9.2, a Specia.1. Report that incluces the following information:
- 1. Identification of the inoperable equipment or subsystems and .
the reason for inoperability,
}
- 2. Action (s)' taken to restore the inoperable equipment to OPERABLE status..and.
3.' Sunnary description of action (s) taken to prevent recurrence,
- b. TheprovisionsofSpecificatiof3.0.3hfi_[jarenotapplicable.
SURVEILLANCE REQUIREMENTS f-i' 4.11.2.4 The instruments specified in the 00CM shall be checked every. ,
+
12 ' hours, whenever the main condenser air ejector is in -operation, to ensure <
that tne GASE0US RADWASTE TREATMENT (OFFGAS) SYSTEM is functioning, w
i s
l RIVER SEND - UNIT 1 3/4 M*13 l h
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RADI0 ACTIVE EFPLUENTS .
i . *l Ypff!LATION 004AUST TREATMENT
"/..
LINITING CON 0! TION FOR OPERATION 3.11.2.5. The VENTILATION. EXHAUST TREATMENT SYSTEM shall be used to reduce i' radioactive materials in gaseous wasta prior to their discharge when the projected doses, due to gaseous affluent releases to areas at and beyond the *
$1TE BOUNDARY (see Figures 5.1.1-1 and 5.1.3-1), would exceed 0.3 ares to any organ in a 31 day period.
. APPLICABILITY: At all times.other than when the VENTILATION EXHAUST TREATHENT system is undergoing routine maintenance. .
ACTION:
- a. Vith gaseous waste being discharged free the ventilation exhaust ducts without treatment and in excess of the above limits, prepare ;
and sutait to the Gossaission within 30 days,. pursuant to specifica-tion 6.9.2 a Special Report that includes the following information:
- 1. Explanation of why gaseous radweste was'being discharged without-treatment, identification of any inoperable equipment or sub-
..N systaas and th's reason for the inoperability.
- 2. Action (s) taken to restore the inoperable equipment to CPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. The provisions of Specificat 3.0.3Qd}[uare not applicable. l SURVEILLANCE REQUIREMENTS 4.11.2.5 Doses due to gaseous releases from the site s'all be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM.
e i
RIVER BENO - UNIT 1 3/4 11-14 1
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i, 3/4. n. 3 SOLID RADICACTIVE WASTE 1
LIMITING CONOTTION FOR OPERATION ,
3.n.3 The solid radwasta systes shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial j ground requiresenta.- ,
l APPLICASILITY: At all times. .;
ACTION:
- a. Witt. the provisions 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 $pecificatiof3.0.3hj are not applicable. }.
i
$URVEILLANCE REQUIRD4ENTS 4.n.3 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION -
of at least one representative test specimen from at least every tenth batch-of each type of wet radioactive waste (e.g., filter sludges, spent. resins, evaporator bottoms, sodium sulfate solutions).
. a. If 'any test specimen fails to verify $0LIDIFICAT!0N,.the SOLIDIFICA-TION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICA-TION of the batch may then be resumed using the alternative SOLIDIFI-CATION parameters determined by the PROCESS CONTROL PROGRAM.
- b. If the initial test specimen from a batch of, waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each.
consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.
The *ROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of wasta.
4 RIVER BEND , UNIT 1 3/4 n-17 4
- . .- - - - - . -. . . - - - . - - .. -~ -.
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RADI0 ACTIVE EFFLUENTS-h . 3/4.n.4 TOTAL 00$E ,. '
LIMITING C0W ITION FOR QPERATION L
$ 3.n.4 The' annual (calendar year) dose or dose consitsent to any MEMBER 0F-THE PUBLIC, due to releases of. radioactivity and to radiation from uranium fuel cycle sources,.shall be limited to less than or equal to 25 areas to the total-
[' body or any organ, except the tityroid, which shall be lietted to less than or r E ' equal to 75 areas.
' APPLICA8ILITY: At all times.
ACTION:
- a. With the calculated doses from the release of radioactive eaterials in liquid or gaseous effluents exceeding:twice the limits of Specifica-tion 3. n.1.2.a,.3. u.1.2.b. 3. n.2.2.a. 3. u.2.2.b 3. u.2.3.a. or <
- 3. n.2.3.b calculations should be made, including direct radiation I contributions from the reactor units and from outside storage tanks, ;
.to determine whether the above limits of 5pecification 3. n.4 have been exceeded. If such is the case, prepare and submit to the Coesis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the. corrective ection to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and that includes the schedule for achieving conformance with the above limits S This Special Report; as defined in 10 CFR Part 20.405c, shall include .
an analysis that estimates the radiation exposure (dose) to a MEM8ER 0F THE.PU8LIC from uranium fuel cycle sources, including all. effluent i
pathways and direct radiation, for the calendar year that includes- ;
the release (s) covered by this report. I.t shall also describe levels l of radiation and concentrations of radioactive eaterial involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) axceeds the above 1imits and, if the release condi- 1 tion resulting in violation of 40 CFR Part 190 has not already been 'l corrected, the Special Report shall. include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of o the report is considered a timely request, and a variance is grantec I until staff action on the request is couplete.
- b. The provisions of Specificatio 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS )
I
- 4. n. 4.1 Caulative dose contributions from liquid and gaseous effluents shall. l
- be determined in accordance with Specifications 4.11.1.2, 4. n.2.2, and 4. n.2.3 and in accordance with the methodology and parameters in the 00CM.
- 4. U. 4. 2 Cumulative dose contributions from direct radiation free the reactor unit and from any unprotected outdoor storage tanks shall be detareined in accordance with the methodology and parameters in the C0CM. This requirement ?-
is applicable only under conditions set forth in Specification 3.u.4, Action a.
RIVER 8END - UNIT 1 3/4 H-18 i
g
o RADIOLOGICAL ENVIRONMENTAL MONITORING .
LDtITING CLwnITION FOR OPERATION (Continued) ,
g: (Continued) specific locations free which samples were unavailable say'then be deleted free the monitoring profiras. Pursuant to Specification 6.9.1.8,
- identify the cause of the unava' lability of samples and identify the new location (s) for obtaining replacement semples 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 Specific,atio 3.0.3(i((3)arenotapplicable. l
$URVEILLANCE REQUIREMENTS
- 4. U.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.M.1-1 free the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of Table 3. U.1-1 and the detection capabilities required by Table 4. U.1-1.
d
. RIVER BEND - UNIT 1 3/4 I M i i
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t-RADIOLOGICAL ENVIR0 MENTAL MONITORING 3/4. u. 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, the nearest residence and the nearest gardena of greater than 50 es (500 ft8) producing broad leaf vegetation. .
APPLICA8ILITY: *At all times.
ACTION:
- a. With a larid use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being-calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant.
to Specification 6.9.1.8.
- b. With-land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location free which samples are currently being obtained in accordance with Spec.ification 3.12.1, add the new loca-tion (s) to the radiological- environmental sonitoring program within 30 days. The sampling location (s), excluding the control station location . having the lowest c&lculated dose or dose *cocit int (s),
via the same exposure pathway, may lie deleted from this moritoring program after October 31 of the year in which this land i;.t census was conducted. Pursuant to Specification 6.9.1.8, identify the new locati'n(s) in-the next Semiannual Radioactive Effluent Release
- Report and include in the report a revised figure (s) and table
- for the 00CM reflecting the new location (s).
- c. The provisions of Specificatio 3.0.3 Q l. M are not applicable. l SURVEILLANCE REQUIRENENTS 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 results, such as by a door-to-door survey or serial survey or by consultir.g
- local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Envirormental Operating . Report pursuant to Specification 6.g.1.7. ,
"In lieu,'of the garden census, brotd leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs. Specifications for broad leaf vegetation sampiing in Table 3,12.1-1, 4e shall be followed, including analysis of' control samples.
I RIVER BEND - UNIT 1 3/4 12-13 Q
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RADIOLOGICAL ENVIRONMENTAL MONITORING ,
3/4.12.3 INftRLABORATORY COWARISON PROGRAM ,
LIMITING CONDITION POR OPERATION'
- 3. u. 3 Analyses-shall be performed on radioactive asterials, that correspond to samples required by Table 3.12.1-1, supplied as part of an Interlaboratory Casparison Program that has been approved by the Commission. .
APPLICABILITY: At all times.
ACTION:
- a. With analyses not being performed as required above, report to the Commission, in the Annual Radiological Environmental Operating Report pursuanc to Specification 6.9.1.7, the corrective actions taken to prevent a recurrence.
- b. TheprovisionsofSpecificatiof3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS
~
,g 4.12.3 the Interlaboratory Coagarison Program shall be described in the 00CM.
.A summary of the results obtained as part of the above required-Interlaboratey Comparison Program shall be .inciude'd in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. .
6 4
9 .
RIVER BEND - UNIT 1 3/4 12-14 l
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