ML082340839
ML082340839 | |
Person / Time | |
---|---|
Site: | Palo Verde ![]() |
Issue date: | 08/13/2008 |
From: | Weber T APS, Arizona Public Service Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
102-05885-TNW/CJS | |
Download: ML082340839 (35) | |
Text
Technical Specification 5.5.14 Thomas N. Weber Mail Station 7636 Palo Verde Nuclear Department Leader Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-05885-TNW/CJS August 13, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-52815291530 Technical Specifications Bases Revision 49 Update Pursuant to PVNGS Technical Specification (TS) 5.5.14, "Technical Specifications Bases Control Program," Arizona Public Service Company (APS) is submitting changes to the TS Bases incorporated into Revision 49, implemented on August 6, 2008.
The revision insertion instructions and replacement pages are provided in the Enclosure.
No commitments are being made to the NRC by this letter. Should you have any questions regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
Sincerely, TNW/RAS/CJS/gat A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon
- Palo Verde 0 San Onofre 0 South Texas 0 Wolf Creek Mf
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Technical Specifications Bases Revision 49 Update Page 2 Enclosure - PVNGS Technical Specification Bases Revision 49 Insertion Instructions and Replacement Pages cc: E. E. Collins Jr. NRC Region IV Regional Administrator (enclosure)
M. T. Markley NRC NRR Project Manager (enclosure)
R. I. Treadway NRC Senior Resident Inspector for PVNGS (enclosure)
ENCLOSURE PVNGS Technical Specification Bases Revision 49 Insertion Instructions and Replacement Pages
Insertion Instructions for the Technical Specifications Bases Revision 49 REMOVE PAGES INSERT PAGES Cover page Cover page List of Effective Pages List of Effective Pages 1/2 through 7/8 1/2 through 7/8 B 3.0-1 / B 3.0-2 B 3.0-1 / B 3.0-2 B 3.0-13 / B 3.0-14 B 3.0-13 / B 3.0-14 through through B 3.0-19 / B 3.0-20 B 3.0-21 / B 3.0-22 B 3.1.5-7 / B 3.1.5-8 B 3.1.5-7/ B 3.1.5-8 B 3.4.6-3 lB 3.4.6-4 B 3.4.6-3/ B 3.4.6-4 B 3.6.1-1 / B 3.6.1-2 B 3.6.1-1 I B 3.6.1-2 B 3.6.2-1 / B 3.6.2-2 B 3.6.2-1 I B 3.6.2-2 B 3.6.3-3 / B 3.6.3-4 B 3.6.3-3 / B 3.6.3-4 1
PVNGS Palo Verde Nuclear GeneratingStation Units 1, 2, and 3 Technical Specification Bases LPDig itally signed by Revision 49 Stephen ison, Carl J August 6, 2008 Aug n 8Stephen 'DN. n=Stephenson, Carl J ofl,.Ca r/ Reason: This is an accurate copq 'ofthe-ofiginal
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Date: 2008.08.01 09:54:50
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- 27 B-3.9.5-4 16 B.3.9.5-5 16 B 3.9.6-1 0 B 3.9.6..-2 0 B 3.-9,63 0 B 3.9.7-1 PALO VERDE UNITS 1, 2, AND 3 8 Revision 49 August 6, 2008
LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCOs LCO 3.0.1 through LCO 3.0.8 establish the general' requirements applicable to all Specifications and'apply at I all times unless otherwise stated.
LCO 3.0.1 LCO 3.0.1 establishes the Applicability statementWithin each individual Specification as the requirement for when."
the LCO is required to be met (i.e., when the unit.is' in the MODES or other specified conditions of the Applicability statement of each Specification).
LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met.-.The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that:,
- a. Completion of the Required Actions within the.
specified Completion Times constitutes compliance with a Specification: and
- b. Completion of the Required Actions is not requiired when an LCO is met within the specified Completion Time, unless otherwise specified'.
There are two basic types of RequiredActions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is-the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. :If this type of Required Action is not completed within the.-.-
specified Completion Time, a shutdown may be required to" place the unit in a MODE or condition in which the -
Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering
,(continued)
PALO VERDE UNITS 1'.2,3 PALO.ERDEUNITS1.. -B 3-0-1 .... -- REVIS'ION-49 REV-IO.4
LCO Applicability B 3.0 BASES LCO 3.0.2, ACTIONS.). The second :type of Required.Action specifies the (continued).- remedial: measures that permit continued operation of the .*
unit that is not further restricted by'the Completion Time.
In this case, compliance with the Required Actions provides an acceptable, level of:safety:for continued operation.
Completing the Required Actions is not r'equired when an LCO 1is met. or is no longer. applicable, unless otherwise stated in thejindividual Specifications.,..
The nature of some Required'Actions of'some Conditions.
.necessitates-that,. once. the..Condition is entered, the Required Actions must be 'co6pleted even though the
. associated-Conditions nolorigeexist. The individual LCO's ACTIONS specify~the Recuired Ac.t.*ions where this is the case.
An exampleof thisi*S. inLCO-3A.3_, "RCS Pressure and Temperature (P/T)[limits._" :.
The. Completion Times of theP-Required..Actions are also applicable when 1a's'yt'em, or ,componentis removed from
_,,ervice intent*.on*li!' Thie.reasons,.for' intentionally relying on t e:.:CIOINS' include, but are'not limited to, ances., preventive maintenance, performance. of, 5uff.,/ei 1.1 corrective maihtenance, or investigation of operational
,,.problems..,Entering ACTIONS f6r these'reasons must be done in a manner that' does.not'.compromise, safety. Intentional entry..,into ACTIONS.should not be made for operational convenience. Alternatives'that' would not result in S..redundant equipment ,being inoperable, should be used instead.
Doing so limits the time, both subsystems/trains of a safety function are inoperable and'limits the time other conditions exist which result in.LCO,3.0.3 being entered. Individual Specifications may specify a"time limit for performing an SR
.when equipment.is removed from service or bypassed for testing. .,In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from.service or bypassed.
When a change in MODE orother~specified condition is required to comply with Required Actions, the unit may enter a: ODE or other specified condition in which another Specification becomes applicable. In this case, the Completion Times of the associated. Required Actions would apply, from the.point in time that the new Specification becomes applicable and the ACTIONS Condition(s) are entered.
(continued)
PALO VERDE UNITS 1,2,3 B 3.0-2 REVISION 0
j~~iC'~
LCO Applicability B 3.0 BASES LCO 3.0.7 otherwise specified,'all'other TS requirements remain (continued) unchanged and-in' effect as applicable...'This will. ensure that al 1..appropri ate requirements of -the. MODE or other specified condition, not directly associated with or required to :be changed or suspended 'to perform the special test or operation will remain in effect.
ThetApplicabi'lity of-an STE LCO .represents a condition not necessarily in .compliance With'the normal requirements of the TS. Compliance with STE LCOs is optional.
A special"',test: may.be performed under either the provisions of the:'apgropri'ate STE LCO.`or the other 'applicable TS requirements. '`If it is desired to perform the special test under th0:-'pr6vi,si:ons of the. STE LCO; the requirements of the STE LCO- shal'l'-e fol'owe. 'This includes the SRs specified in the STE LCO.
"Some Of the STE. LCOs-require'that one or more of the LCOs for' normal operatiohwbe met :t(i.e:,-meeting the STE LCO requires mmeeting theLsp'ptified normaiýLCOs). The Applicabil'i'ty, "ACTIONS!,..arid SRs'of'the specified normal
.LCOs, however,- are' not"r'equired tobe met in order to meet the STE LCO when itis is*fn.effect. This means that, upon failure- to meet, a specified normal LCO, the associated ACTIONS of the STE LCO apply,' in lieu of the ACTIONS of the normal LCO. Exceptions-to the above.do exist. There are instances when the Applicability of the specified normal LCO must-be met, where its ACTIONS must be taken, where certain of its Surveillances 'must be performed, or where all of these requirements must be met concurrently with the requirements of theSTE LCO.
Unless the SRs of the specified normal LCOs are suspended or
.changed by' the special test, those SRs that are necessary to meet the specified normal LCOs must be met prior to performing the special test. During the conduct of the' special test, those Surveillances need not be performed unless specified by the ACTIONS or SRs of the STE LCO.
ACTIONS for STE LCOs provide appropriate remedial measures upon failure to meet the STELCO. Upon failure to meet these ACTIONS. suspend the performance of the special test and enter:the ACTIONS:for.all LCOs that are then not met.
Entry-into LCO 3.0.3 may possibly be- required, but this determination should not be made by considering only the failure to meet the ACTIONS of the STE LCO.
(continued)
PALO VERDE UNITS 1,2,3 ' B 3.0-13 'REVISION'42
LCO Applicability B 3.0 BASES LCO 3.0.8. LCO 3.0.8 establishes conditionis under which systems are considered to remain capable of performing their intended safety function when associated snubbers are not capable of providing their associated support function(s). This LCO states -that the'suppor'ted.;system is not considered to be inoperable solely- due to lone :ormore snubbers not capable of performing'their associated support
'function(s),' This is'appropriatebecause a limited length of time, is allowed .for riaintenance, testing, or repair of oneor more snubbers .'not cap'abl6,"0of, performing their associated support, FunctJion(sand appropriate compensatory measures are! specti *ied in the snubber requi rements,; :which,-are locatedob-tside of the Technical Specifications.'- CTS) -under If e,r,3e`ee control. The snubber requirements do' nbt meet*_the' cite'ria in 10 CFR 50.36()(e2));(iý, ard<' as.,such are appropriate for control by't- '-I i cerns'ee.
If the allowed fi66 expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's LCO(s) must be declared not met ,and the ýondi.tions:and Required Actions entered in accordance wi.th, LCD '30,-2.
'LCO 3.08.8a applies when one or more snubbers are not capable of providing their associated support function(s) to a single train or subsystem of a multiple train or subsystem supported system..or to a single train or subsystem supported system. LCO 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring the supported system..inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function andidue to the availability of the redundant train. of the supported system.',
LCO 3.0.8.b applies when one or more snubbers are not capable of providing their associated support function(s) to more than one train or subsystem of a multiple train or subsystem supported system. LC 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the supported
-system inoperable.:. The,12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.Completion Time is reasonable based on the low probability of a seismic event concurrent with-an event that would require operation of (continued)
PALO VERýE UNITS 1,2,3 B 3.0-14 REVISION 49 IL
LCO Applicability B 3.0 BASES LCO 3.0.8 -the supported system occurring while the snubber(s) are (continued) not capable bof:performing their associated support function.
. LCD.3.0:8 requires-that risk be assessed and managed.
Industry and,,,NRC guidance oh the implementation of 10 CFR,50.65(a)(4)Y(the Maintenance 'Rule) does not address seismic risk.. However, use of LCO-3.'0.8-should be considered with respect to..other plant maintenance activities,.,and, integrated into the existing Maintenance Rule process* t6ý ,he extent possible so that maintenance on any., unaffected: train-;. or subsystem is properly controlled, and emergent issues are properly' addressed. The risk
,assessment-ieednot be, quanti.fied., but may be a qualitatiyetawarenesls of thbevulnerabilfty of systems and componentsI.whenone o,3r ,more,snubbers are not able to perform their assd6jat'ed s'u'Lport function.
In .orderl to utilizeLPO 3.Q,.8,. -the' restrrictions listed below shall 'be met. s',." :.
."1.. WhenLco 3.8is.used. '- Confifrm that at least one tr6ain -(or subsy t6te) of systems -supported by the non-functional snubber(s),.would remain capable of performing their required safety or support
-functions forpostulated design loads other than seismic loads. LCO 3.0.8 does not apply to non-seismi.c',,snubbers.
2, When LCO 3'.0*8 is used, a record .of the design function of the nonfunctional snubber(s) (i.e.,
seismic vs. :non-seismic). implementation of the
- applicable LCO 3.0.8' restrictions,, and the associated plant configuration shall be available on a recoverable basis for NRC inspection.
- 3. When LCO 3.0.8.ais used: at-,least one AFW train (including a minimum set of supporting equipment required for its successful operation) not associated with the non-functional snubber(s), must be available.
4., When LC0,3'0.8.b is used, at. least one AFW train (including a minimumset of supporting equipment
. required,for. its successful operation) not associated with the non-functional snubber(s), or some alternative means of. core cooling (e.g., fire water system or "aggressive secondary cooldown" using the steam generators) mustt.be available.
(continued)
PALO VERDE UNITS 1,2,3 B 3.0-15 RIEV.I SION,, 49
LCO Applicability B 3.0 BASES B 3.0 SURVEILLANCE.REQUIREMENT (SR) APPLICABILITY SRs-. SR,3..0.1 through SR" 30.4 establish the general requirements appl-icable to all Specifications'and apply at all times, unless otherwise stated.
SF .-3.0.1 SR-3.0.1 establishes the requirement that SRs must be met during the MODES! or other, speci fied conditions in the Applicability. forj which the uqi'r.ements of the LCO apply,
-.' unless otherwise specified i.n,,the :individual SRs. This SpecificatiOn is toensure tthat Surveillances are performed toverify the OPERABILITY..f- s0ystems and components, and that. variab!es* are. :withi.n.speci;f ed limits. Failure to meet a; Survei l-ance withirn the 'spec, fled Frequency, in accordance with SR .3.0;?.. consti'tutes.,a _aiure to meet an LCO.
.-Systems and comporents ýare.-assumred-tokbe OPERABLE when the
.asociated SRs haveýbeen ,met, othing in this
." Specifi(*ation, owvever., is., to be construed as implying that A
-'systems or componeri,:s. arc OPER BLE when:.
- a. The:systems or', components, are. known to be inoperable, although still meeting the SRs; or
- b. The requiremeints-of the Surveillance(s) are known to be not met between required Surveillance performances.
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the .associated LCO are not applicable, unless otherwise specified. The SRs associated with a Special Test*Exception (STE) are only applicable when the STE is used as an allowable exception to the requirements of a Specification.
Unplanned events may satisfy the requirements (including applicable acceptance criteria).-for a given SR. In this case, the unplanned:event, may.ýbe..credited as fulfilling the performance of the SR.. This. allowance includes those SRs whose performance is normally precluded in a given MODE or other specified condition, (continued)
.PALO.VERDE UNITS 1.2,3 B 3.0-16 REVISION 49
SR Applicability B 3.0 BASES SR 3.0.1 Surveillances, includifig Surveillances invoked by. Required (continued) . Actions, do not have to be performed on-inoperable equipment because theACTIONS define the remedial. measures that apply.
-Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status..... ...
Upon completion of maintenance, appropriate post maintenance testing is required to.declare,.equi pment OPERABLE. This incl'udes,.ensur-ing applicable.Survei1lances are not failed and thei'rý ?ost "recent-performance is,.4n accordance with SR 3.0.2. "Post'maintenance;.testing may not be possible in the current MODE or other.ýspecifiied, conditions in the Applicabiility.,due ,to thenecessary unitiparameters not having-been established.k In.these situations, the equipment may be ConrSidered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipments;snot...otherwise bel~ieved, to be incapable of
'performing its -function.i This wil -allow operation to
'proceed to a MODEor,,other specified~condition where other necessaryp'ost maintenancev'tests can be completed.
-Some examples ofthis.iprocess. are:
- a. Auxiliary Feedwater (AFW) pump turbine maintenance during refuel.ing-thatrequires testing at steam pressures >--800.,psi,. -However, if other appropriate testing is satisfactorily completed, the AFW System can be considered OPERABLE. This allows startup and other necessary testing to proceed until the plant reaches the steam pressure'required to perform the testing "..; . ,
- b. High Pressure Safety Injection (HPSI) maintenance during shutdown that requires system functional tests at a specified pressure. Provided other appropriate testing is satisfactorily completed, startup can
.proceed with HPSI considered OPERABLE. This allows operation to.reach the specified pressure to complete the necessary.post maintenance testing.
(continued)
PALO VERDE UNITS 1,2,3 B 3.0-17 .'REVISION',49
SR Applicability B 3.0 BASES SR 3. 0..2 SR 3.0.2 establishes the, requirements for meeting the.
specified Frequency. for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..."
interval. .
SR 3.0.2-permits a 25% extension of the interval specified.
in. the Frequency. -This, extension facilitates Surveillance
- scheduling and considers plant .operating conditions that may
- .not be suitable for'conducting .;the' Surveillance (e.g.,
transient ,conditiions or. .other., onggoi ng Surveillance or maintenance activities).., "
T.The 25% extens~ion -does not .signi.idantly degrade the i.." reliability that results fr'om peforming the Surveillance at most :reQuency.
its specified. ,this'Isanyparticular
'based on the recogni ti on Surveillance
.,that.the probable resultof' being performed0is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the, interval.specified in the Frequency doesr!ot apply.,, TheSe exceptions are stated in the iindividual Specificatiqons., An example of where SR 3.0.2 does not apply is the Containment.I"eak' Rate Testing Program.
As'stated in SR3.0.2, the:25% extension also does not apply to the initial portion of.a periodic Completion Time that requires performance~on a"once.per... basis. The 25%
extension applies'.to-each'performance after the initial
'performance. The. initial performance of the Required Action. whether'it i"s a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time.':, One reason for not allowing the 25%
extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status.of redundant or diverse components or accompl.ishes the function of the inoperable equipment in an
,alternative manner.
(continued)
- PALO .VER,.E UNITS 1,2,3 B 3.0-18 REVISION 49
SR Applicability B 3.0 BASES SR 3.0.2' Te*iprovisions of SR 3.0.2 are.not intended to be used K (continued) repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) o:r periodic Completion Time intervals beyond those specified.
SR 3.0.3 S'R3.0.3 establishes the flexibility todefer declaring affected equipment inoperable or ari'affected variable
.outside.'the' specified limits when a Surveillance has not been completed within the specifieo Frequency. A delay period of up to 24'hours or~up to the limit of the specified Frequency, ,whicheveris greater, applies from the point in time that it,,is-discovered thiat the, Surveillance has not been. perfdrmeýd in' acc6r.dance with SR 3.0.2, and not at the
. time thatthe,,speci,'fted Frequency wasnot met. Reference Bases2Section 3 fordiscussion b*O.2 and applicability of Frequency.1and*25%ext~nsion.. .
-This S 1 delay 'period-proovid.s ,1n adequate' time to complete Surveillances.that,6h6v' been missed .- This delay period permits -the tompleti on"of a Surveillance before complying with Required Actionsor'other remedial-measures that might preclude completion,.of the.Surveillance.
The basi's f6r this.deiay period includes consideration of unit conditions. adequate~planningl availability of personnel-the time required to perform the Surveillance,
.the safety significance of the delayincompleting the required Surveillance, and the recognition that the most probable. result ofany particular Surveillance being performed is!.the. erification-of conformance with the requirements... .
When a Surveillance with a Frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading, or in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance. However, since there is not a time interval (continued)
PALO VERDE UNITS 1.2.3 - B 3.0-19 'REVISIONi-49
SR Applicability B 3.0 BASES SR 3.0.3" specified, the missed Surveillance should be performed at (continued), the first reasonable opportunity.
SR,3,,.0,3 provides a time limit for, and allowances for the
,perfor ance of,,Surveillances~that become applicable as a consequence of.-MODE changes imposed by Required Actions.
Failure to comply with specified. Frequencies for SRs is expected.to be an infrequent by SR 3.0,3, occurrence.
jis. a -fleibility Use ofwhich the delay is not period established intended to be used as an operational convenience to extend
!SurveillTance intervals. jWhile,!.ip to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified Frequency. is provided to perform the missed Surveillance, ,it.isexpected thatthe missed Surveillance will be performed at the firs reasonable opportunity. The determinatior-of the-first reasonable opportunity should include consideration of the impact on plant risk (from
,;delaying the Surveill.ance as well as any plant configuration changes.requtired,.cr,shuttingthe plant down to perform the Surveillance),and'.impact or any ana1ysis assumptions, in addition to unit. conditions, planning,'availability of personnel-,- nd t.he, time required to perform the Surveillance.,-This risk-:impact-'should be managed through the program nplaceto implement 10 CFR 50.65(a)(4) and its implementation guidance, NRCiRegulatoryGuide 1,182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." This Regulatory Guide addresses consideration of temporary and:aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The
- .missed Surveillance should be treated as an emergent condition as discussed in the: Regulatdry Guide. The risk evaluation may use quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the .importance of the component.
Missed Surveillances for important.components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this eval.uation should be used to-determine the safest course of action. All missed,Surve'llances will'be placed in the licensee's Corrective Action Program.
(continued)
ýPALO VERDE UNITS 1,2,3 - 3.0-20 REVISION.49
- .' . ..-. . '* -*. . .. : . *. . . . .'.. . . . ". q..
SR Applicability B 3.0 BASES SR 3:0.3 If': aSurveillance is riot completed within the allowed del.ay (conti nued) period,, then the-;equ.ipnent 'is-considered inoperable-or the variable is considered outside the specified limits and the Completion Times of'tho Required Acti:ons for the applicable LCO Conditions begin' iimiediateiy upon, expi ration of the delay period. - If'a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified1limits =:and the Completion Times of the Required'Actions'.for the applicable LCO Conditions begin immediately upon the failure of the Surveillance.
completi~on "of. the Survei lance: wiithi n the delay period al Iowed" byi th,! s Spec.ficati:n,, or within the Completion Time of the AC-TIONS;:.,r~estores.compliance with SR 3.0.1.
SR_ 3.0.4 SR:3.0-8.4 ;e`stalbli.sh[S :the'requirfement:that all applicable SRs must ýbe mei befo)re 'entryt.irMto :a MODE- or other speci fied
. Condition'i'n the.Applicability. ."
This Specification:*ensures,that system and component OPERABILITY requi remients and variable limits are met before entry-into '.MODES or other ýpecified conditions in the Applicability for which'ithese systems and components ensure safe operatiohnof'the'"unit.
The provisions of this'Specification should not be interpreted as endorsing the failure toexercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in'the Applicability.,
A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to a Surveillance not being met in accordance with LCO 3.0.4.'
However6;,"incertain'circumstances; failing to meet an SR will not'resultin.SR.3.024 restricting a MODE change or other specified condition change. When a system. subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1. which states that surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the (continued)
PALO VERDE UNITS 1,2,3 B 3.0-21 :REVISION 49
SR Applicability B 3.0 BASES SR 3.0.4 SR(s.) to be performed'is removed. Therefore, failing to (continued) perform the Surveillance(s) within the specified Frequency does not result in an SR 3..0:4 restriction to changing MODES or:other specified conditions of the Applicability.
However, sincethe LCOjis not~met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.
SR 3.0.4 does not restrict changing MODES or other specified conditions .of- the Applicability when a
- Surveillance-has not-been performed within the specified Frequency, provided the,)requirementto declare theLCO not met has been delayed~inýaccordancewith SR 3.0.3.
The provisions of SR 3.0.4 shall not prevent changes in MODES or other specified conditions.in the Applicability that are required to comply with ACTIONS. In addition, the
- provisions.ofSR. 3:-.4 'shalloot~preveht changes in MODES or other specifiedcndciditionis' in *the Applicability that result from any unit shutdown.
-In this context,"a.unit'shUtdown is defined as a change in MODE or other specified dondition in the Applicability associated with transitioning from MODE I to MODE 2, MODE 2 Sto MODE 3, MODE 3 to MODE, 4, and MODE 4 to MODE 5.
The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary.. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the:MODE or other specified condition in the Applicability of the associated,LCO prior to the performance or completion of a Surveillance;.' A Surveillance that could not be performed until 'after-entering the LCO Applicability, would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition,,or time has been reached. Further discussion of the specific formats.of SRs' annotation is found in Section 1.4, Frequency.
PALO VERDE UNITS 1,2,3 B 3.0-22 REVISION 49
CEA Alignment B 3.1.5 BASES ACTIONS A.I and A.2 (continued)
In both, cases, a,2 hourtime period is ssufficient to:,
.a."identify causeof a misaligned.CEA-'
- b. Take appropriate corrective actibn.to realign the
.CEAs: and
- c. Minimize the effects of xenon redistribution.
The CEA must be6.returnedto:- OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
if a:CEAmisagnmentresults-in the COLSS programs being
..declared'lNOPER
' BLE, refer:tc Section 3.2 Power Distribution Limits --for appli cabl e. acti ons,'
B. and, B. . ...
At-.ileast.two`of the fobll wing three CEA position indicator
" channels.shall.be
," OPERABLEfor eich.CEA:
- a. CEA Reed"Switch Position Transmitter (RSPT 1)
,,,with the capability of determining the absolute "CEA positions within 5.2 inches,
- b. CEA Redd Switch. Position Transmitter (RSPT 2)
Swith the capabi-lity of determining the absolute CEA positions within 5.2 inches, and
- c. The: CEA1 pulse-counting position indicator channel.,,,
If only one CEA position indicator channel is OPERABLE for one CEA per CEA Group,. continued operation in MODES 1 and 2 may continue. provided, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, at least two position indicator-channels are returned to OPERABLE status; or within.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and' once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify that the CEA roup with the inoperable position indicators are either ullywithdrawn or fully inserted while maintaining the ins'ertion limits of,LCO 3.1.6, LCO 3.1.7 and LCO 3.1.8.
CEAs are fully withdrawn when the requirements of LCO 3.1.6
. and 3.1.:7 are met.
Additionally,"the Upper Electrical Limit (UEL) CEA reed switches provide an acceptable indication of CEA position for a fully withdrawn,condition.
(continued)
PALO VERDE UNITS 1,2,3 B 3.1.5-7 REVISION 49
CEA Alignment B 3.1.5 BASES ACTIONS C.1 or zssociated.Completion Timeor ofmore Condition A or Action If a, ReQuired Condition B is not.met..'.or if one regulating or.shutdown CEAs are untrlppable (immovable as a result of excessive friction.or. mechanical, interference or knowvn to be untrippable), the unit.is required to be brought to MODE 3. By. being brought to. MODE 3 .'the unit is brought outside i.ts MODE of applicabifl:ity When a RequAired Action cannot be completed within the required Com letion Time, 6 coni,,olled shutdown should be commenced.: The-"a 1owed.Co.mpletion Time-of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, for reaching MODE 3 from full power conditions,.in an orderly manner and
- without challenging plant systems.
If a full strength CEA is untri~ppable, it is not available for..reactivity- inserti*n during,a reactor.trip. With an untrippable CEA,.'. meetjir t, e!i inserti on limits of LCO 3.1.6.
-.'Shutdo~; ControlEiEcmenti:Asebly '(EA) Insertion Limits,"
and LCO 3.1.7, .7'Regulating Control .Element Assembly (CEA)
.,Insertion Limit.s," does not ensure that adequate SOM exists.
Therefore, the pl:ant:. must'be shut down in order to evaluate the SDM required boron concentration and power level for critical operation. Continued operation is allowed with untrippable part length. or part strength CEAs if the alignment and insertion limits are met.'
Continued operationis not allowed with one or more full length CEAs untrippable. This is because these cases are indicative of.a loss of-SDM and'"power distribution, and a loss of safety function, respectively.
D.1 Continued operation is not allowed 'inthe case of more than one.CEA:,misaligned from any other CEA in its group by
> 9.9 inches. For example, t1,4o,.CEAs in a group misaligned' from any other CEA in that grou.6y:> 9.9. inches, or more than one CEA group that~has a least one CEA misaligned from any. other CEA in that group by >.9.9,inches. This is indicative of a loss of power distribution and a loss of safety-function, respectively. ,Multiple CEA misalignments should resultin automatic protective action. Therefore, with two or more CEAs misalignedmore than 9.9 inches, this (continued)
PALO VERDE UNITS 1,2,3 B 3.1,.5-8 REVISIION. 46
~ -~-'
RCS Loops - MODE 4 B 3.4.6 BASES LCO Note 2.requires, that before an RCP may be started with any (continued) RCS cold,leg temperature
- 214°F during cooldown, or
- 291'F during heatUpi that secondary side.water temperature (saturation "temperature corresponding'to SG pressure) in each SG is <'1000 F above each of the RCS cold leg tem,peratures. The'numerical Values. forRCS cold leg temperatureat which'this Note is'applicable do not account for all instrument uncertainty.: .Use of an indicated value of 2171F or below during cooldown and 294 0 F or below during h6eatupensures that the actual1 Jlmits will not be exceeded.
'These valO6siwhich.inclUde appropriate instrument uncertainty.'ar'-establishediwithin the applicable plant procedu'es; I Satisfying'the .above'condition will, preclude a large pressure surge in the RCS when the RCP is.started.
Note- 3rest icts RCPý -0atlion to no more! than 2 RCPs with RCS' cold; eg; temperaturel,5 200F.,'and-no more than 3 RCPs with RCS coldleg trmperatdre >200 0 Fbut,*5 500OF.
Satisfying theseconditibons will maintain the analysis assumptions ,Of the flow lnduced pressure correction factors due to RCP operation (Ref.j1)
An OPERABLE:RCS 'loop consists of at least one OPERABLE RCP and an SG that is OPERABLE and has the minimum water level specified in SR 3.4.6:2.'
Similarly, for the SDC System, anl OPERABLE SDC train is composed of-an OPERABLE. SDC pump 1(LPSi) capable of providing flow to the SDC heat exchanger for heat removal. RCPs and I
SDC pumps are ,OPERABLE if they are capable of being powered and are able to provide flow, if required.
APPLICABILITY In MODE 4;`this LCO 'applies because it.is possible to remove core decay-heat and to provide proper boron mixing with either-,fhe RCS loops and SGs or the SDC System.
Operation.in other MODES is covered by:
LCO 3.4.4 "RCS Loops-MODES 1 and 2";
LCO 3.4.5, "RCS Loops - MODE 3";
(continued)
PALO VERDE UNITS 1.2,3 B 3.4.6-3 'REVISION 49
RCS Loops - MODE 4 B 3.4.6 BASES APPLICABILITY LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled";
(continued) LCO 3.4.8,"RCS Loops - MODE 5, Loops Not Filled":
LC LC-3.9..4, "Shutdown Cool-ing (SDC) and-Coolant Circulation - High Water Level" (MODE 6); and LCO 3'95 rShutdown Cooling (SDC)and Coolant Cir-fCulation -rLowWater. Level" (MODE 6).
ACTI'ONS X. 1 If only one requ red kC§' lo i s OPERABLE and imn oeration, redundancity iorhedat is bse tre stov&r Action must be Initiated immedi aely to restoreCa.second.loop to OPERABLE status. The *edi abteýColet a Tile reflects the of.' .*"ing"aa hieitaait*o i.i.portancej t of two paths for deca., heat removal'"
Eb. ' ".
If only one required SDC train is OPERABLE and in operation, redundancy, for heat. removal :is:lost. The plant must be
.placed in MODE 5 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Placing the plant in MODE 5 is a conservative action with regard to
... decay heat removai. Wi.th.-only one SDC train OPERABLE, redundancy for decay heat removal is lost and, in the event of a loss of the remaining SDC train, it would be safer to initiate that0 lossfrom MODE..5_(* 210°F),rather than MODE 4 (210°F to 350 F). The Completion<Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is
,reasonable, based on operating experience, to reach MODE 5
.from MODE 4, with only one SDC train operating, in an orderly manner and without challenging plant systems.
C.1 and C.2 If no RCS loops or SDC trains"are.OPERABLE. or in operation, all operations. involving reduction of RCS boron concentration must be suspended and action to restore one RCS loop or SDC train to OPERABLE status'and operation must be initiated.
Boron dilution requires forced circulation for proper mixing, and the margin to criticality must not be reduced in this type of operation. The immediate'Completion Times reflect the importance of decay heat removal. The action to restore must continue until one loop or train is restored to operation.
(continued)
PA VERDE UNITS 1,2,3 B 3.4.6-4 REVISION 6
.'. Containment
" '
- 8 3.6.1 B 3.6 CONTAINMENT SYSTEMS B 3.6.1 Containment" BASES . ' .
BACKGROUND The containment consists of the concrete Containment Building (CB).* i*ts steel, liner. and the"penetrations through
..this structure; The structur6 is designed to contain
.radioacti~ve material -that may, be,.released. from the reacZt.or.
core following a design basis Loss of Coolant Accident.
Additionally, this structure provides shielding from the.,
fi ssionr4products,. that may.be.present in the containment atmospherbeý-followi g acc.identtconditions.
The conta[inrdnt.,1s-, ai , ýýieiforced concrete *tructure with a cyl i ndri cAl. wal,1 a_- lat f,oiundation mat,_ .and a shallow dome roof. The 'cylinder 'w'all,',isf'.prestressed with a post tensioning system in the vertical-andhOrizontal directions, and the dome roof is prestressed utilizing a two way pattern of tendons, which are an extension of the continuous vertical tendons. The inside surface of the containment is l*ined withi a-carbon., steelýliner to ensure a high degree of
" leak tightness during operating and accident conditions.
.. .The cdncreteCB is required for structural integrity of the containment underiDesign. Basi.s Accident (DBA) conditions.
The steel liner and'itspenetrations establish the leakage limiting boundary of~the containment. Maintaining the.
containmentOPERABLE limits the leakage of fission product radioactivity from the containment to the environment.
SR 3.6.11' leakage rate requirements comply with 10 CFR 50.
Appendix-J, Option B (Ref. 1), as modified by approved exemptions.
The isolation devices for the penetrations in the containment boundary are a part of the'containment leak tight barrier. To maintain this leak tight barrier:
- a. A'I*'penetrations .required to be closed during accident conditions, are either:.
- 1. capable -of being. closed by an OPERABLE automatic containment isolation system, or
.(continued)
PALO VERDE UNITS 1.2,3 B 3.6.1-1
-. REVISION 0
Containment B 3.6.1 BASES (continued)
BACKGROUND 2. closed by manual valves, blind'flanges, or (continued) de-activated automatic valves secured in their closed positions, except as provided in LCO 3.6.3, "Containment. Isolation Valves",
b-. Each aair lock is OPERABLE : , except as provided in LC 3..6.2., "Containment"Air Locks"; ;and
- c. All equipment hatche6s are closed.
APPLICABLE The safetytdesignbaIsorhe Lointainment is that the SAFETY ANALYSES Containmentmust withstand the pi'essures and temperatures of
- ,,the limiting OBA.without exceeding the design leakage rate.
I ..The llimtilng..DBAS. that,;*resufit in a largerelease of radi oacti ve mate'ri a , wi thir conti n e'nt are a Loss Of Coolant Accident (LOCA). a Main'"Steam"Line Break (MSLB), a feedwater lineib 1'eak, and a.con&61_ol.element assembly Jn ejectJion, accident ef.2),<Ththe(anaiysis of each of these .accidents,, it. Is'assumedbithat containment is OPERABLE
,.such that. rel ease oftissionproducts to. the environment is controlled by the rate of 'containment leakage. The containment was desi.1gned with'an allowable leakage rate of 0.1% of containment'ai.r mass per day (Ref. 3). This leakage rate is defined in"10 CFR 50, Appendix J', Option B (Ref. 1),
.. as La: the maximum allowable containment leakage rate at the. calculated maximum. peak' contai'nment pressure (Pa) of 52.0 psig for units 1-and 3,_58.0.psig 'for unit 2, which results from the limiting desigon basis LOCA.
- Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY.
The containment satisfies Criterion 3 of 10 CFR 50.36 (c)(2)(ii).
LCO Containment OPERABILITY is maintained by limiting leakage to
_*1.0 La, except prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test. At this time, the applicable leakage limits must be met.
(continued)
PAEO VERDE UNITS 1,2,3 B 3.6.1-2 ,,,
REVISION 49
Containment Air Locks B 3.6.2 B 3.6 CONTAINMENT SYSTEMS B 3.6.2 Containment.Air Locks...
- BASES ' ' "..
BACKGROUND Containment-air locks form part 6f the containment pressure boundary and provide a'means- for personnel access during all MODES of.. operation.
Each air lock is nominally a right circular cylinder.
9ft.-6 inches in diameter.-with-a door-at each end.". The-doors are interlocked.to prevent simultaneous opening.-.
Duringpe.rids When containment'is not 'required to be OPERABLE, `th' door, interlock mechanism may be disabled-,
'allowing 1bbthdoorS "of anIa'ir' lock to remain open for extended periods .vhen frequent containment entry is necessary,: ,,Ea ch air":'l-ck door'has beendesigned and tested
.to certify._its abill].ty',to wi.thstand -a' pressure in excess of the 'maximum' expect'ddpressure followiig a Design Basis Accident! (DBA)- in cpotainment., As,'such, closure of a single door suppoorts_ contalhm~nt OPERABILITY, Each of the doors containsdo~uble gasketed seals and local leakage rate testing capability to ýensurepressure integrity. To effect a leak tight seal,, the air lock' design uses pressure seated doors (-i.e., an increase in containme'nt internal pressure results in increased:.seali.ng'force-on each door).
The containm6nt air "locks form part of -the containment pressure boundary. As such, air,lock -integrity and leak tightness, is. essential for ma intaining the containment leakage ratewithin limit in the event'of a DBA. Not maintaining air lock integrity or leak tightness may result in.a leakage, rate in excess of that assumed in the unit safety 'analysis.
-p.. .
... . .. .... .. . . . .. ... .. -(continued )
PALO VERDE UNITS 1.2.3 .9 8.6.2-1 ý'_.REVISION 45
Containment Air Locks B 3.6.2 BASES (continued)
I APPLICABLE SAFETY ANALYSES The limiting DBAs that ,result in a large release of radioactive:material withincontainment are a Loss Of "CoolantAccident (LOCA), a, Maain Steam Line Break (MSLB), a feedwater line break, and a control element assembly (CEA) ejection accident (Ref., 2)....Iri the analysis of each of these accidents, it is assumed-:that.containment is OPERABLE such that release. offission produLcts to the environment isý controlled by the rate.of containment leakage. The containment was designed with an allowable leakage rate of 0.1% of containment airmass:-per day (Ref. 3). This leakage 'rate, is defined in 1I CFR 50, Appendix J, Option B,
- as the maximum ,allowable containment leakage rate at the calculated peak;cont-ainment.interhnal pressure P, [52.0 psig 3876,.M/Wt 58.0 psig RTP, and design for unit
- for "operating-at 3990 MWtat RTP]':
units operating f,]l:;jng'a basis LOCA.
This allowable- leakage' rate., forms- the ba.si s for the acceptance criteriaimposed:onthe SRs associated with the air lock "
The containment air locks satisfy Criterion 3 of 10 CFR 50.36 (c)(2,)(ii)*
LCO Each containment air lock forms part of the containment pressure boundary. ,As~part of the containment pressure boundary, the air lock safety function *isrelated to control of the containment leakage rate resulting from a DBA. Thus, each air lock's structural integrity and leak tightness are essential to the successful.mitigation of such an event.
Each air, lock is required to be OPERABLE. For the air lock to, be considered OPERABLE, the air lock interlock mechanism must be OPERABLE, the air'lock must be in compliance with the Type.,Bair lock leakage'test, and both air lock doors must be OPERABLE. The interlock allows only one air lock door of an air, lock to be opened at one time. This provision ensures that a.gross.hreach of containment does not exist when containment is; required to be OPERABLE.
Closure of a single door in each, air lock is sufficient to rovide a leak tight barrier following postulated events.
evertheless., both doors are kept closed when the air lock is not being' used for nbrmal, entry .into or exit from containment.
(continued)
PALO. VERDE -UNIT-S, 1,-2,33 B 3.6.2-2 REVISION 49
Containment Isolation Valves B 3.6.3 BASES APPLICABLE The containment'isolation valve LCO was derived from- the SAFETY ANALYSES assumptions related.to minimizing the loss of reactor coolant "inventory.and establishing.ýthe containment boundary
-during majoraccidents:. As part of the containment boundary, contaihment isolation valve OPERABILITY supports leak'tightness of:the containment.> Therefore, the safety analysis of :any event requiring isolation of containment is applicableL-;to this LCO.
The DBAS 'thait result.in 'a release of radioactive material wi thin containment* are documented in UFSAR Chapters 6 and 15.
In theb'anahlysis: for each,.of'.these'accidents, it is assumed I
that cont ainment'i solationu.valves are either closed or fuhcti6nrtd. cliose within" the required isolation time following,:event. irtiatioin; This ensures that potential paths'-to..!'the enlvironriepnt thrbugh containment isolation valves
-(ncluding 'containment :purge valves) are: minimized. The safety analysis assumes that the-refueling purge valves are closed at event initiation.
The DBA analysis assumie's that,. withfin 60 seconds after the accident, isolation except-.for-the leakage terminated of the containment is completerate, design-leakage and L,.
The power access purge' valves are assumed to close.within 12 seconds of.-the DBA. The 'cOntainment isolation response ti.me S .includes signal delay,. diesel generator startup (for loss of
- offsite power),.ando-containment isolation, valve stroke times.
The~single failure criterionrequired to be imposed in the conductof,'*nit safety analyses was considered in the original design of the containment purge valves. Two valves in series' on each purge line provide assurance that both the supply and exhaust lines could be isolated even if a single failure occurred. The inboard and outboard isolation valves on each line, are provided with diverse power sources.
The refueling purge valves may be unable to close in the environment' following a LOCA. Therefore, each of the refuel'ing purge valves is required to remain sealed closed duringMODES 1. 2,.3, and 4 or the flow paths of the refueling purge valves are required to be isolated with blind remainsflanges..-
I applicableIn-this' to thecase, 'the single failure criterion containment refueling purge valves due to failure in the control circuit associated with each valve. Again, the purge system valve design precludes a single failure from compromising the containment boundary as long as the system is operated in accordance with the subject LCO.
(continued)
PALO VERDE UNITS 1,2,3 B 3.6.3-3 REVISION 49
Containment Isolation Valves B3.6.3 BASES APPLICABLE The power access purge valves are capable of closing under SAFETY ANALYSES accident conditions. Therefore, they are allowed to be open (continued) for limited periods during power operation.
The OPERABILITY of main steam safety valves, main steam isolation valves, main feedwater isolation valves, and main steam atmospheric dump valves is covered by Specifications 3.7.1, 3.7.2, 3.7.3 and 3.7.4 respectively.
The containment isolation valves satisfy Criterion 3 of 10 CFR 50.36 (c)(2)(ii).
LCO Required containment.isolation valves, (CIVs) form a part'of the containment boundary. A containment penetration is considered to be the area bounded by the inboard and outboard CIVs and includes all valves, piping, and connections within this boundary (e.g., vents, drains, and test connections)
(Ref. 7). The containment isolation valve safety function is related to minimizing the loss of reactor coolant inventory and establishing the containment boundary during a DBA. The automatic power operated isolation valves are required to have isolation times within limits and to actuate on an automatic isolation signal. The refueling purge valves must be maintained sealed closed. All manual vent, drain, and test valves within a Containment Penetration (i.e., between the Containment Isolation Valves) will be maintained locked closed per the locked valve administrative program or surveilled closed per Technical Specification SR 3.6.3.3 or SR 3.6.3.4.
The valves covered by this LCO are listed with their associated stroke times in the UFSAR (Ref. 1). The analyses assume the containment is isolated within 60 seconds following an isolation signal (CIAS).
All containment isolation valves are considered to be required except for each 42 inch refueling purge valve when its flow path is isolated with a blind flange tested in accordance with SR 3.6.1.1 as allowed by Note 5 under LCO 3.6.3. This is allowed because the blind flange, instead of the valve, provides the function of the containment boundary.
Required CIVs are considered OPERABLE for LCO 3.6.3 when they are closed (i.e., manual valves are closed, automatic valves are de-activated.and secured in their closed position), blind flanges are in place, and closed systems are intact. The Steam Generating System and the Containment.Pressure Monitoring System are the only credited closed systems at PVNGS. Placement of CIVs in this configuration may impact the operability of the associated system. If the required valve surveillances have lapsed for a CIV secured in its closed (continued)
PALO VERDE UNITS 1,2,3 B 3.6.3-4 REVISION 43