ML061380540

Technical Specifications Bases Revision 37 Update

ML061380540
Person / Time
Site:	Palo Verde
Issue date:	05/11/2006
From:	Bauer S Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05491-SAB/TNW/RKR
Download: ML061380540 (34)

Text

Technical Specification 5.5.14 LAMP A subsidiaryofPnacle West CapitalCerporafion Scott A. Bauer Department Leader, Regulatory Affairs Tel. 623-393-5978 Mail Station 7636 Palo Verde Nuclear Fax 623-393-5442 PO Box 52034 Generating Station e-mail: sbauer@apsccom Phoenix, Arizona 85072-2034 102-05491 -SAB/TNW/RKR May 11, 2006 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3 Docket Nos. STN 50-52815291530 Technical Specifications Bases Revision 37 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 37, implemented on April 19, 2006. The Revision 37 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, please contact Thomas N. Weber at (623) 393-5764.

Sincerely, SA SBTWtRKr SABITNW/RKR/gt

Enclosure:

PVNGS Technical Specification Bases Revision 37 Insertion Instructions and Replacement Pages cc: B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager G. G. Wamick NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak

• Diablo Canyon

• Palo Verde

• South Texas Project

• Wolf Creek ADC)l

ENCLOSURE PVNGS Technical Specification Bases Revision 37 Insertion Instructions and Replacement Pages

PVNGS Technical Specifications Bases Revision 37 Insertion Instructions Remove Paae: Insert New Page:

Cover page Cover page List of Effective Pages, List of Effective Pages, Pages 1/2 through Pages 1/2 through List of Effective Pages, List of Effective Pages, Page 7/8 Page 7/8 B 2.1.1-3/2.1.1-4 B 2.1.1-3/2.1.1-4 B 3.1.10-3/3.1.10-4 B 3.1.10-3/3.1.10-4 B 3.1.10-5/3.1.10-6 B 3.1.10-5/3.1.10-6 B 3.3.12-3/3.3.12-4 B 3.3.12-3/3.3.12-4 B 3.7.2-3/3.7.2-4 B 3.7.2-3/3.7.2-4 B 3.7.3-3/3.7.3-4 B 3.7.3-3/3.7.3-4 B 3.8.1-23/3.8.1-24 B 3.8.1-23/3.8.1-24 B 3.8.4-1/3.8.4-2 B 3.8.4-1/3.8.4-2 B 3.8.4-9/3.8.4-10 B 3.8.4-9/3.8.4-10 B 3.8.4-11/blank B 3.8.4-11/blank B 3.8.6-5/3.8.6-6 B 3.8.6-5/3.8.6-6 I

P VNGS Palo Verde Nuclear GeneratingStation Units 1, 2, and 3 Technical Specification Bases Revision 37 April 19, 2006 I

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B 3.8.4-3 0 B 3.8.1-9 27 B 3.8.4-4 2 B 3.8.1-10 2 B 3.8.4-5 2 B 3.8.1-11 2 B 3.8.4-6 2 B 3.8.1-12 2 I-B 3.8.4-7 35 B 3.8.1-13 2 7 B 3.8.4-8 35 B 3.8.1-14 2 I, B 3.8.4-9 35 B 3.8.1-15 2 B 3.8.4-10 37 B 3.8.1-16 20 B 3.8.4-11 37 B 3.8.1-17 20 B 3.8.5-1 1 B 3.8.1-18 20 k-B 3.8.5-2 1 B 3.8.1-19 20 B 3.8.5-3 21 B 3.8.1-20 20 B 3.8.5-4 21 B 3.8.1-21 20 B 3.8.5-5 2 B 3.8.1-22 20 B 3.8.5-6 2 B 3.8.1-23 37 B 3.8.6-1 0 B 3.8.1-24 37 B 3.8.6-2 0 B 3.8.1-25 20 B 3.8.6-3 0 B 3.8.1-26 20 B 3.8.6-4 6 B 3.8.1-27 35 B 3.8.6-5 37 B 3.8.1-28 35 B 3.8.6-6 37 B 3.8.1-29 35 B 3.8.6-7 0 B 3.8.1-30 35 B 3.8.7-1 0 B 3.8.1-31 35 B 3.8.7-2 0 B 3.8.1-32 35 B 3.8.7-3 0 B 3.8.1-33 35 B 3.8.7-4 0 B 3.8.1-34 35 B 3.8.8-1 1 B 3.8.1-35 35 B 3.8.8-2 1 B 3.8.1-36 35 B 3.8.8-3 21 B 3.8.1-37 35 B 3.8.8-4 21 B 3.8.1-38 35 B 3.8.8-5 1 B 3.8.1-39 35 B 3.8.9-1 34 B 3.8.1-40 35 B 3.8.9-2 0 B 3.8.1-41 35 B 3.8.9-3 0 B 3.8.1-42 35 B 3.8.9-4 0 B 3.8.1-43 35 B 3.8.9-5 0 B 3.8.1-44 35 B 3.8.9-6

• 0 B 3.8.2-1 0 B 3.8.9-7 0 B 3.8.2-2 0 B 3.8.9-8 0 B 3.8.2-3 0 - B 3.8.9-9 0 B 3.8.2-4 21 B 3.8.9-10 0 B 3.8.2-5 21 B 3.8.9-11 0 B 3.8.2-6 0 ..

B 3.8.10-1 0 B 3.8.3-1 0 B 3.8.10-2 21 B 3.8.3-2 B 3.8.10-3 0 B 3.8.3-3 34 CorreLcted B 3.8.10-4 0 B 3.8.3-4 0

-. w I . B 3.9.1-1

• 34 Corrected B 3.8.3-5 34 B 3.9.1-2 0 B 3.8.3-6 0 B 3.9.1-3 0 B 3.8.3-7 0 B 3.9.1-4 0 I -

B 3.8.3-8 0 B 3.9.2-1 15 PALO VERDE UNITS 1, 2, AND 3 Ec G.1 ", I Revision 37 April 19, 2006

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev. Page Rev No. . . No. . . . No. No.

B 3.9.2-2 15 - ..

B 3.9.2-3 15 B 3.9.2-4 1518 .i ; j I ,i .- I , i

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B 3.9.3-1 ' 18' B 3.9.3-2 19 B 3.9.3-3 27 B 3.9.3-4 19 B 3.9.3-5z' I' 19 f- &'*

B.3.9.3-6 .19 B 3.9.4-1

• 0. 1 B 3.9.4-2 1 B 3.9.4-3 .0 B 3.9.4-4 0 B 3.9.5-1 0 B 3.9.5-2 16 B 3.9.5-3 27 B 3.9.5-4 - 16 B .3.9.5-5 I -16 B 3.9.6-1 0 B 3.9.6L-2 - I' j' B 3.9.6-3 B 3.9.7-1 .- 0 O B 3.9.7-2 ---0 B 3.9.7-3 0 i -

I  : " . I I I - r.

t V , .. , , i ,

A . . I VER DE UNITS 12,ND  :  ; ,. ,.

PALO VERDE UNITS 1, 2, AND 3 8 .

- Revision 37 April 19, 2006

Reactor Core SLs B 2.1.1 BASES APPLICABLE h. Log Power Level - High trip:

SAFETY ANALYSES (continued) i.- 'Reactor Coolant Flow - Low trip; and j;. Steam Generator Safety Valves. -

The limitation that the average enthalpy in the hot leg be less than or equal to the enthalpy of saturated liquid also ensures that the AT measured by instrumentation used in the protection system design as a measure of the core power is proportional to core power.:

The SL-represents a design requirement for establishing the protection system trip setpoints identified previously.

LCO 3.2.1, "Linear Heat Rate (LHR) " and LCO 3.2.4, "Departure From Nucleate Boiling Ratio (DNBR)," or the assumed initial conditions of the safety analyses (as indicated in the UFSAR, Ref. 2) provide more restrictive limits to ensure that the SLs are not exceeded.

SAFETY LIMITS SL 2.1.1.1 and SL 2.1.1.2 ensure that the minimum DNBR is knot less than the safety analyses limit and that fuel centerline temperature remains below melting.

The minimum value of the DNBR during normal operation and design basis AOOs is limited to 1.34, based on a statistical I combination of CE-1 CHF correlation and engineering factor uncertainties, and is established as an SL. Additional factors such :as rod bow and spacer grid-size and placement will determine the limiting safety system-settings required to ensure that the SL is maintained. Maintaining the dynamically adjusted peak LHR to s 21 kW/ft or peak fuel centerline temperature < 50800 F (decreasing by 58 F per

-10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A), ensures that fuel centerline melt will not occur during normal operating conditions or design AOOs.

The design melting point of new fuel with:no burnable poison is 50800 F. The melting point is adjusted downward from this temperature depending on the amount of burnup and amount and type of burnable poison in the fuel. The 580F per 10,000 MWD/MTU adjustment for burnup was accepted by the NRC in I I II Z 1 717 1 1 1 (continued)

PALO VERDE UNITS 1,2,3 B 2.1.1-3 REVISION 37 C, - >e

Reactor Core SLs B 2.1.1 BASES --

t,, - _.~

SAFETY LIMITS Tdpical Report CEN-386-P-A. "Verification of the (continued) - Acceptability of a 1-PinBurnup'Limit'of 60 MWD/kgU for:

'Combustior Engi~neering'16x16 .PWR Fuel',"i August 1992.;

'!AdjusXvtments for burnable poisons-are established based on NRC-lapproved TopicalnReport CENPD-382-P-A. "Methodology for Core Designs Containing-Erbium Burnable Absorbers," August 1993.

,steady A state peak lfnear h 'raie of.-21 kW/ft has been established'd thbe ,(iri'ting.S$afety-System Setting to prevent fuel centerl ne mel ti,Ag ciudirg nor'mal s'teady state operation. Following 'design'basis anticipated operational occurrences, the tr'ansient linear' heat, rate may exceed 21

.'kW/ft provided'the f~el'centerline mrelit temperature is not

. 'exceeded..However, if the transiet 'linear heat rate does

'not exceed 21 kW/ft, then the fuel centerline melt temperature is also not exceeded."

APPLICABILITY SL 2.1.1.1 ahd SL 2.1.1.2 only apply in MODES 1 and 2 because these are the only MODES in which the reactor is critical. Automatic protection functions are required to be OPERABLE during'MODES 1 and 2 to ensure operation within the reactor core SLs. The steam generator safety valves or automatic protection actions serve to prevent RCS heatup to the reactor core SL conditions-or to initiate a reactor trip function, which forces the unit into MODE-3. Setpoints for the'reactor trip functions are specified'in LCO 3.3.1.

In MODES'3, 4, 5. and 6. Applicability is not required, since the reactor is not generating significant THERMAL POWER.

SAFETY LIIlIT The following violation responses are applicable to the VIOLATIONS reactor core SLs.

2.2.1 If SL 2.1.1.1 or SL 2.1.1.2 is violated,'the requirement to

..go to MODE 3 places the unit'in a MODE in which this SL is not applicable.  ;

The allowed Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> recognizes the importance of bringing the unit to a MODE where this SL is not applicable and reduces the probability of fuel damage.

.. . j..

(continued)

PALO VERDE UNITS 1,2,3 B_

2. 4 PAOVr R-U 1;BREVISION 21

STE-MODES 1 and 2 B 3.1.10 BASES APPLICABLE : The safety analys\isC(Ref,-:6) placfs limits on allowable--

SAFETY ANALYSES THERMAL POWER'durkingiPHYSICS TESTS-'andcfrequires that the LHR (continued) and the depa.rturetzfromnnucleite boiling:-;(DNB) parameter be maintained lwithin limits. The poweriplateau of < 85% RTP and the associ~ated;-trfip-setpointsare-required to ensure these limits are'inaintained.- -

The individual ,L.Cps goverripng.CEA group height, insertion and:a'll.'gmwentLtAS, t't't.'plap r-nadial~peaking factor, total'Ipte' r g.adial. Oeaki,'g'factor,-and Tq. preserve the

.. LHR Vllits.'CYAdd 't'ionaly. the LCOs governing Reactor 6oqlantCSystSi'(RC*) Af3Owre'actpr. inlet temperature (Tc.),

parmetetr liliits.. ..Theinitial c6ndition criteria for

.accidents sen$itiv6 to core power distribution are preserved by the'LHR and'DNB parameter limits. Thelcriteria for the loss of codlant'accident' (LOCA) are specified in

-10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors" (Ref. 7). The criteria for the loss of forced reactor

.1coolant flow accident are specified inReference 7.

Operation within the LHR limit preserves the LOCA criteria; operation within the DNB parameter limits preserves the loss of flow criteria.

' During PHYSICS TESTS, one or more-of the LCOs that normally reserve the LHR and DNB parameter limits may be suspended.

he results.of theaccident analysis are not adversely impacted, however, ifLHR and DNB parameters are verified to be within their limits while the LCOs are suspended.

Therefore, SRs are placed as necessary to' ensure that LHR and DNB parameters remain within limits during PHYSICS TESTS. Performance of these Surveillances allows PHYSICS TESTS to be conducted without decreasing the margin of safety.

PHYSICS TESTS include.measurement of core parameters or exercise of control components that affect process variables, VAmong the process variables involved are total

-planar radial peaking factor, total integrated radial I ,- ..

peaking factor, Tq. and ASI, which represent initial condition input. (power peaking) to.:the accident analysis.

"Also t involved are the shutdown.and regulating CEAs, which affect power peaking and are required for shutdown of the reactor.. The limits for these variables are specified for each fuel cycle in the COLR.

,- , i' '-

..A-y,1, I- '-'--h

`r i A (continued)

PALO VERDE UNITS 1,2,3 tI B . 1. 10 -3 REVISION 0

STE-MODES 1 and 2 B 3.1.10 BASES .

APPLICABLE PHYSICS TESTS meet the criteria for inclusion in the.

SAFETY ANALYSES Technical Specifications, since the component and process (continued) .,.-;variabi e.LUOs suspended during,,PHYSICS TESTS meet

, .,Critedial,2,. and.3of-,10:CFR 50.36 (c)(2)(i.

.'~.~.. :, i1 " -

LCO This LCO permits individual CEAs to be'positioned outside of their normal group heights and insertion limits during the performance of PHYSICS TESTS. suckh-a,s those required to:

a. Measure CEA worth;,

b. Determine the reactor stabilityjindex and damping factor under, xenon osci lIati-on conditions;

c. Determine power distributions for nonnormal CEA configurations;

d. Measure rod shadowing factors; and

e. Measure temperature and power coefficients.

Additionally, it permits the center CEA to be misaligned during PHYSICS TESTS required to, determine the isothermal' temperature coefficient (ITC), MTC, and power coefficient.

The requirements of LCO 3.1.4- LCO 3.1.5, LCO 3.1.6.

LCO 3.1.7,,.:LCO 3.1.8. LCO 3.2.2, LCO 3.2.3, LCO 3.2.5 and LCO 3.3.3, may be suspended during the performance of PHYSICS TESTS provided THERMAL POWER is restricted to test power plateau, whichshall not exceed 85X RTP and that a minimum amount of CEA worth is immediately,available for reactivity control.

APPLICABILITY This LCO is applicable inMODES 1 and 2 because the reactor must be critical at various THERMAL POWER'levels to perform the PHYSICS TESTS described in the LCO section. Limiting the test power plateau to *-85% RTP ensures that LHRs are maintained within acceptable limits.-

(continued)

PALO VERDE UNITS 1,2.3 B 3.1.10-4 f t REVISION 37

I-'

STE-MODES 1 and 2 B 3.1.10 BASES (continued)

ACTIONS A.1

• IfTHERMAL'POWER Llceeds'the'teflt`power plateau inMODE 1.

THERMAL POWER"n's'st-beo:redhed.to.restererthe additional thermal margin provided by the reduction. The 15 minute Completion Time-.ensures-that-prompt-action shall be taken to reduce THERMAL POWER to within acceptable limits.

r :*t s1Z -,?Jf iJ , . .C

t 8, 1" a'nd~i 2BLJc2 r If Required Action A. 1cannbt be completed within the required Completion Time, PHYSICS TESTS must be suspended

~withi~n 1;hourl.! All'olgL hour for suspending PHYSICS TESTS

'allows th6-bperator'Sufficient time to change any abnormal CEA configuration back to within the limits of LCO 3.1.5,

'LCO 3'.1,6, anhdLCG 3.1.7: Suspension' of PHYSICS TESTS exceptions requires restoration of each of the applicable LCOs to within specification.

SURVEILLANCE SR 3.1.10.1 REQUIREMENTS Verifying that THERMAL POWER is equal toior less than that allowed by the test power plateau, as specified in the PHYSICS TEST procedure and required by the safety analysis, ensures that adequate LHR and departure from nucleate boiling ratio margins are maintained while LCOs are suspended. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Frequency is sufficient, based upon the slow rate of power change and increased operational controls in place during PHYSICS TESTS. Monitoring LHR ensures that the limits are not exceeded.

SR 3.1.10.2 Verification of the position of each partially or fully withdrawn full strength; part length. or part strength CEA is necessary to ensure that the minimum negative reactivity requirements'for insertion onla trip arepreserved. A 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Frequency is sufficient for the operator to verify that each'CEA position is within the acceptance criteria, (continued)

PALO VERDE ;UNITS 1,2,3 - leB 3A.. 10-5

.1 .REVISION 37

BAE, j( STE-MODES 1 and 2 B 3.1.10 BASES (continued)

REFERENCES .1.. .10 CFR:50., Appendix:B..Section XI.

t2. -10,iCFR 50..59. r.i . -

3. Regulatory Guide 1.68. Revision 2, August 1978.

4. ANSI/ANS-19.6.1-1985. December 13.-1985.

5. ,-iUFSAR, Chapter 1 - ,,-l

6. UFSAR. Section 15.3.,

,7. ,10 CFR 50A46, -

I 4 - - I oI

. . I ...

I I I .

PALO VERDE UNITS 1,2.3 .",B - A .,,10-6

• I, I.f  ;.,

- -, I ." REVISION

~. 0

Boron Dilution Alarm System (BDAS)

B 3.3.12 BASES (continued)

ACTIONS A channel is inoperablo'wheni~t'd"esinot satisfy the OPERABILITY criteria for the channel's function. These criteria are outlined in-the'LCO section of the Bases.

• -. ~t A.1 With one required channel inoperable, Required Action A.1

-requires the RCS boron cOncentration to be determined immediately and at.the applicable monitoring Frequency specified in the COLRI 'The RCS boron concentration is determined by RCS sampling: The RCS sample should be from the hot leg if one or more Reactor Coolant Pumps (RCPs) are running or from the discharge of the operating pump providing shutdown-cooling f-low with no RCPs running. The monitoring Frequency specified in the COLR ensures that a decrease in the boron concentration during a boron dilution event will be detected. The boron concentration measurement and the OPERABLE BDAS channel provide alternate methods of detection of boron dilution with sufficient time for termination of the event before the reactor achieves criticality.

(continued)

PALO VERDE UNITS 1,2.3 1, B. 8.11 2-3 REVISIOV37

Boron Dilution Alarm System (BDAS)

B 3.3.12 BASES AC] FIONS, B. 18.

,continued)

With two required channels inoperable Required Action B.1

.-r: -quirestheRCS..

boron concentration to be determined by a r ndant,method immed.iate~yand at the monitoring Frequency specifiedvin the COLRE Theredundant method uses independent collectionand:analysis of two RCS samples. The

-RCS

. ampleshould be from ,the-!hot leg if one or more Reactor Coolant PumpsT .(RCPs),are4renniwgonrfrom the discharge of

.the operatingpump providing sshutdown cooling flow with no I RCPs running. The use.of intepenrdent collection and analysis of two RCS samples to monitor the RCS boron concentration'providesral ternate 4 indications of inadvertent boron dilution. This.wi,l l.,a~llow detection with sufficient time for termination-ofiboron dilution before the reactor achieves criticality. I C.1 Condition C is entered when the Required Actions and associated Completion Times of Condition A or B are not met.

If the Required Actions associated with these Conditions cannot be.completed within the required Completion Time, the neutron flux level monitoring function cannot be reliably performed. The absence of reliable neutron flux level monitoring makes it difficult to ensure SDM is maintained.

Required Action C.1o.therefore requires that all positive reactivity additions that are under operation control, such

• as boron dilution or Reactor Coolant System temperature changes, be halted immediately preserving SDM.

(continued)

PALO-VERDE UNITS 1,2.3 I " B 3-1.t 12-4 - ."r I: '., .' 11REVJ.5ON 37

MSIVs B 3.7.2 BASES I L ';

APPLICABLE main steam header downstream of the closed MSIVs in SAFETY ANALYSES the intact loops.

(continued)

b. A break outside ,of ontainment and-upstream from the

• "MSIVs'. This scenario'-is'-notta, containment

-pressurizatTln concern. The uncontrolled blowdown of

fiorethenW new steam,generator mustj;be prevented to

,limit th'e potentia-l foriuncohtrolled-RCS cooldown and

'positive :re:ac-tivity<'addition. Closure of the MSIVs Isolates th& break,'-and limits the-blowdown to a single steam generat'r.

c. A break downstream of the MSIVs. This type of break

'will be isolated by the closure of the MSIVs. Events

-suth as increased steam flow through the turbine or the steam bypass valves will also terminate on closure of the MSIVs.

d. A steam generator tube rupture. For this scenario, closure of the MSIVs isolates the affected steam generator from the intact steam generator. In addition to minimizing radiological releases. this enables the operator to maintain the pressure of the steam generator with the ruptured tube high enough to allow flow isolation while remaining below the MSSV setpoints, a necessary step toward isolating the flow through the rupture.

e. The MSIVs are also utilized'during other events such as a feedwater line break. These events are less limiting so far as MSIV OPERABILITY is concerned.

The MSIVs satisfy Criterion 3 of 10 CFR 50.36 (c)(2)(ii).

LCO This LCO requires that the MSIV in each of the four steam lines be OPERABLE. The MSIVs are considered OPERABLE when the isolation times are within limits, and they close on an isolation actuation signal. The MSIVs have redundant actuator trains. An MSIV is OPERABLE with one train of hydraulics unavailable to shut the valve. Only one OPERABLE MSIV is allowed to have an unavailable hydraulic train.

This LCO provides assurance that the MSIVs will perform their design safety function to mitigate the consequences of accidents that could result in offsite exposures comparable to the 10 CFR 100 (Ref. 4) limits.

- --.-. *-.--. (continued)

PALO VERDE UNITS 1,2,3 B4.7.2-3 . REVISIOW31

MSIVs B 3.7.2 BASES (continued) , ,. a .-

APPLICABILITY .The MSIVs-must be OPERABLE in MODE.1 and in MODES 2,.3 and-4 except when all MSIVs are closed and deactivated when there is significant mass and- energy in the RCS and steam l '.;generators. When-the NSIVs are closed,;they are already performing their safetyfunction..- -

--;InnMODESY5'and 6',the steam generators do not contain much

-.-- energy because tbeit temperature is below the boiling point

'of water;,therefore. the;MSIVs are not, required for isolation of potential!,high energy secondary system pipe breaks in these MODES.'a,.- ..

ACT IONS A.1 and A.2 With one MSIV inoperable in MODE 1, time is allowed to restore the component to OPERABLE status. Some repairs can be made to the MSIV-with the unit hot.--The 4-hour Completion Time is reasonable, considering the probability of an accidentoccurring during the time period that would require closure of the MSIVs.

The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is consistent with that normally allowed for containment isolation valves that isolate a closed system penetrating containment. These valves differ from other containment isolation valves in that the closed

'system provides an additional means for containment isolation.

(continued)

PALO VERDE UNITS 1,2,3 B 3.7.2-4 REVISION 1 37

~~~E.- -.1_ .- - - - - I . 'i

.i ......_. .....

_I........

MFIVs B 3.7.3 BASES (continued)

APPLICABILITY The MFIVs.must beOPERABLE whenever there is significant mass and energy imthe~Reactor Coolant.Sylstem and steam generators. *Thisdensures that,.in';the'event of an HELB, a single-failure cannot resuitiin the blowIown of more than one steam generatore:

In MODE&S 3a",--and-4, the.MFIVs. ar:required to be OPERABLE, except when theyfareclosedand deactivated or isolatedby a-deactivated andclosedipower operated valve, inv.order\to.limitrth§,amount of available fluid that could be added to containment.1'in the case of a~secondary system pipe break inside containment. When the valves are closed

...or-isolated by a closed power operated valve, they are already performing their safety function.

In MODES 5 and 6. steam generator energy is low. Therefore.

the.MFIVs ate not required.

ACTIONS The.ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each penetration flow path.

A.1 and A.2 With one MFIV inoperable, action must be taken to close or isolate the inoperable valves within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. When these valves are closed or isolated, they are performing their required safety function (e.g., to isolate the line).

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time takes into account the redundancy afforded by the remaining OPERABLE valves, and the low probability of an event-occurring during this time period that would require isolation of the MFW flow paths.

Inoperable MFIVs that are closed to comply with Required Action A.1 must be verified on a periodic basis to be closed. This is necessary to ensure that the assumptions in the safety analysis remain valid. The seven day completion time is responsible, based on engineering judgement, MFIV status indications available in the control room, and other administrative controls, to ensure these valves are in the closed position.

(continued)

PALOVERE .2, B 37.33 UNTS REISIN 3 PALO VERDE UNITS 1,2.3 B 3.7.3-3 REVISION 37

MFIVs B 3.7.3 BASES ACTIONS B.1 and B.2 (continued) - -' -

If more than ,one MFIV, ir~the same flow path cannot be","

restored 'to 'OPERABLE.statust.'then there may be no system to operate.,automatically and perform the required safety function.' Under these conditions',' valves-'in each flow path

. must-be restoted to OPERABLE status, closed, or the flow path isol ated -within 8 houa'rs.',Thisaction returns the system to the ,conditiop. where-At leastone.valve in each flow path is performing threquired 'safety function. The B hour Completion T.ime isreasonable to close an MFIV or otherwise isolate the affected'flow path..

Inoperable,MFIVs that cannot be restored to OPERABLE status within the.Comoiietion Time,.but are closed or isolated, must be verified on a perjodic basis tha they' are closed or

.isolated. This isnecessary-to' ensure that the assumptions

-in theisafety analysis remain' valid. The 7 day Completion Time is reasonable, based on engineering judgment, inview, of valve status indications available in the control room, and other administrative controls to ensure that these valves are closed or isolated.

C.1 and C.2 Ifthe MFIVs cannot be restored to OPERABLE status, closed, or isolated inthe associated C6mpletion-Time, the unit must be placed'in a'MODE inwhich the LCO does not apply. To achieve this status, the unit must be placed inat least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and inMODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions inan orderly manner and without challenging unit systems.

(continued)

PAL V ERD

. U 1 7.

PALO VERDE UNITS 1,2,3 B 3;7.3-4 REVISION 0

. ; 1~1. . . ', ; , A' . 1

i. AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7  :>.  :.

INI%4 Fnl ITDPMPMTq continued) These ,SRs hep 'tot 'hs6uirehe'avbifabil'ityof the standby

l ectrical :pow~er Vpplykr.-te`tigDateMD.BAs Ahd transients and to maintain the -irit' inCpsafe shtitdovin condition.

TQ .i niPi~t T ithe 1 e`2.r on,'t'o intg not get lr~ts'that'do

'lubri~dated'\herf'the i en i'e 'n6ldftrunnihg. these SRs are

' 'ibodf

• by,-a' Notb tb 'irid cate thal all DG' starts for these

'u.'rv ,i1l'ahce~s'Ta$b'kreceded'by afl engine prelube period

':'an .f Mow .y;a 'warm p p' riod prior to loading.

For the purposes.of SR 3.8.1.;2 and SR 3.8.1.7 testing, the DGs',arer Otarted from' standby condition.: Standby conditions fora DG mean that' the enginh lube oil and coolant

'temperatures, are maintained- consistent with manufacturer recommendations. Additionally, during standby conditions the.d esel'engine lube oil is circulated continuously and the engine coolant is circulated on and off via thermostatic control..

In order to reduce stress and wear on diesel engines. the DG manufacturer recommends a modified start in which the starting speed of DGs is limited, warmup is limited to this lower speed, and the DGs are gradually accelerated to synchronous, speed prior to loading. This is the intent of Note 3, which is only applicable when such modified start proceduresare recommendedby theimanufacturer.

I

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- . . . . At : - 0 - .

X . U ;Ko si Z - - .. ' ,. . ,, 1 ', '  :  :  ! - -

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(continued)

PALO VERDE UNITS 1,2,3 B 3.8.1-23 REVISION 37

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 (continued)' --

REQUIREMENTS SR 3.8.1.2 Note 4 and SR 3.8.1.7 Note 2 state that the steady state voltage and frequency'limits are analyzed valunes' ~and hde idt be'-i adjusted for instrument accuracy.

• The.analyzed.values for, the steady-state diesel generator voltage.il1mit' ore 2' 40Ob dnd'ds 4377.2 vi'olts and the the

's'fead#tat'diesel analyzed valhe's'fdr generator

-frequency linrv'ts are w.59:hand S'60.7 'hertz. The indicated steady'state 'diesel Oene'rat&r v6lt g-4andfrequency limits, using the.panel mounted"diese'lwgeneraforinstrumentation and adjusted fo'r'instrunMent error,' are'a 4080 and s 4300 volts (Ref. 12). and. 2 59.9'and_'.s60'.5Jhertz (Ref. 13).

respectively. Ifdigital.'Maintenance. 1andjTesting Equipment (M&TE) isused instead of the pqnel mounted diesel generator instrumentation, the ihstrument error'may'.be reduced increasing the range for the indicated steady state voltage and frequency limits.

SR 3.8.1.7 requires'that, at a 184 day Frequency, the DG starts from standby conditions with the engine at normal

'keep-warm conditions and achieves required voltage and frequency within 10 seconds,'and subsequently achieves steady state required.voltage and frequency ranges. The 10 second'start requirement supports the assumptions of the design basis LOCA analysis inthe'FSAR, Chapter 15 (Ref. 5).

A'-minimum voltage and frequency isspecified rather than an upper and a lower limit because a diesel engine acceleration at full fuel (such as during a fast start) is likely to "overshoot" the upperilimit initially and then go through several oscillations prior to a voltage and frequency within the stated upper and lower bounds. The time to reach "steady state" could exceed 10 seconds, and be cause to fail the SR. However, on an actual emergency start, the EDG would reach minimum voltage and frequency in* 10 seconds at which time itwould be loaded. Application of the load will dampen the oscillations. Therefore, only specifying the minimum voltage and frequency' (at which the EDG can accept load) demonstrates the necessary'capability of the EDG to satisfy safety requirements without including a potential for failing the Surveillance.

While reaching minimum voltage and frequency (at which the DG can accept load) in< 10 seconds is an immediate test of OPERABILITY, the ability of the governor and voltage regulator to achieve-steady state operation, and the time to do so are important indicators of continued OPERABILITY.

Therefore, the time to achieve steady state voltage and (continued)

PALO'VERDE UNITS 1,2,3 .11 W3'.'& .-1"24 t, .:_I! 1j;-REVISION I 11 37

DC Sources - Operating B 3.8.4 B 3.8 ELECTRICAL POWER SYitEMS B 3.8.4 DC Sources - Operating J, BASES BACKGR( )UND The'station DC6eietrical power system provides the AC emergencyJpOwe-r.,,sy~tem with dCoonitrolpoWer.. It also provides both pmotive an d Control '.power'to selected safety related equipment and`preferred AC vital i nstrument bus power (via inverters). IAse'uired by i0;CFk. 50, Appendix A. GDC 17 (Ref.1)'. the DC.&'1ectrital power system isdesigned to have sufficient inndiependence, redundancy, and-testability to perform, 1its safetk' functions, assuming a single failure.

The,:IDC electrical power system also conforms to the recommendations' of RegulatoryAGuide 1.6 (Ref. 2) and IEEE-308 (Ref. ' R3)e a.n The 125 VDC electrical power system consists of two independent and redundant safety related Class 1E DC electrical power subsystems,(Train A and Train B). Each subsystem consists of two:125 VDC batteries (each battery >

100% capacity), the associated'battery charger(s) for each battery, and all the associated control equipment and interconnecting cabling. Each subsystem'contains two DC

,power channels. There are four channels designated as A and C for Train A. and B and D for'Train B for each unit (See

'-3.8.4 LCO Bases section for detailed description).

Additionally there is one backup.batte ry charger per

subsystem which provides backupiservice in the event that the normal battery charger is out of service. If the backup battery charger is substituted for one of the normal I battery chargers, then the requirements of independence and

.- redundancy betw'eensubsystems

redundancy be Weens e are maintained.

.A During normal operation, the 125-VDC".load ispowered from the battery chargers with the batteries'floating on the system. Incase of loss of normal powerto the battery

-- charger, the-DC-load-is automatically powered from the station batteries,.

The Train A and Train B DC electrical power subsystems provide the control power for its associated Class lE AC power load group, 4.16 kV-switchgear., and 480 V load

-centert"i3-The DC electrical power subsystems also provide DC IeLectr'ital'power to the inverters, which in turn power the

..;XAvitu1 Instrument buses.

(continued)

PALO, ERDEjIUNITS 1,2,3 :I_i,Bj- 3, 8,471

.. 7 . 11- , .

REVISION 0

DC Sources - Operating B 3.8.4 BASES BACKGROUND The DC power distribution system is described in more detail (continued) in the Bases for LCO3'3.8.9, "Distribution Systems-'

!Oeratingd" afdfQrICO 38.,10, "Distribution Systems-Each battery has'adequat' storage capacity to carry the required( oacontinuously fortat'least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as discussed in the UFSARS C1)apter(8'(Ref '4)? , -

-Each 125 VDC bhttery issa'ratdl'ty-hodsed in a ventilated room apart-from'its chaWger'ahd distrjbution centers. Each subsystemis located indan area separated'physically and electrically from the other-subsystem to'ensure that a single failure in one subsystem doesnot,'cause a failure in

,,a redundant subsystem.' There is no 'shari g between

'redundant Class lE1subsystems,*such as'batteries, battery

,chargers, or distribution panels.

'Inaddition, each DC electrical power subsystem contains a backup battery charger which is manually transferable to either channel of a subsystem. The transfer mechanism is mechanically interlocked'to prevent both DC channels of a subsystem from being simultaneously connected to the backup battery charger.

The batteries for Train A and Train B DC electrical power subsystems are sized to produce required capacity at 80% of nameplate rating. The voltage limit is 2.13 V per cell, which corresponds'to a total minimum voltage output of 128 V per battery discussed in the Design Basis Manual (Ref. 12).

Each Train A and Train B DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation. while at the same time maintaining its battery bank fully charged.

Each battery charger also has suffic'ient'capacity to restore the battery from the design minimum charge to its fully charged state within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while supplying normal steady state loads discussed in the UFSAR, Chapter 8 (Ref. 4).

(continued)

PALO VERDE UNITS 1,2,3 B 3.8.4-2 REVISION 37

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.84.8 (contiiupd) ; -. ,;

,'.a'..........

REQUIREMENTS.. ,.'I R OPERABILITY wouldtpe'rturb the'eleftricaf :distribution system and challenge safety systems. This resriction from normally- performing the.surveillance'in MODE 1. 2. 3, and 4

' is further 'amplified to.allow portions of.,the surveillance to be performed for the purpose of reestablishing OPERABILITY (e.g. post work testing following corrective

. maintenance., corrective modification, deficient or

- .incomplete survei laIce testfing,' and other unanticipated

• ,OPEBILITYconcerns)

'i provided an.assessment determines plant safety is maintainedor enhanced'. This assessment

shall. as a minimum, consider,,the,-potential outcomes and transientsassociated-with a failed partial surveillance, a ie successful

partial.surveiflance.p and a perturbation of the offsite or onsite'system when. they'vre'tied together or operated independently for the partial'surveillance; as well as the~operator procedures available to cope with these outcomes. These shall be-measured against the avoided risk of a plant shutdown and startup to.determine that plant safety is maintained or enhanced when.portions of the surveillance are-performed in MODE 1, 2, 3, or 4. Risk insights or deterministic methods may be used for this assessment.

SR 3.8.4.7  ;

A.battery;service test is'aspecialt'test of battery capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length should correspond to the design duty-cycle requirements as specified in Reference 4.

The Surveillance'Frequency of 18 months is consistent with the recommendations-of Regulatory Guide 1.32 (Ref. 10) and Regulatory-GuideJ1.129 (Ref. 11). which state that the

'.,battery service r.test'should be performed during refueling operations, or-at.some other outage,:with intervals between tests not toexceed'.18 months.

This SR is modified by two Notes. Note 1 allows the performance of a battery performance discharge test or a modified performance discharge test in SR 3.8.4.8 in lieu of a service test since both performance discharge test F parameters envelope.the servi.ce test. The reason for Note 2 is that performing the Surveillance would perturb the electrical distribution system and challenge safety systems.

- " (contifriud)

PALO VERDE UNITS 1,2.3 B 3.8.4-9 REVISION 35

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.8 REQUIREMENTS (continued) . A battery performance discharge test is a test of constant current capacity offI battery., normally done in the "as after..having been in service, to detect

-found".condition,,

. any change Jin the capacity.determinedby the acceptance test.,. The .testiis intended to determine overall battery degradation due to age:.and.-usage.

'The modified derformance.4ischarge .test'is a simulated duty cycle consisting-of jusit'two rates:the.:one minute rate published for.the battery or.the larbjest current load of the duty cycle(but inno caselower than the performance test rate), followed by the test'rate employed for the performance test,-both'of which envelope the duty cycle of the~service test. Since'the.ampere'-hoUrs removed by a rated one minute.discharge represents a very small portion of the battery capacityythe test rate can be changed to that for the performance test without compromising the results of the performance discharge test.

A modified discharge test is a test of the battery capacity and its ability-to provide a high rate, short duration load (usually the highest rate of the duty cycle). This will often confirm the battery's ability to meet the critical period of the load duty cycle, in addition to determining its percentage of rated capacity. Initial conditions for the modified performance discharge test should be identical to those specified for a service test.

Either the battery performance discharge test or the modified performance discharge test is acceptable for satisfying SR 3.8.4.8.. In addition, either of the performance discharge tests may be used to satisfy SR 3.8.4.8 while satisfying the requirements of SR 3.8.4.7 at the same time, because the test parameters envelope the service test described in SR 3.8.4.7.

The acceptance.criteria for'this Surveillance are consistent with IEEE-450 (Ref. 9) and IEEE-485 (Ref. 5). These references recommend that the battery be replaced if its capacity is below 80% of the manufacturer rating. A capacity of 80% shows that the battery rate of deterioration is increasing, even if there is amplecapacity to meet the load requirements.

The surveillance Frequency for'this test is normally 60 months. If the battery showms.degradation, or if the (continued)

PALO VERDE UNITS 1,2,3 - B-.38.4-10 ' REVISION,37

DC Sources - Operating B 3.8.4 BASES .. . .

SURVEILLANCE SR 3.8.4.8 (continued)

DCJ ITTDFMFIMTC battery has re'ached:85X-of its expected;Jife and capacity is

< 100% of the menUfavturer.'s rating,' the Surveillance Frequenoy 'is' reduoed. to 12ilnonthsX. However, if the battery shows no' degradatltorvrbut has reached 85t of its expected life, the Surveil-ance Frequency;is'only-reduced to 24 nQnths for .batteries that retaini capacity Ž 100% of the manifiactuiere's a'in .t' D adation is'indicated when the battlrq'c-p'acftyd rops 'bymore; tbian 10% relative to its capacity on the pr'eViouus'performance test, or when it is

,10Q% elow theqiiianufactufrer's rati'ng.'

This SRis dified'by a Note. _The reason for the Note is that perforning' thetSurveillance woul'd jrturb the elect~rical distri~bution'system and' h'al Ienge safety systems.

ec!'a

' ." r i -btio REFERENCES 1. 10,CFR.50, Appendix A. GDC 17.

2. Regulatory Guide 1.6, March 10, 1971.

3. IEEE-308-1974.

4. UFSAR, Chapter,8,3.2.

5. IEEE-485-1983, June 1983.

6. UFSAR, Chapter 6.

7. UFSAR, Chapter 15.

8.

Regulatory Guide 1.93, December 1974.

9. IEEE-450-1980.

10. Regulatory Guide 1.,32, Revision 0, August 11. 1972.

I II

11., Regulatory Guide 1.129, Rev'ision 1, February 1978.

'12.' Design Basis Manual "Class 1E 125 VDC Power System".

13., Calculation 1,2,3ECPK207.

-) 2 PALO VERDE UNITS 1.2,3 -, I,..:,B-1.. .8-.4-11 i! REVISION 37

't :1 I

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Battery Cell Parameters B 3.8.6 BASES SURVEILLAI NCE Table 3.8.6-1 (continued)

REQUIREMEINTS effects. In addition to this allowance, footnote (a)to Table 3.8.6-1 permits the electrolyte level to be above the specified maximum level during equalizing charge, provided it isnot overflowing. These limits ensure that the plates suffer no physical damage, and that adequate electron transfer capability ismaintained in the event of transient conditions. IEEE-450 (Ref. 3) recommends that electrolyte level readings should be made only after the battery has been

-at float charge for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The Category A limit specified-for float voltage is2 2.13 V per cell. This value isbased on the battery vendor recommendation which states that prolonged operation of cells < 2.13 V can reduce the life expectancy of cells.

The Category'A limit specified for specific gravity for each pilot cell is2 1.200 (0.015 below the vendor fully charged nominal specific gravity or a battery charging current that had stabilized at a low value). This value ischaracteristic of a charged cell with adequate capacity. According to IEEE-450 (Ref. 3). the specific gravity readings are based on a temperature of 770F (250C).'

The specific gravity readings are corrected for actual 0 electrolyte temperature and level. For each 3 0F (1.67 C)

.above 770F (250C), 1 point (0.001) isadded to the reading; 1 point is-subtracted for each 30F below 770F. The specific

.,gravity of the electrolyte in a cell increases with a loss of water due to electrolysis or evaporation.

Category B defines the normal parameter limits for each connected-cell. -The term "connected cell" excludes any battery cell that may be jumpered out.'

The Category-B limits specified for-electrolyte level and float voltage are the same as those specified for Category A

,'and have been discussed above. Footnote (d)to Table 3.8.6-1

'jis applicable to Category'B float voltage. Footnote (d) requires correction for average electrolyte temperature. The Category B limit specified for specific gravity for each

-connected cell is Ž1.195 (0.020 below the vendor fully charged. nominal specific gravity) with the average I (continued)

PALO VERDE UNITS 1,2.3 B 3.8.6-5 REVISION 37

Battery Cell Parameters B 3.8.6 BASES SURVEILLANCE Table 3.8.6-1 (continued)

REQUIREMENTS of all connected cells 2 1.205 (0.010 below the vendor fully charged, nominal specific gravity). These values are based on vendor's recommendations. The minimum specific gravity value required for each cell ensures that the effects of a highly charged or newly installed cell will not mask overall degradation of the battery.

Category C defines the limit for each connected cell. These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function and maintain a margin of safety. When any battery parameter is outside the Category C limit, the assurance of sufficient capacity described above no longer exists and the battery must be declared inoperable.

The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value for float voltage is based on vendor recommendations which state that a cell voltage of 2.07 V or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement.

The Category C limit of average specific gravity 2 1.195 is based on vendor recommendations (0.020 below the vendor recommended fully charged, nominal specific gravity). In addition to that limit, it is required that the specific gravity for each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery.

Footnotes (b)and (c)to Table 3.8.6-1 are applicable to Category A, B. and C specific gravity. Footnote (b)to Table 3.8.6-1 requires specific gravity correction for electrolyte level and temperature, with the exception that level correction is not required when battery charging current is < 2 amps on float charge.- This current provides, in general, an indication of overall battery condition.

(continued)

PALO VERDE UNITS 1.2,3 IB 3.8.6-6 . REVISION 37