ML13120A502

Technical Specification Bases (TS Bases) Revision 57, Replacement Pages and Insertion Instructions

ML13120A502
Person / Time
Site:	Palo Verde
Issue date:	04/10/2013
From:	Arizona Public Service Co
To:	Office of Nuclear Reactor Regulation
References
102-06689-TNW/RKR/CJS
Download: ML13120A502 (37)

Text

PVNGSTechnical SpecificationBases (TS Bases)

Revision57 ReplacementPagesand InsertionInstructions The following LDCRs are included in this change:

LDCR 10-B012reflect removal of Unit 3 Post-AccidentSamplingSystem(PASS) containmentisolationvalve (ClV) RDB UV-407from TS Bases 3.3.10, Post-Accident MonitoringInstrumentation,as describedin the LCO Section, item 8, ContainmentIsolation ValvePosition. LicenseAmendment 136 authorized abandonmentof PASS, however, a numberof the PASSvalves remain physicallyconnected. DMWO2778159 removed the Unit 3 valve during the past Unit 3 outage.Only the Unit 1 valve remains installed.

LDCR 12-B008clarifiedTS Bases3.1.7, Regulating Control ElementAssembly (CEA) InsertionLimits, BackgroundSection,that the CEA fully withdrawn position is specified in the COLR. This is consideredto be an editorial enhancement.

LDCR 12-B009 removedspecific surveillancefrequenciesstated in various TS Bases which were missedduring the implementationof TSTF-425 and License Amendment 188. This is considered to be an editorial correction.

LDCR 12-B011corrects and clarifiesthe descriptionof the emergencydiesel generator (EDG)performancerequirementsduring starting under loss of power (LOP),with or withoutsafety injection actuation plant conditions. The changes clarify that the EDG is to start and close the EDGbreaker within a 10 second window.

Instructions Remove Pa.qe: Insert New Pa.qe:

Cover Page Cover Page List of Effective Pages List of EffectivePages 1/2 through 7/8 1/2 through 7/8 B 3.1.7-1 / B 3.1.7-2 B 3.1.7-1 / B 3.1.7-2 B 3.3.1-47/ B 3.3.1-48 B 3.3.1-47/ B 3.3.1-48 B 3.3.10-9/ B 3.3.10-10 B 3.3.10-9/ B 3.3.10-10 B 3.4.2-1/ B 3.4.2-2 B 3.4.2-1/ B 3.4.2-2 B 3.4.17-5/ B 3.4.17-6 B 3.4.17-5/ B 3.4.17-6 B 3.5.1-9 / B 3.5.1-10 B 3.5.1-9 / B 3.5.1-10 Digitally signed by Stephenson, Stephenson, Carl J(Z05778)

DN: cn=Stephenson, Carl J(Z05778)

Carl J(Z05778)

Reason: I attest to the accuracy and integrity of this document Date: 2013.04.05 12:38:44 -07'00'

PVNGS Technical Specification Bases (TS Bases)

Revision 57 Replacement Pages and Insertion Instructions B 3.5.2-9 / B 3.5.2-10 B 3.5.2-9 / B 3.5.2-10 B 3.6.2-7 / B 3.6.2-8 B 3.6.2-7 / B 3.6.2-8 B 3.7.4-5 / Blank B 3.7.4-5 / Blank B 3.7.11-7 / B 3.7.11-8 B 3.7.11-7 / B 3.7.11-8 B 3.7.13-3 / B 3.7.13-4 B 3.7.13-3 / B 3.7.13-4 B 3.8.1-5 ! B 3.8.1-6 B 3.8.1-5 ! B 3.8.1-6 B 3.8.1-23 / B 3.8.1-24 B 3.8.1-23 / B 3.8.1-24

PVNGS Palo Verde Nuclear Generating Station Units 1, 2, and 3 Technical Specification Bases Revision57 April 10,2013 C.e'_'enson Jtw- I o,.,ta,,.s,gn.0 b.s.eo.

DN:cn=S_ephenson, Reason:

CarlJ(Z0577R)

...... CarlJ(Z05778)

I attestto the;iccuracyand integrityof CarlJ(ZO5778) _°......,

Date:2013.04.0512:24:42-OT00*

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B 2.1.i-i 0 B 3 1.4-2 31 B 2 i.i-2 0 B 3 1.4-3 0 B 2 i.i-3 37 B 3 1.4-4 0 B 2 i.i-4 21 B 3 1.4-5 0 B 2 i.i-5 54 B 3 1.5-i 0 B 2 1.2-i 0 B 3 1.5-2 52 B 2 1.2-2 31 B 3 1.5-3 52 B 2 1.2-3 0 B 3 1.5-4 52 B 2 1.2-4 54 B 3 1.5-5 52 B 3 0-i 49 B 3 1.5-6 52 B 3.0-2 0 B 3 1.5-7 52 B 3.0-3 0 B 3 1.5-8 52 B 3.0-4 0 B 3.1 5-9 52 B 3.0-5 42 B 3.1 5-i0 56 B 3.0-6 48 B 3.1 5-ii 56 B 3.0-7 48 B 3.1 5-12 56 B 3.0-8 42 B 3.1 6-i 0 B 3.0-9 42 B 3.1 6-2 46 B 3.0-I0 42 B 3.1 6-3 42 B 3.0-ii 42 B 3.1 6-4 42 B 3.0-12 42 B 3.1 6-5 56 B 3.0-13 42 B 3.1 6-6 46 B 3 0-14 49 B 3.1 7-i 57 B 3 0-15 50 B 3 1 7-2 0 B 3 0-16 50 B 3 1 7-3 53 B 3 0-17 50 B 3 i 7-4 48 B 3 0-18 49 B 3 1 7-5 25 B 3 0-19 49 B 3 1 7-6 0 B 3.0-20 49 B 3 I 7-7 0 B 3.0-21 49 B 3 1.7-8 56 B 3.0-22 49 B 3 1.7-9 56 B 3.1.i-I 28 B 3 1 8-i 52 B 3.1 i-2 0 B 3 1 8-2 52 B 3.1 I-3 43 B 3.1 8-3 52 B 3.1 i-4 43 B 3.1 8-4 52 B 3.1 i-5 27 B 3.1 8-5 56 B 3.1 i-6 56 B 3.1 9-I 0 B 3.1 2-i 28 B 3.1 9-2 0 B 3.1 2-2 0 B 3.1 9-3 0 B 3.1 2-3 43 B 3.1 9-4 0 B 3.1 2-4 28 B 3.1 9-5 56 B 3.1 2-5 0 B 3.1 9-6 56 B 3 1 2-6 43 B 3.1.I0-I 0 B 3 1 2-7 12 B 3 i.i0-2 53 B 3 1 2-8 47 B 3 i.i0-3 0 B 3 1 2-9 56 B 3 i.i0-4 37 B 3 1 3-i 0 B 3 i.i0-5 56 B 3 1.3-2 0 B 3 i.i0-6 0 B 3 1.3-3 0 B 3 i.Ii-i 0 B 3 1.3-4 0 B 3 i.ii-2 53 B 3.1.3-5 0 B 3 i.Ii-3 0 B 3.1.3-6 56 B 3 i.Ii-4 53 B 3.1.4-i 0 B 3.1.ii-5 0 PALO VERDE UNITS i, 2, AND 3 1 Revision 57 April i0, 2013

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B 3.2 i-i 53 B 3 3.1-12 53 B 3.2 1-2 i0 B 3 3.1-13 53 B 3.2 1-3 53 B 3 3.1-14 53 B 3.2 1-4 0 B 3 3.1-15 53 B 3.2 1-5 0 B 3 3.1-16 53 B 3.2 1-6 0 B 3 3.1-17 53 B 3.2 1-7 56 B 3 3.1-18 53 B 3.2 1-8 56 B 3 3.1-19 53 B 3.2.2-1 52 B 3 3.1-20 53 B 3.2.2-2 i0 B 3 3.1-21 53 B 3.2.2-3 0 B 3 3.1-22 53 B 3.2.2-4 52 B 3 3.1-23 53 B 3.2.2-5 1 B 3 3.1-24 53 B 3.2.2-6 0 B 3 3.1-25 53 B 3.2 2-7 56 B 3 3.1-26 53 B 3.2 3-1 52 B 3 3.1-27 53 B 3.2 3-2 i0 B 3 3.1-28 53 B 3.2 3-3 0 B 3 3.1-29 53 B 3.2 3-4 52 B 3 3.1-30 53 B 3.2 3-5 0 B 3 3.1-31 53 B 3 2 3-6 0 B 3 3.1-32 53 B 3 2 3-7 0 B 3 3.1-33 53 B 3 2 3-8 56 B 3 3.1-34 53 B 3 2 3-9 56 B 3 3.1-35 53 B 3 2 3-10 0 B 3 3.1-36 53 B 3 2 4-1 52 B 3 3.1-37 53 B 3 2 4-2 i0 B 3 3.1-38 53 B 3 2 4-3 0 B 3 3.1-39 53 B 3 2 4-4 52 B 3 3.1-40 56 B 3 2 4-5 53 B 3 3.1-41 56 B 3 2 4-6 53 B 3 3.1-42 56 B 3 2 4-7 53 B 3.3.1-43 56 B 3 2 4-8 56 B 3.3.1-44 56 B 3 2 4-9 56 B 3.3.1-45 53 B 3 2 4-10 31 B 3.3.1-46 56 B 3 2 5-1 52 B 3.3.1-47 57 B 3 2 5-2 i0 B 3.3.1-48 56 B 3 2 5-3 0 B 3.3.1-49 56 B 3 2 5-4 52 B 3.3.1-50 53 B 3 2 5-5 0 B 3.3.1-51 53 I

B 3 2 5-6 56 B 3.3.2-1 50 B 3 2 5-7 0 B 3.3.2-2 0 B 3 3 I-I 35 B 3.3.2-3 1 B 3 3 1-2 53 B 3.3.2-4 35 B 3 3 1-3 53 B 3.3.2-5 35 B 3 3 1-4 53 B 3.3.2-6 51 B 3 3 1-5 53 B 3.3.2-7 35 B 3 3 1-6 53 B 3.3.2-8 35 B 3 3 1-7 53 B 3.3.2-9 50 B 3 3 1-8 53 B 3.3.2-10 38 B 3 3 1-9 53 B 3.3.2-11 42 B 3 3 i-i0 53 B 3.3.2-12 42 B 3 3.1-11 53 B 3.3.2-13 56 PALO VERDE UNITS i, 2, AND 3 2 Revision 57 April I0, 2013

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B 3.3.9-6 56 B 3.4 4-2 50 B 3.3.9-7 56 B 3.4 4-3 7 B 3.3.10-i 0 B 3.4 4-4 56 B 3.3.10-2 0 B 3.4 5-i 0 B 3.3.10-3 0 B 3.4 5-2 38 B 3.3.10-4 0 B 3.4 5-3 38 B 3.3.10-5 18 B 3.4 5-4 56 B 3.3.10-6 0 B 3.4 5-5 56 B 3.3.10-7 0 B 3.4 6-i 0 B 3.3.10-8 14 B 3.4 6-2 6 B 3.3.10-9 14 B 3.4 6-3 52 B 3.3.10-i0 57 B 3.4 6-4 6 B 3.3.10-ii 50 B 3.4 6-5 56 B 3.3.10-12 50 B 3.4 7-i 0 B 3.3.10-13 50 B 3.4 7-2 6 B 3.3.10-14 50 B 3.4 7-3 52 B 3.3.10-15 50 B 3.4 7-4 54 B 3.3.10-16 50 B 3.4 7-5 0 B 3.3.10-17 50 B 3.4 7-6 56 B 3.3.10-18 50 B 3.4 7-7 52 B 3.3.10-19 56 B 3.4 8-i 0 B 3.3.10-20 56 B 3.4 8-2 54 B 3.3.10-21 50 B 3.4 8-3 56 B 3.3.10-22 32 B 3.4 9-1 41 B 3.3.11-i 0 B 3.4 9-2 31 B 3.3.11-2 2 B 3.4 9-3 41 B 3.3.11-3 2 B 3.4 9-4 41 B 3.3.11-4 42 B 3.4 9-5 56 B 3.3.11-5 42 B 3.4 9-6 56 B 3.3.11-6 56 B 3.4 i0-I 53 B 3.3.11-7 56 B 3.4 i0-2 7 B 3.3.12-i 15 B 3.4 i0-3 0 B 3.3.12-2 50 B 3.4 i0-4 54 B 3.3.12-3 37 B 3.4 Ii-i 0 B 3.3.12-4 37 B 3.4 ii-2 53 B 3.3.12-5 56 B 3.4 ii-3 0 B 3.3.12-6 56 B 3.4 ii-4 52 B 3.4 I-i i0 B 3.4 ii-5 56 B 3.4 i-2 53 B 3.4 ii-6 54 B 3.4 i-3 0 B 3.4 12-i 1 B 3.4 i-4 0 B 3.4 12-2 34 B 3.4 i-5 56 B 3.4 12-3 48 B 3.4 2-i 7 B 3.4 12-4 56 B 3.4 2-2 57 B 3.4 12-5 31 i B 3.4 3-i 52 B 3.4 13-i 0 B 3.4 3-2 52 B 3.4 13-2 55 B 3.4 3-3 0 B 3.4 13-3 55 B 3.4 3-4 52 B 3.4 13-4 52 B 3.4 3-5 52 B 3.4 13-5 55 B 3.4 3-6 0 B 3.4 13-6 55 B 3.4 3-7 56 B 3.4 13-7 52 B 3.4 3-8 52 B 3.4 13-8 52 B 3.4 4-i 0 B 3.4 13-9 56 PALO VERDE UNITS i, 2, AND 3 4 Revision 57 April i0, 2013

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B 3 4 13-i0 56 B 3.5.2-7 1 B 3 4 13-ii 55 B 3.5.2-8 22 B 3 4 14-i 0 B 3.5.2-9 57 B 3 4 14-2 34 B 3.5.2-I0 56 B 3 4 14-3 34 B 3.5.3-I 0 B 3 4 14-4 38 B 3 5.3-2 48 B 3 4 14-5 38 B 3 5.3-3 0 B 3 4 14-6 38 B 3 5.3-4 0 B 3 4 14-7 56 B 3 5 3-5 0 B.3.4 14-8 56 B 3 5 3-6 2 B 3.4 15-i 0 B 3 5 3-7 2 B 3.4 15-2 48 B 3 5 3-8 56 B 3.4 15-3 0 B 3 5 3-9 56 B 3.4 15-4 0 B 3 5 3-I0 56 B 3.4 15-5 56 B 3 5 4-i 15 B 3.4 15-6 56 B 3 5 4-2 0 B 3.4 15-7 54 B 3 5 4-3 42 B 3.4 16-i 2 B 3 5 5-i 54 B 3.4 16-2 i0 B 3 5 5-2 54 B 3.4 16-3 0 B 3 5 5-3 55 B 3.4 16-4 42 B 3 5 5-4 54 B 3.4 16-5 56 B 3 5 5-5 51 B 3.4 16-6 56 B 3 5 5-6 51 B 3.4 17-i 0 B 3 5 5-7 51 B 3.4 17-2 27 B 3 5 5-8 56 B 3.4 17-3 42 B 3 5 5-9 56 B 3.4 17-4 42 B 3 5 6-i 0 B 3.4 17-5 57 B 3 5 6-2 1 B 3 4 17-6 56 B 3 5 6-3 0 B 3 4 18-i 38 B 3 5 6-4 56 B 3 4 18-2 40 B 3 5 6-5 56 B 3 4 18-3 38 B 3 6 i-i 0 B 3 4 18-4 38 B 3 6 i-2 53 B 3 4 18-5 38 B 3 6 i-3 0 B 3 4 18-6 38 B 3 6 i-4 29 B 3 4 18-7 38 B 3 6 I-5 29 B 3 4 18-8 38 B 3 6 2-I 45 B 3 5 i-i 0 B 3 6 2-2 53 B 3 5 i-2 53 B 3 6 2-3 0 B 3 5 i-3 7 B 3 6 2-4 0 B 3 5 i-4 0 B 3 6 2-5 0 B 3 5 i-5 0 B 3 6 2-6 0 B 3 5 I-6 0 B 3 6 2-7 0 B 3 5 i-7 1 B 3 6 2-8 57 B 3 5 i-8 1 B 3 6 3-i 36 B 3 5 i-9 57 B 3 6 3-2 43 B 3 5 i-i0 56 B 3 6 3-3 49 B 3 5 2-i 0 B 3 6 3-4 43 B 3 5 2-2 53 B 3 6 3-5 43 B 3 5 2-3 53 B 3 6 3-6 43 B 3 5 2-4 0 B 3 6 3-7 43 B 3 5 2-5 0 B 3.6 3-8 43 B 3 5 2-6 0 B 3.6 3-9 43 PALO VERDE UNITS i, 2, AND 3 5 Revision 57 April i0, 2013

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B 3.6 3-i0 43 B 3 7.5-3 40 B 3.6 3-ii 43 B 3 7.5-4 27 B 3.6 3-12 43 B 3 7.5-5 42 B 3.6 3-13 43 B 3 7.5-6 42 B 3 6 3-14 43 B 3 7.5-7 9 B 3 6 3-15 43 B 3 7.5-8 56 B 3 6 3-16 56 B 3 7.5-9 56 B 3 6 3-17 56 B 3 7.5-10 56 B 3 6 3-18 56 B 3 7.5-11 54 B 3 6 3-19 56 B 3.7 6-1 54 B 3 6.4-i 53 B 3.7 6-2 54 B 3 6.4-2 38 B 3.7 6-3 55 B 3 6.4-3 56 B 3.7 6-4 56 B 3.6.5-i 0 B 3.7 7-I 0 B 3 6.5-2 1 B 3.7 7-2 1 B 3 6.5-3 56 B 3.7 7-3 1 B 3 6.5-4 0 B 3.7 7-4 56 B 3 6.6-i 0 B 3 7 7-5 56 B 3 6.6-2 0 B 3 7 8-i 1 B 3 6.6-3 53 B 3 7 8-2 1 B 3 6 6-4 7 B 3 7 8-3 1 B 3 6 6-5 1 B 3 7 8-4 56 B 3 6 6-6 56 B 3 7 9-I 0 B 3 6 6-7 56 B 3.7 9-2 44 B 3 6 6-8 56 B 3.7 9-3 56 B 3 6 6-9 54 B 3.7 i0-i I0 B 3 7.1-i 50 B 3.7.10-2 1 B 3 7.1-2 50 B 3.7.10-3 1 B 3 7.1-3 34 B 3.7 i0-4 56 B 3 7.1-4 34 B 3.7 ii-i 50 B 3 7.1-5 54 B 3 7 ii-2 50 B 3.7.1-6 54 B 3 7 ii-3 51 B 3.7.2-i 40 B 3 7 ii-4 55 B 3.7.2-2 42 B 3 7 ii-5 50 I B 3.7.2-3 40 B 3 7 ii-6 55 B 3.7,2-4 40 B 3 7.11-7 57 B 3.7 2-5 40 B 3 7.11-8 56 B 3 7 2-6 40 B 3 7.11-9 50 B 3 7 2-7 40 B 3 7.12-i 1 B 3 7 2-8 54 B 3 7.12-2 21 B 3 7 2-9 54 B 3 7 12-3 55 B 3 7 3-i 1 B 3 7 12-4 56 B 3 7 3-2 1 B 3.7 13-i 0 B 3 7 3-3 37 B 3.7 13-2 0 B 3.7 3-4 0 B 3.7 13-3 0 B 3.7 3-5 54 B 3.7 13-4 57 B 3.7 4-i 50 B 3 7 13-5 56 i B 3.7.4-3 3.7.4-2 50 B 3 7 14-2 14-i 21 0

B 3.7.4-4 50 B 3 7 14-3 56 B 3.7.4-5 57 B 3 7 15-i 3 B 3.7.5-I 0 B 3 7 15-2 56 B 3.7.5-2 0 B 3.7 16-i 7 PALO VERDE UNITS I, 2, AND 3 6 Revision 57 April i0, 2013

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B 3 7 16-2 0 B 3 8.1-45 56 B 3 7 16-3 56 B.3 8 1-46 56 B 3 7 16-4 0 B.3 8 1-47 45 B 3 7 17-i 52 B.3 8 1-48 53 B 3 7 17-2 3 B 3 8 2-i 0 B 3 7 17-3 3 B 3 8 2-2 0 B 3 7 17-4 3 B 3 8 2-3 0 B 3 7 17-5 3 B 3 8 2-4 21 B 3 7 17-6 52 B 3 8 2-5 21 B 3 8 i-i 35 B 3 8 2-6 0 B 3 8 i-2 2 B 3 8 3-i 0 B 3 8 i-3 34 B 3 8 3-2 0 B 3 8 i-4 34 B 3 8 3-3 50 B 3 8 i-5 20 B 3 8 3-4 0 B 3 8.1-6 57 B 3 8 3-5 54 B 3 8.1-7 42 B 3 8 3-6 56 B 3 8.1-8 50 B 3 8 3-7 56 B 3 8.1-9 42 B 3 8 3-8 41 B 3 8.1-i0 43 B 3 8 3-9 56 B 3 8 I-ii 50 B 3 8 3-i0 54 B 3 8 1-12 48 B 3 8 4-i 0 B 3 8 1-13 48 B 3 8 4-2 37 B 3 8 1-14 48 B 3 8.4-3 0 B 3 8 1-15 48 B 3 8.4-4 2 B 3.8 1-16 41 B 3 8.4-5 2 B 3.8 1-17 41 B 3 8.4-6 56 B 3.8 1-18 41 B 3 8.4-7 56 B 3.8 1-19 41 B 3 8.4-8 56 B 3.8 1-20 41 B 3 8.4-9 56 B 3.8 1-21 41 B 3 8.4-i0 56 B 3.8 1-22 41 B 3 8.4-Ii 48 B 3.8 1-23 57 B 3 8.5-i 1 B 3.8 1-24 50 B 3 8.5-2 1 B 3.8 1-25 56 B 3 8 5-3 21 B 3 8 1-26 56 B 3 8 5-4 21 B 3 8 1-27 56 B 3.8 5-5 2 B 3 8 1-28 56 B 3.8 5-6 2 B 3 8 1-29 53 B 3.8 6-i 0 B 3 8 1-30 56 B 3.8 6-2 0 B 3 8 1-31 50 B 3.8 6-3 56 B 3 8 1-32 56 B 3.8 6-4 56 B 3 8 1-33 56 B 3.8 6-5 37 B 3 8 1-34 56 B 3.8 6-6 37 B 3 8 1-35 50 B 3 8 6-7 48 B 3 8 1-36 56 B 3 8 7-i 48 B 3 8 1-37 45 B 3 8 7-2 48 B 3 8 1-38 56 B 3 8 7-3 53 B 3 8 1-39 56 B 3 8 7-4 53 B 3 8 1-40 56 B 3 8 7-5 56 B 3.8 1-41 56 B 3 8 8-i 1 B 3.8 1-42 56 B 3 8 8-2 1 B 3.8 1-43 56 B 3 8 8-3 21 B 3.8.1-44 56 B 3 8 8-4 56 PALO VERDE UNITS I, 2, AND 3 7 Revision 57 April I0, 2013

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B 3.8.8-5 56 B 3 8.9-1 51 B 3 8.9-2 0 B 3 8 9-3 51 B38 9-4 0 B38 9-5 0 B 3 8 9-6 0 B 3.8 9-7 0 B 3.8 9-8 0 B 3.8 9-9 0 B 3.8 9-10 56 B 3.8 9-11 51 B 3.8 i0-i 0 B 3.8 10-2 21 B 3.8 10-3 48 B 3.8 10-4 56 B 3.9 i-i 34 Corrected B3 91-2 0 B3 91-3 0 B 3 9 1-4 56 B 3 9 2-1 48 B 3 92-2 15 B 3 9 2-3 56 B 3 9 2-4 56 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 9.3-5 56 B.3 9.3-6 56 B 3 9.4-1 0 B 3 9.4-2 54 B 3 9.4-3 0 B 3 9.4-4 56 B 3 9.5-1 0 B 3 9.5-2 54 B 3 9.5-3 27 B 3 9.5-4 56 B 3 9.6-1 0 B 3 9.6-2 0 B 3 9.6-3 56 B 3 9.7-1 0 B 3 9.7-2 0 B 3 9.7-3 56 PALO VERDE UNITS i, 2, AND 3 8 Revision 57 April i0, 2013

RegulatingCEAInsertion Limits B 3.1.7 B 3.1 REACTIVITYCONTROL SYSTEMS B 3.1.7 Regulating Control Element Assembly (CEA) Insertion Limits BASES BACKGROUND The insertion limits of the regulating CEAsare initial assumptions in all safety analyses that assume CEAinsertion upon reactor trip. The insertion limits directly affect core power distributions, assumptions of available SDM, and initial reactivity insertion rate. The applicable criteria for these reactivity and power distribution design requirements are 10 CFR50, Appendix A, GDC10, "Reactor Design," and GDC26, "Reactivity Limits" (Ref. 1), and 10 CFR50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors" (Ref. 2).

Limits on regulating CEA insertion have been established, and all CEApositions are monitored and controlled during power operation to ensure that the power distribution and reactivity limits defined by the design power peaking, ejected CEAworth, reactivity insertion rate, and SDMlimits are preserved.

The regulating CEAgroups generally operate with a predetermined amount of position overlap, in order to approximate a linear relation between CEAworth and position (integral CEAworth). The regulating CEAgroups are withdrawn and operate in a predetermined sequence. The group sequence, overlap limits, and fully withdrawn position are specified in the COLR.

The regulating CEAsare used for precise reactivity control of the reactor. The positions of the regulating CEAsare manually or automatically controlled. They are capable of changing reactivity very quickly (compared to borating or diluting).

The power density at any point in the core must be limited to maintain specified acceptable fuel design limits, including limits that preserve the criteria specified in 10 CFR50.46 (Ref. 2). Together, LCO3.1.7; LCO3.2.4, "Departure from Nucleate Boiling Ratio (DNBR)"; and LCO 3.2.5, "AXIAL SHAPEINDEX (ASl)," provide limits on control component operation and on monitored process variables to ensure the core operates within LCO3.2.1, (continued)

PALOVERDEUNITS 1,2,3 B 3.1.7-1 REVISION57

RegulatingCEAInsertion Limits B 3,1.7 BASES BACKGROUND "Linear Heat Rate (LHR)"; LCO3.2.2, "Planar Radial Peaking (continued) Factor (F_) : and LCO3.2.4, "Departure FromNucleate Boiling Ratio (DNBR)," limits in the COLR. Operation within the LHRlimits given in the COLRprevents power peaks that would exceed the loss of coolant accident (LOCA)limits derived by the EmergencyCore Cooling Systemsanalysis.

Operation within the F_ and departure from nucleate boiling (DNB)limits given in the COLRprevents DNBduring a loss of forced reactor coolant flow accident. In addition to the LHR, F_, and DNBRlimits certain reactivity limits are preserved by regulating CEAinsertion limits. The regulating CEAinsertion limits also restrict the ejected CEAworth to the values assumedin the safety analyses and preserve the minimumrequired SDMin MODES I and 2.

The establishment of limiting safety system settings and LCOsrequire that the expected long and short term behavior of the radial peaking factors be determined. The long term behavior relates to the variation of the steady state radial peaking factors with core burnup and is affected by the amountof CEAinsertion assumed,the portion of a burnup cycle over which such insertion is assumed,and the expected ower level variation throughout the cycle. The short term ehavior relates to transient perturbations to the steady state radial peaks, due to radial xenon redistribution. The magnitudes of such perturbations dependupon the expected use of the CEAsduring anticipated power reductions and load maneuvering. Analyses are performed, based on the expected modeof operation of the Nuclear SteamSupply System (base loaded, maneuvering, etc.). Fromthese analyses, CEA insertions are determined and a consistent set of radial peaking factors defined. The long term steady state and short term insertion limits are determined, based upon the assumedmodeof operation used in the analyses, and provide a meansof preserving the assumptionson CEAinsertions used. The long and short term insertion limits of LCO3.1.7 are specified for the plant, which has been designed for primarily base loaded operation, but has the ability to accommodate a limited amountof load maneuvering.

The regulating CEAinsertion and alignment limits, ASI and Tq are process variables that together characterize and control the three dimensional power distribution of the reactor core. Additionally, the regulating bank insertion limits control the reactivity that could be added in the (continued )

i PALOVERDEUNITS1,2,3 B 3.1.7-2 REVISION0

RPSInstrumentation - Operating B 3.3,1 BASES SURVEILLANCE SR 3.3.1.8 (continued)

REQUIREMENTS CALIBRATIONbecause they are passive devices with minimal drift and because of the difficulty of simulating a meaningful signal. Slow changes in detector sensitivity are compensated for by performing the calorimetric calibration (SR 3.3.1.4) and the linear subchannel gain check (SR 3.3.1.6). In addition, the associated control room indications are monitored by the operators.

SR 3.3.1.9 SR 3.3.1.9 is the performance of a CHANNEL CALIBRATION.

CHANNEL CALIBRATIONis a complete check of the instrument channel including the sensor. The Survei I Iance verifies that the channel responds to a measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drift between successive calibrations to ensure that the channel remains operational between successive tests. CHANNEL CALIBRATIONS must be performed consistent with the plant specific setpoint analysis.

The as found and as left values must also be recorded and reviewed for consistency with the assumptions of the surveillance interval extension analysis. The requirements for this review are outlined in Reference 9.

The Survei I Iance Frequency i s control led under the Survei I Iance Frequency Control Program.

The Surveillance is modified by a Note to indicate that the neutron detectors are excluded from CHANNEL CALIBRATION because they are passive devices with minimal drift and because of the difficulty of simulating a meaningful signal. Slow changes in detector sensitivity are compensated for by performing the calorimetric calibration I (SR 3.3.1.4) and the linear subchannel gain check (SR 3.3,1.6).

I (continued)

PALOVERDEUNITS 1.2,3 B 3.3.1-47 REVISION57

RPSInstrumentation - Operating B 3.3.1 BASES SURVEILLANCE SR 3.3.1.10 REQUIREMENTS I (continued) A CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TESTis performed TESTshall on injection include the the CPCs.ofThe a signal as close to the sensors as practicable to verify OPERABILITY including alarm and trip Functions.

I Surveillance FrequencyControl The Surveillance Program. under the Frequency is controlled SR 3.3.1.11 The three excore detectors used by each CPCchannel for axial flux distribution information are far enoughfrom the core to be exposedto flux from all heights in the core, although it is desired that they only read their particular level. The CPCsadjust for this flux overlap by using the predetermined shape annealing matrix elements in the CPC software.

After refueling, it is necessary to re-establish or verify the shape annealing matrix elements for the excore detectors based on moreaccurate incore detector readings.

This is necessary becauserefueling could possibly produce a significant change in the shape annealing matrix coefficients.

Incore detectors are inaccurate at low power levels.

I THERMAL POWER should be significant but < 70%to perform an accurate axial shape calculation used to derive the shape annealing matrix elements.

By restricting power to _ 70%until shape annealing matrix elements are verified, excessive local power peaks within the fuel are avoided. Operating experience has shownthis Frequency to be acceptable.

(continued)

PALOVERDE UNITS1,2,3 B 3.3.1-48 REVISION56 i

PAMInstrumentation B 3.3.10 BASES LCO 8. Containment Isolation Valve Position (continued)

(continued)

At PVNGSthe Containment Isolation Valve position instrumentation consist of:

CPA-UV-2A Containment Refueling Purge Supply CPA-UV-2B Containment Refueling Purge Exhaust CPB-UV-3A Containment Refueling Purge Supply CPB-UV-3B Containment Refueling Purge Exhaust CPA-UV-4A Containment Power Access Purge Supply CPA-UV-4B Containment Power Access Purge Exhaust CPB-UV-5A Containment Power Access Purge Supply CPB-UV-5B Containment Power Access Purge Exhaust CHB-UV-505 RCPControlled Bleedoff to VCT CHA-UV-506 RCPControlled Bleedoff to VCT CHA-UV-516 Letdown to Regen HX CHB-UV-523 Letdown from Regen HX CHA-UV-560 Reactor Drain Tank Outlet CHB-UV-561 Reactor Drain Tank Outlet CHA-UV-580 Make-Up Supply to Reactor Drain Tank CHA-UV-715* Sample Return to Reactor Drain Tank CHB-UV-924* Letdown Line Sample PASS GM-UV-1 HP Nitrogen to Safety Injection Tanks GM-UV-2 LP Nitrogen to Containment GRA-UV-1 Waste Gas Header GRB-UV-2 Waste Gas Header HCB-UV-44* Radiation Monitor RU-1 Supply HCA-UV-45* Radiation Monitor RU-1 Supply HCA-UV-46* Radiation Monitor RU-1 Return HCB-UV-47* Radiation Monitor RU-1 Return HPA-UV-I Containment Hydrogen Control System HPB-UV-2 Containment Hydrogen Control System HPA-UV-3 Hydrogen Recombiner Supply HPB-UV-4 Hydrogen Recombiner Supply HPA-UV-5 Hydrogen Recombiner Return HPB-UV-6 Hydrogen Recombiner Return HPA-UV-23* Hydrogen Monitor Return HPA-UV-24* Hydrogen Monitor Supply IM-UV-2* Instrument and Service Air (continued)

PALOVERDEUNITS 1,2,3 B 3.3.10-9 REVISION14

PAMInstrumentati on B 3.3.10 BASES LCO 8. ContainmentIsolation Valve Position (continued)

(continued)

NCB-UV-401 Nuclear Cooling Water NCA-UV-402 Nuclear Cooling Water NCB-UV-403 Nuclear Cooling Water RDA-UV-23 ContainmentSumps RDB-UV-24 ContainmentSumps I RDB-UV-407*ContainmentRadwasteSumps(Unit 1 Only)

SGB-HV-200 SteamGenerator #1 Chemical Injection SGB-HV-201 SteamGenerator #2 Chemical Injection SIA-UV-708 ContainmentRecirc SumpPASS SSB-UV-200 Hot Leg Sample SSB-UV-201 Surge Line Sample SSB-UV-202 Pressurizer SteamSpaceSample SSA-UV-203 Hot Leg Sample SSA-UV-204 Surge Line Sample SSA-UV-205 Pressurizer SteamSpaceSample WCB-UV-61 Normal Chilled Water Return Header WCA-UV-62 Normal Chilled Water Return Header WCB-UV-63 Normal Chilled Water Supply Header

• -Solenoid operated valves with relay driven SESS/ERFDADS indication.

9. ContainmentArea Radiation (high range)

ContainmentArea Radiation is provided to monitor for the potential of significant radiation releases and to provide release assessmentfor use by operators in I determining the need to invoke site emergencyplans.

The alarm setpoints shall be set within the limits specified in the UFSAR.

At PVNGS,ContainmentArea Radiation instrumentation consists of the following:

SQA-RU-148 SQB-RU-149 (continued)

PALOVERDE UNITS1,2,3 B 3.3.10-10 REVISION 57

RCSMinimum Temperaturefor Criticality B 3.4.2 B 3.4 REACTORCOOLANT SYSTEM(RCS)

B 3.4.2 RCSMinimum Temperature for Criticality BASES BACKGROUND Establishing the value for the minimum temperature for reactor criticality is based upon considerations for:

a. Operation within the existing instrumentation ranges and accuracies;

b. Operation within the bounds of the existing accident analyses; and

c. Operation with the reactor vessel above its minimum nil ductility reference temperature when the reactor is critical.

The reactor coolant moderator temperature coefficient used in core operating and accident analysis is typically defined for the normal operating temperature range (550°F to 611°F).

Nominal Tcoldfor making the reactor critical is 565°F.

Safety and operating analyses for lower temperature have not been made.

APPLICABLE There are no accident analyses that dictate the minimum SAFETY ANALYSEStemperature for criticality. I The RCSminimumtemperature for criticality satisfies Criterion 2 of 10 CFR50.36(c)(2)(ii).

LCO The purpose of the LCOis to prevent criticality below the minimumnormal operating temperature (550°F) and to prevent operation in an unanalyzed condition.

The LCOis only applicable in MODES 1 and 2 with Keff_ 1.0 and provides a reasonable distance to the limit of 545°F.

This allows adequate time to trend its approachand take corrective actions prior to exceeding the limit.

(continued)

PALOVERDE UNITS1,2,3 B 3.4.2-1 REVISION7

RCSMinimumTemperature for Criticality B 3.4.2 BASES(continued)

APPLICABILITY The reactor has been designed and analyzed to be critical in MODES i and 2 only and in accordancewith this specification. Criticality is not permitted in any other MODE.Therefore, this LCOis applicable in MODE I, and MODE 2 whenKeffm 1.0. Monitoring is required at or below a Tco1_ of 550°F. The no load temperature of 565°F is maintained by the SteamBypassControl System.

ACTIONS A.I If Tco]dis below 545°F, the plant must be brought to a MODE in which the LCOdoes not apply. To achieve this status, the plant must be brought to MODE 3 within 30 minutes.

Rapid reactor shutdowncan be readily and practically achieved within a 30 minute period. The allowed time reflects the ability to perform this action and to maintain the plant within the analyzed range.

I SURVEILLANCE SR 3.4.2.1 REQUIREMENTS Tco]_is required to be verified _ 545°F after any RCSloop under the Surveillance FrequencyControl Program. A Note I Tcold states< 550°F. The Surveillance the Surveillance Frequency is required is controlled wheneverthe reactor is critical and temperature is below 550°F. A second Frequency requires Tco]dto be verified within 30 minutes of reaching criticality. This will require repeated performance of SR J 3.4.2.1 since a reactor startup takes longer than 30 minutes. The 30 minute time period is frequent enoughto prevent inadvertent violation of the LCO.

REFERENCES 1. UFSAR,Section 15.

PALOVERDEUNITS1,2,3 B 3.4.2-2 REVISION57

_r

RCSSpecifi c Acti vi ty B 3.4.17 BASES (continued)

SURVEILLANCE SR 3.4.17.1 REQUIREMENTS The Surveillance requires performing a gammaisotopic analysis as a measure of the gross specific activity of the reactor coolant. While basically a quantitative measure of radionuclides with half lives longer than 15 minutes, excluding iodines, this measurement is the sum of the degassed gammaactivities and the gaseous gammaactivities in the sample taken. This Surveillance provides an indication of any increase in gross specific activity.

Trending the results of this Surveillance allows proper remedial action to be taken before reaching the LCOlimit under normal operating conditions. The Surveillance is applicable in MODES1 and 2, and in MODE3 with RCScold leg temperature at least 500°F. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.4.17.2 This Surveillance is performed to ensure iodine remains within limit during normal operation and following fast power changes when fuel failure is more apt to occur. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The surveillance frequency is I modified by the Note "Only required to be performed in MODE 1". This is acceptable because the level of fission products generated in MODES 2 and 3 is much less than in MODE1. The Frequency, between 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power change of 2 15%RTPwithin a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, is established because the iodine levels peak during this time following fuel failure; samples at other times would provide inaccurate results. One sample is sufficient if the plant has gone through a shutdown or if the transient is complete in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SR3.4.17.2 Frequencyis modified by a Note which requires I the Surveillance to only be performed in MODE 1. This is required becausethe level of fission products generated in other MODES is muchless. Also. fuel failures associated with fast power changesis more apt to occur in MODE 1 than in MODES 2 or 3.

(continued)

PALOVERDEUNITS 1,2,3 B 3.4.17-5 REVISION57

RCSSpecific Activity B 3.4.17 BASES SURVEILLANCE SR 3.4.17.3 REQUIREMENTS i (continued) with the plant operating A radiochemical analysis infor MODE 1 equilibrium isconditions.

_ determination required The _ determination directly relates to the LCOand is required to verify plant operation within the specified gross activity LCOlimit. The analysis for _ is a measurementof the average energies per disintegration for isotopes with half lives longer than 15 minutes, excluding iodines. The Surveillance Frequencyis controlled under the Surveillance FrequencyControl Program.

This SRhas been modified by a Note that indicates sampling is required to be performed within 31 days after 2 effective full power days and 20 days of MODE1 operation have elapsed since the reactor was last subcritical for _ 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> should the 184 day Frequencyinterval be exceeded. Further discussion of SRNote format is found in Section 1.4, Frequency. This ensures the radioactive materials are at equilibrium so the analysis for E is representative and not skewedby a crud burst or other similar abnormal event.

REFERENCES 1. 10 CFRI00.II, 1973.

2. UFSAR,Section 15.6.3.

i PALOVERDEUNITS 1,2,3 B 3.4.17-6 REVISION56

SITs-Operating B 3.5.1 BASES(continued)

SURVEILLANCE SR 3.5.1.1 REQUIREMENTS Verification that each SIT isolation valve is fully open, as indicated in the control room, ensures that SITs are available for injection and ensures timely discovery if a valve should be partially closed. If an isolation valve is not fully open, the rate of injection to the RCSwould be reduced. Although a motor operated valve should not change position with power removed, a closed valve could result in not meeting accident analysis assumptions. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.5.1.2 and SR 3.5.1.3 SIT borated water volume and nitrogen cover pressure should be verified to be within specified limits in order to ensure adequate injection during a LOCA. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.5.1.4 Frequency is reasonable for verification to determine that I each SIT's boron concentration is within the required limits, because the static design of the SITs limits the ways in which the concentration can be changed. The Survei I Iance Frequency i s control Ied under the Survei I Iance Frequency Control Program.

(continued)

PALOVERDEUNITS 1,2,3 B 3.5.1-9 REVISION57

SITs-Operati ng B 3.5.1 BASES SURVEILLANCE SR 3.5.1.5 REQUIREMENTS I (continued) Verification valve operatorthat powerthat ensures is removedfrom each SIT an active failure isolation could not result in the undetected closure of a SIT motor operated isolation valve. If this were to occur, only two SITs would be available for injection, given a single failure I controlled underathe coincident with Surveillance LOCA. FrequencyControl The Surveillance FrequencyProgram.

is SR3.5.2.5 allows power to be supplied to the motor operated isolation valves whenRCSpressure is < 1500 psia, thus allowing operational flexibility by avoiding unnecessary delays to manipulate the breakers during unit startups or shutdowns. Evenwith power supplied to the valves, inadvertent closure is prevented by the RCSpressure interlock associated with the valves. Should closure of a valve occur in spite of the interlock, the Sl signal provided to the valves would open a closed valve in the event of a LOCA. At RCSpressures abovethe valve auto-open interlock, the maximumpressure at which the SIASopen signal will open the valves is limited by the valve operator differential pressure design capability.

REFERENCES 1. IEEEStandard 279-1971.

2. UFSAR,Section 6.

I 3. I0 CFR50.46.

4. UFSAR,Chapter 15.

5. NUREG-1366, "Improvementsto Technical Specifications Surveillance Requirements," December1992.

6. CENPSD-994,"CEOG Joint Applications Report for Safety Injection TankAOT/STIExtension," May 1995.

7. UFSARSection 7.6.2.2.2.

! 8. TRMT3.5 (ECCS)" TSR3.5. 200.4 PALOVERDEUNITS 1,2,3 B 3.5.1-10 REVISION56 i

SITs- Shutdown B 3.5.2 BASES (continued)

SURVEILLANCE SR 3.5.2.1 REQUIREMENTS Verification that each required SIT isolation valve is fully open when pressurizer pressure is >_430 psia as indicated in the control room, ensures that the required SITs are available for injection and ensures timely discovery if a valve should be partially closed. If a required isolation valve is not fully open, the rate of injection to the RCS would be reduced. Although a motor operated valve should not change position with power removed, a closed valve could result in not meeting accident analysis assumptions. The Survei I Iance Frequency i s control led under the Survei I Iance Frequency Control Program.

SR 3.5.2.2 and SR 3.5.2.3 Borated water volume and nitrogen cover pressure for the required SITs should be verified to be within specified limits in order to ensure adequate injection during a LOCA.

The Survei I Iance Frequency is control led under the Surveillance Frequency Control Program.

SR 3.5.2.4 Frequency is reasonable for verification to determine that I each required SIT's boron concentration is within the required limits, because the static design of the SITs limits the ways in which the concentration can be changed.

The Survei I Iance Frequency i s controlled under the Surveillance Frequency Control Program, (continued)

PALOVERDEUNITS 1,2,3 B 3.5.2-9 REVISION57

SITs - Shutdown B 3.5.2 BASES I SURVEILLANCE SR 3.5.2.5 REQUIREMENTS I (continued) Verification thatoperator power iswhenthe removedfrom each required isolation valve pressurizer pressureSIT is 1500 psia ensures that an active failure could not result in the undetected closure of a SIT motor operated isolation valve. If this were to occur, two less than the required SITs would be available for injection, given a single failure coincident with a LOCA.

I Surveillance The FrequencyControl Surveillance Program. under the Frequencyis controlled This SR allows power to be supplied to the motor operated isolation valves whenpressurizer pressure is < 1500 psia, thus allowing operational flexibility by avoiding unnecessarydelays to manipulate the breakers during unit startups or shutdowns. Evenwith power supplied to the valves, inadvertent closure is prevented by the RCSpressure interlock associated with the valves. Should closure of a valve occur in spite of the interlock, the SI signal provided to the valves would open a closed valve in the event of a LOCA. At RCSpressures above the valve auto-open interlock, the maximumpressure at which the SIAS open signal will open the valves is limited by the valve operator differential pressure design capability.

REFERENCES 1. IEEE Standard 279-1971.

2. 10 CFR50.46.

I 3. UFSAR,Chapter 15.

4. NUREG-1366,"Improvements to Technical Specifications Surveillance Requirements," December 1992.

5. CE NPSD-994, "CEOGJoint Applications Report for Safety Injection Tank AOT/STI Extension," May 1995.

6. UFSARSection 7.6.2.2.2 7, TRMT3.5 (ECCS); TSR3.5.200.4 PALOVERDEUNITS 1,2,3 B 3.5.2-10 REVISION56

ContainmentAir Locks B 3.6.2 BASES ACTIONS C.1, C.2, and C.3 (continued)

Required Action C.2 requires that one door in the affected containment air lock must be verified to be closed. This action must be completed within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time.

This specified time period is consistent with the ACTIONSof LCO3.6.1, which requires that containment be restored to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Additionally, the affected air lock(s) must be restored to OPERABLE status within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time. The specified time period is considered reasonable for restoring an inoperable air lock to OPERABLE status, assuming that at least one door is maintained closed in each affected air lock.

D.1 and D.2 If the inoperable containment air lock cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODEin which the LCOdoes not apply. To achieve this status, the plant must be brought to at least MODE3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE5 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 plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.2.1 REQUIREMENTS Maintaining containment air locks OPERABLE requires compliance with the leakage rate test requirements of the ContainmentLeakageRate Testing Program. This SR reflects the leakage rate testing requirements with regard to air lock leakage (Type B leakage tests). The acceptance criteria were established during initial air lock and containment OPERABILITY testing. The periodic testing requirements verify that the air lock leakage does not exceed the allowed fraction of the overall containment leakage rate. The Frequency is required by the Containment LeakageRate Testing Programand includes testing of the airlock doors following each closing, as specified.

(continued)

PALOVERDEUNITS 1,2,3 B 3.6.2-7 REVISION0

ContainmentAir Locks B 3.6.2 BASES SURVEILLANCE SR 3.6.2.1 (continued)

REQUIREMENTS The SRhas beenmodified by two Notes. Note 1 states that an inoperable air lock door does not invalidate the previous successful performanceof the overall air lock leakage test.

This is considered reasonable since either air lock door is capable of providing a fission product barrier in the event of a DBA. Note 2 has been added to this SRrequiring the results to be evaluated against the acceptance criteria which is applicable to SR3.6.1.1. This ensures that air lock leakage is properly accounted for in determining the combinedType BandC containment leakage rate.

SR 3.6.2.2 The air lock interlock is designed to prevent simultaneous opening of both doors in a single air lock. Since both the inner and outer doors of an air lock are designed to withstand the maximumexpected post accident containment pressure, closure of either door will support containment OPERABILITY.Thus, the door interlock feature supports containment OPERABILITY while the air lock is being used for personnel transit into and out of containment. Periodic testing of this interlock demonstratesthat the interlock will function as designed and that simultaneous opening of the inner and outer doors will not inadvertently occur. Due to the purely mechanical nature of this interlock, and given that the interlock mechanismis not normally challenged when containment is used for entry and exit (procedures require strict adherenceto single door opening), this test is only required to be performed periodically. The Surveillance Frequencyi s control led under the SurveiI Iance Frequency Control Program.

REFERENCES 1. 10 CFR50, Appendix J, Option B.

2. UFSAR,Section 3.8.

3. UFSAR,Section 6.2.

4. UFSAR,Section 15.6 PALOVERDE UNITS1,2,3 B 3.6.2-8 REVISION 57

ADVs B 3.7.4 BASES ACTIONS C.1 and C.2 (continued)

If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODEin which the LCOdoes not apply. To achieve this status, the unit must be placed in at least MODE3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE4, without reliance on the steam generator for heat removal, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.4.1 REQUIREMENTS To perform a controlled cooldownof the RCS,the ADVsmust be able to be openedand throttled through their full range.

This SR ensures the ADVsare tested through a full control cycle. Performanceof inservice testing or use of an ADV I during a unit cooldownmay satisfy this requirement. The Surveillance Frequencyis controlled under the Surveillance FrequencyControl Program.

REFERENCES 1. UFSAR,Section 10.3.

PALOVERDEUNITS 1,2,3 B 3.7.4-5 REVISION57

This page intentionally left blank CREFS B 3.7.11 BASES ACTIONS E.1 and E.2 (continued)

An alternative to Required Action E.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the CRE. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel to a safe position.

F.1 and F.2 If two CREFStrains become inoperable for reasons other than an inoperable CREboundary or one or more CREFStrains become inoperable due to an inoperable CREboundary, during Mode 5 or 6, or during the movementof irradiated fuel assemblies, immediate action must be taken to suspend activities that could release radioactivity that might enter the CRE. The Required Actions place the unit in a condition that minimizes accident risk. These actions do not preclude movement of fuel assemblies to safe positions.

G.1 If both CREFStrains are inoperable in MODE1, 2, 3, or 4 for reasons other than an inoperable CREboundary (i.e.,

Condition B), the CREFSmay not be capable of performing the intended function and the unit is in a condition outside the accident analyses. Therefore, LCO3.0.3 must be entered i mmediately.

SURVEILLANCE SR 3.7.11.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. Since the environment and normal operating conditions on this system are not severe, testing each train periodically provides an adequatecheck on this I system.

Periodic operations for _ 15 minutes to demonstrate the I function of the system is required. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.11-7 REVISION57

CREFS B 3.7.11 BASES SURVEILLANCE SR 3.7.11.2 REQUIREMENTS (continued) This SRverifies that the required CREFStesting is performed in accordancewith the Ventilation Filter Testing Program(VFTP). The CREFSfilter tests are in accordance with Regulatory Guide 1.52 (Ref. 5). The VFTPincludes testing HEPAfilter performance, charcoal adsorber efficiency, minimumsystem flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test Frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.11.3 This SRverifies that each CREFStrain starts and operates on an actual or simulated actuation signal. This includes verification that the system is automatically placed into a filtration modeof operation with flow through the HEPA Frequency is controlled under the Surveillance Frequency I Control filters Program.

and charcoal adsorber banks. The Surveillance SR 3.7.11.4 I This SRverifies the operability of the CREboundary by testing for unfiltered air inleakage past the CREboundary and into the CRE. The details of the testing are specified in the Control RoomEnvelope Habitability Program.

The CREis considered habitable when the radiological dose of CREoccupants calculated in the licensing basis analyses of DBAconsequencesis no morethan 5 rem whole body or its equivalent to any part of the body and the CREoccupants are protected from hazardouschemicals and smoke. This SR verifies that the unfiltered air inleakage into the CREis no greater than the flow rate assumedin the licensing basis analyses is greaterof than DBAconsequences.

the assumedflowWhenunfiltered airB must inleakage rate, Condition be entered. Required Action B.3 allows time to restore the CRE boundaryto OPERABLE status provided mitigating actions can ensure that the CREremains within the licensing basis habitability limits for the occupants following an accident.

Compensatorymeasuresare discussed in Regulatory Guide 1.196, Section C.2.7.3, (Ref 6) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 7).

l (continued)

PALOVERDE UNITS1,2,3 B 3.7.11-8 REVISION56

ESFPREACS B 3.7.13 BASES LCO c. Heater, prefilter, ductwork, valves, and dampers are (continued) OPERABLE,and air circulation can be maintained.

In addition, the auxiliary building envelope below the 100 ft. elevation must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors.

APPLICABILITY In MODES1, 2, 3, and 4, the ESF PREACSis required to be OPEP_ABLE consistent with the OPERABILITYrequirements of the ECCS.

In MODES5 and 6, the ESFPREACSis not required to be OPERABLE,since the ECCSis not required to be OPERABLE.

ACTIONS A.I With one ESF PREACStrain inoperable, action must be taken to restore OPERABLE status within 7 days. During this time, the remaining OPERABLE train is adequate to perform the ESF PREACSfunction.

The 7 day Completion Time is appropriate because the risk contribution is less than that for the ECCS(72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time) and this system is not a direct support system for the ECCS. The 7 day Completion Time is reasonable, based on the low probability of a DBAoccurring during this time period, and the consideration that the remaining train can provide the required capability.

B.1 and B.2 If the ESF PREACStrain cannot be restored to OPERABLE status within the associated Completion Time, the unit must be in a MODEin which the LCOdoes not apply. To achieve this status, the unit must be placed in at least MODE3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE5 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 in an orderly manner and without challenging unit systems.

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.13-3 REVISION0

ESF PREACS B 3.7.13 BASES(continued)

SURVEILLANCE SR 3.7.13.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. Since the environment and normal operating conditions on this system are not severe, I testing each train periodically provides an adequatecheck on this system.

Operations for _ 15 minutes demonstrates the function of the system. There is not expected to be any moisture buildup on the adsorbers and HEPAfilters due to the low humidity at PVNGS (Ref. 7). The Surveillance Frequency is controlled under the Surveillance FrequencyControl Program.

SR 3.7.13.2 This SR verifies that the required ESF PREACStesting is performed in accordance with the Ventilation Filter Testing Program (VFTP). The ECCSPREACSfilter tests are in accordance with Regulatory Guide 1.52 (Ref. 4). The VFTP includes testing HEPAfilter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.13.3 This SR verifies that each ESFPREACS train starts and operates on an actual or simulated actuation signal, The Surveillance Frequencyis controlled under the Surveillance FrequencyControl Program.

SR 3.7.13.4 This SRverifies the integrity of the ESFenvelope. The I ability of the ESFenvelope to maintain a negative pressure, with respect to potentially uncontaminatedadjacent areas, is periodically tested to verify proper function of the ESF PREACS.During the post accident modeof operation, the ESF PREACS is designed to maintain a slight negative pressure in the ESFenvelope with respect to adjacent areas to prevent unfiltered LEAKAGE.For the purposes of testing, the term (continued)

I PALOVERDE UNITS1,2,3 B 3.7.13-4 REVISION57

AC Sources - Operating B 3.8.1 BASES LCO Two circuits between the offsite transmission network and the onsite Class 1E Electrical Power Distribution System and separate and independent DGsfor each train ensure availability of the required power to shut down the reactor and maintain it in a safe shutdown condition after an anticipated operational occurrence (AO0) or a postulated DBA.

Offsite circuits are those that are described in the updated FSARand are part of the licensing basis for the unit.

In addition, one automatic load sequencer per train must be OPERABLE.

Each offsite circuit must be capable of maintaining rated frequency and voltage, and accepting required loads during an accident, while connected to the ESF buses.

The startup transformers (NAN-X01, NAN-X02, and NAN-X03) convert the 525 kV offsite power to the Non-Class 1E 13.8 kV power. Each secondary winding of a startup transformer normally provides power to one of two interconnected 13.8 kV intermediate buses (NAN-S05& NAN-S06) per unit, in such a way that the two 13.8 kV intermediate buses of the same unit receive power from two different start-up transformers (preferred offsite sources: normal and alternate supply).

For example, Unit 1NAN-SO5's normal supply is from a NAN-X03 secondary winding and NAN-SO5's alternate supply is from a NAN-X01secondary winding; Unit 1NAN-SO6's normal supply is from a NAN-X02secondary winding and NAN-SO5's alternate supply is from a NAN-X01secondary winding. The secondary winding are sized to start and carry one-half of the non-Class 1E loads of one unit and two trains of ESF loads, one which is from another unit, during unit trips or during startup/shutdown operation.

The 13.8 kV intermediate buses (NAN-S05& NAN-S06), in turn, distribute power to the 4.16 kV Class 1E buses (PBA-S03&

PBB-S04) via a 13.8 kV bus (NAN-S03or NAN-S04) and an ESF transformer (NBN-X03or NBN-X04).

Two fast bus transfer circuits are also provided to transfer the non-Class 1E house loads fed from NAN-S01and NAN-S02to 13.8 kV buses NAN-S03and NAN-S04respectively during a plant trip or during startup/shutdown operation. Prior to a plant trip, NAN-S01and NAN-S02are fed from the auxiliary transformer, and are fed from NAN-S03and NAN-S04 respectively after the plant trip.

(continued)

PALOVERDEUNITS 1,2,3 B 3.8.1-5 REVISION20

ACSources - Operating B 3.8.1 BASES LCO Each DGmust be capable of starting, accelerating to at (continued) least the minimumacceptable speed (i.e., frequency) and voltage, and connecting to its respective ESFbus on detection of bus under-voltage. This will be accomplished within (_) I0 seconds after receipt of the diesel generator start signal. EachDGmust also be capable of accepting required loads within the assumedloading sequence intervals, and continue to operate until offsite power can be restored to the ESFbuses. These capabilities are required to be met from a variety of initial conditions such as DGin standby condition with the engine hot and DGin standby condition with the engine at normal keep-warm conditions. Additional DGcapabilities must be demonstrated to meet required Surveillances (e.g., capability of the DG to revert to standby status on an ECCSsignal while operating in parallel test mode).

Proper sequencing of loads, including tripping of nonessential loads, is a required function.

The AC sources in one train must be separate and independent (to the extent possible) of the AC sources in the other train. For the DGs, separation and independenceare complete.

For the offsite AC sources, the separation and independence are to the extent practical. An offsite circuit maybe connected to both 4.16 kV Class 1E buses (PBA-S03& PBB-S04) and not violate separation criteria. While in this alignment, the associated 13.8 kV startup transformer secondary circuit must not be connected to any non-Class IE house load bus (NAN-S01or NAN-S02)nor have fast bus transfer capability to any such bus enabled. This restriction assures adequacyof voltage to ESFequipment.

The offsite circuit that is not connected to either 4.16 kV Class IE bus is inoperable.

APPLICABILITY The AC sources and sequencersare required to be OPERABLE in MODES I, 2, 3, and 4 to ensure that:

a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceededas a result of AOOsor abnormal transients; and

b. Adequatecore cooling is provided and containment OPERABILITY and other vital functions are maintained in the event of a postulated DBA.

(continued) i PALOVERDE UNITS1,2,3 B 3.8.1-6 REVISION57

AC Sources- Operating B 3.8.1 BASES SURVEILLANCE The required steady state frequency range for the DG is REQUIREMENTS 60 +0.7/-0.3 Hz to be consistent with the safety analysis to (continued) provide adequate safety injection flow. In accordance with the guidance provided in Regulatory Guide 1.9 (Ref. 3),

where steady state conditions do not exist (i.e.,

transients), the frequency range should be restored to within +/- 2% of the 60 Hz nominal frequency (58.8 Hz to 61.2 Hz) and the voltage range should be restored to within +/- 10%

of the 4160 volts nominal voltage (3740 volts to 4580 volts). The timed start is satisfied when the DG achieves at least 3740 volts and 58.8 Hz within 10 seconds.

At these values, the DGoutput breaker permissives are satisfied. Then, with concurrent or subsequent detection of a loss of voltage on the ESF bus, the DGbreaker would close, reenergizing the bus.

Steady state and transient voltage and frequency limits have not been adjusted for instrument accuracy. Error values for specific instruments are established by plant staff to derive the indicated values for the steady state and transient voltage and frequency limits.

Specific MODErestraints have been footnoted where applicable to each 18 month SR. The reason for "This Surveillance shall not be performed in MODE1 or 2" is that during operation with the reactor critical, performance of this SR could cause perturbations to the EDSthat could challenge continued steady state operation and, as a result, unit safety systems; or that performing the SR would remove a required DGfrom service. The reason for "This Surveillance shall not be performed in MODE1, 2, 3, or 4" is that performing this SR would remove a required offsite circuit from service, perturb the EDS, and challenge safety systems.

SR 3.8.1.1 This SR assures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and indicated availability of offsite AC electrical power.

The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are connected to their preferred power source, and that appropriate independence of offsite circuits is maintained.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

PALOVERDEUNITS 1,2,3 B 3.8.1-23 REVISION57

ACSources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 REQUIREMENTS (continued) These SRshelp to ensure the availability of the standby electrical power supply to mitigate DBAsand transients and to maintain the unit in a safe shutdowncondition.

To minimize the wear on moving parts that do not get lubricated whenthe engine is not running, these SRsare modified by a Note to indicate that all DGstarts for these Surveillances may be preceded by an engine prelube period and followed by a warmupperiod prior to loading.

For the purposes of SR3.8.1.2 and SR 3.8.1.7 testing, the DGsare started from standby condition. Standby conditions for a DGmeanthat the engine lube oil and coolant temperatures are maintained consistent with manufacturer recommendations. Additionally, during standby conditions the diesel 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 recommendsa modified start in which the starting speed of DGsis limited, warmupis limited to this lower speed, and the DGsare gradually accelerated to synchronousspeed prior to loading. This is the intent of Note 3, which is only applicable whensuch modified start procedures are recommended by the manufacturer.

SR3.8.1.2 Note 4 and SR 3.8.1.7 Note 2 state that the steady state voltage and frequency limits are analyzed values and have not been adjusted for instrument accuracy.

The analyzed values for the steady-state diesel generator voltage limits are _ 4000 and _ 4377.2 volts and the analyzed values for the steady-state diesel generator frequency limits are _ 59.7 and _ 60.7 hertz. The indicated steady state diesel generator voltage and frequency limits, using the panel mounteddiesel generator instrumentation and adjusted for instrument error, are _ 4080 and _ 4300 volts

[ (Ref. 12), and _If 59.9 respectively. and _

digital 60.5 hertz (Ref.

Maintenanceand 13), Equipment Testing (M&TE)is used instead of the panel mounteddiesel generator instrumentation, the instrument error maybe reduced, increasing the range for the indicated steady state voltage and frequency limits.

(continued)

[ PALOVERDE UNITS1,2,3 B 3.8.1-24 REVISION 50