"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.

Text

Forwards marked-up Draft Tech Specs,Per Util 850712 Commitment.Corrections,Comments,Graphs,Tables,Figures & Justifications Included.Meetings to Resolve Issues or Questions Scheduled for 850805 & 06 at NRC
	ML17299A468
Person / Time
Site:	Palo Verde
Issue date:	08/02/1985
From:	Van Brunt E; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G; Office of Nuclear Reactor Regulation
References
	ANPP-33162-EEVB, TAC-60706, NUDOCS 8508050402
	Download: ML17299A468 (168)
	v • d • e

g C',

c REGULATORY li FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR!8508050402 DOC ~ DATE: 85/08/02 NOTARI2ED:

NO DOCKET FACIL:STN 50 529 Palo Verde Nuclear Stationr Unit 2g Arizona Publi 05000529 AUTH,NAME AUTHOR AFFILIATION VANBRUNT.E~

Arizona Publ ic Ser vice'o, RECIP ~ NAMEI RECIPIENT AFFILIATION KNIGHTON g*G ~ Pl ~

Licensing Branch 3

SUBJECT:

Forwards marked-up draft Tech Specs<per util.850712 commitment~Corrections<comments<graphsitablesrfigures'8 Justifications included. Meetings to resolve issues or~

Questions scheduled for. 850805 L 06 at NRG ~

AJ DISTRIBUTION CODE:

B001D COPIES RECEIVED:LTR.

TITLE: Licensing Submittal:

PSAR/FSAR Amdts 8 Related Correspondence NOTES:Standardized plant.

05000529 RECIPIENT ID CODE/NAME.

NRR/DL/ADL-NRR LB3 LA COPIES LTTR ENCL=

1 0

1 0 RECIPIENT ID CODE/NAME NRR LB3 BC LICITRArE 01

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INTERNAL ACRS 41 ELD/HDS3 IE/DEPER/EPB 36 NRR ROErM ~ L.

NRR/DE/CEB il NRR/DE/EQB 13, NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40.

NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CPB 10.

NRR/DSI/ICSB 16 NRA/DSI/PSB 19 NRR/DSI/RSB 23 RGN5 6

1 0

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2 2

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1 PNL" GRUEL'gR 1

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/RAB 22'4 RM/

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Arizona Nuclear Povver ProJect P.O. SOX 52034 o

PHOENIX, ARIZONA85072-2034 Mr. George W. Knighton, Chief Licensing Branch No.

3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 ANPP-33162-EEVB/JRP August 2, 1985

Subject:

Palo Verde Nuclear Generating Station Unit 2 Docket No. 50-529 Plant Technical Specifications (Draft)

File:

85-055-026

Reference:

1)

Letter from G. Knighton,

NRR, to E. E. Van Brunt, ANPP, dated June 21, 1985 2)

Letter from E. E. Van Brunt, ANPP, to G. Knighton, NRR, dated July 12, 1985

Dear Mr. Knighton:

Reference 1 transmitted to ANPP a "Draft" copy of PVNGS Unit 2 Technical Specifications.

ANPP was to review this draft and make appropriate comments and changes.

By copy of Reference 2,

ANPP supplied the first set of comments along with a revised schedule as to the need date of Unit 2

Tech.

Spec.

issuance.

We also identified that marked up tables, graphs and figures would be supplied by August 15, 1985.

By copy of this letter, all the corrections,

comments, graphs, tables and figures for PVNGS Unit 2

Tech.

Specs.

and their justifications are being transmitted to you.

Meetings to resolve these

issues, or any questions, are to be held August 5 and 6, 1985, in your offices.

The next step is the issuance and review of the PVNGS Unit 2 proof and review.

8508050402 850802 PDR ADOC'K 05000529 g

A PDR

<<I II I,

<<f l<<

II I,

I II 5 I.

Mr. George W. Knighton, Chief U. S. Nuclear Regulatory Commission Page Two ANPP-33162-EEVB/JRP If you have any questions, please contact me.

Very truly yours, GLA~

E. E.

Van Brunt, Jr.

Executive Vice President Prospect Director EEVB/SRF/)le cc:

Director, Region V, USNRC E. A. Licitra R. P.

Zimmerman S. Brown

Justifications For Enclosed PVNGS Unit 2 Tech.

Spec.

Changes The following pages contain administrative changes such as typographical and unit specific number changes.

Index VIII pg. 3/4 3-5 Index XIII pg. 3/4 1-21 pg. 3/4 3-12 pg. 3/4 3-13 pg. 3/4 3-14 Add Cathodic protection to 3/4 8.1.

Action 2

Change 6.5.1.6.h to 6.5.1.6.G.

There is not an Item h.

Add Cathodic protection Item C2a add Figure 3.1.2a.

Delete the last 2 sentences in the 8$/ Footnote.

Table 3.3-2a does not exist.

The table for the CPL addressable constants was deleted for all CE units.

Delete reference to Footnote 9 for Item C.2 "Channel Functional Test."

The old footnote is deleted and the new footno'te doesn't apply to CPC's.

Item III.A. "Channel Functional Test" change Footnote 10 to 9.

Footnote 10 does not exist.

pg. 3/4 3-15 Delete old Footnote 9

because the 2.2.2 Tech.

Spec.

no PS'g Pg.

Pg.

PS'S'g.

PS'S'/4 3-49 3/4 3-50 3/4 3-51 3/4 3-52 3/4 3-53 3/4 3-54 3/4 3-64 3/4 6-30 3/4 7-42 longer exists.

Change Footnote 10 to 9.

Typo's, unit specific numbers and added verbage for switch identification.

l il l

pg. 3/4 7-41

,pg. 3/4 8-3 pg. 3/4 8-5 Action b.

Delete "...In recirculation Mode..."

and add the word "operation" in its place.

This is a typo.

When action A was changed between Unit 1 Low Power License and Full Power License the change to Action b. was not made.

Delete Item B and use insert.

This brings our Spec. into compliance with the previously approved McGuire Spec.

which was an agreed position between NRR and ANPP during PVNGS Unit 1 Pull Power License changes.

Footnote 0

Remove "This".

Delete Item 5 This is replaced with Item C.2 on pg. 3/4 8-3a.

Change Item d to e Typo.

PS'S'S'g.

PS'S'S'S'S'S'S'S'S'S'S'S'S'S'S'S'/4 8-7 3/4 8-16 3/4 8-23 3/4 8-24 3/4 8-26 3/4 8-27 3/4 8-28 3/4 8-29 3/4 8-34 3/4 8-35 3/4 8-37 3/4 8-38 3/4 8-39 3/4 8-40 3/4 8-43 3/4 8-44 3/4 8-45 3/4 8-46 3/4 8-47 3/4 8-48 3/4 8-49 Change Items g to f and f to g Typo.

Typo's, unit specific numbers and added verbage for over-current devices.

n a t'P n

1

~,

t

pg. 3/4 8-8a pg. 3/4 9-1 pg. 3/4 10-1 pg. B3/4 3-4 Cathodic Protection Add this Spec.

to be consistent with 'Unit l.

Change 40 gpm in action statement to 26 gpm.

This is to be consistent with changes made in 4.1.2.2.b.

Same as above.

3/4.6.5.1 should be changed to 3/4 6.4.1.

The following graphs are being supplied for the PVNGS Unit 2 Tech.

Specs.

pg. 3/4 1-5 pg. 3/4 1-12 pg. 3/4 1-23 pg. 3/4 1-24 pg. 3/4 1-31 pg. 3/4 1-32 pg. 3/4 2-6 pg. 3/4 2-7 pg. 3/4 2-10 pg. 3/4 3-10 pg. 3/4 4-28 pg. 3/4 4-30 pg. 3/4 7-26 pg. B3/4 4-10 pg. B3/4 5-2 pg. B3/4 5-3 pg. B3/4 5-4 pg. B3/4 6-3 pg. B3/4'-4 pg. 3/4 3-29 Item 10 Add H "180+/180+*H" "H

The response time for monitors XJ-SgA-RU-29 and XJ-SgB-RU-30 to trip on radiation is not included in the response time measurements for dampers M-HJA-MOl, M-HJA-M52, M-HJB-M01 and M-JHB-M55."

This clarifies that the monitors are not included in the response time measurements for dampers.

r-

"i E

I, II I

pg. 3/4 3-6 pg. 3/4 3-74 pg. 3/4 6-12 pg. 3/4 6-15 pg. 3/4 3-22 pg. 3/4 3-23 Add "5 of" to action statements A and B.

a "...per hour at 5 of the..."

b "...per hour at 5 of the..."

These additions are to bring Spec.

3.3.3.7 in agreement with Spec. 4.6.1.5.

Replace Action 37 with insert.

This change is being made to bring the Tech.

Spec.,

Preplanned Alternate Sampling Program and Region V desires into compliance.

Make noted changes in Table 4.6-1 to bring PVNGS Unit 2

Tech.

Specs in compliance with Reg.

Guide 1.35 Section C.1.3 and C.3.

Suxveillance 4.6.2.1.6.

Change 273 psid to 275 psid.

T11is change is based on test data.

Item IX deleted 8 under applicable modes.

This footnote is no longer applicable.

Delete footnote No longer applicable.

pg. 3/4 7-41 pg. B3/4 4-8 pg. 3/4 3-36 Change hydrant numbers as shown.

These are unit specific.

Change numbers as shown to make applicable to Unit 2.

Delete CIASA K205 CIASB K205 as per recent design change.

These are now spares.

~

A

)

I P

I, 0

~

I,I F

gl

.85080504a2 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4. 7 PLANT SYSTEMS 3/4. 7..1 TURBINE CYCLE SAFETY VALVES.................................

AUXILIARYFEEDMATER SYSTEH.....................

CONDENSATE STORAGE TANK............-........-.

MAIN STEAM LINE ISOLATION VALVES..............

ATMOSPHERIC DUMP VALVES............-.-.-.-...-

~ ~ ~ ~ ~ ~ ~

PAGE 3/4 7"1 3/4 7-4 3/4 7-6 3/4 7-7 3/4 7-9 3/4 7-10 3l4.7.2 3/4..7. 3 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION..

ESSENTIAL COOLING MATER SYSTEH...................

3/4 7-11 3/4 7"12 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM..........................

3/4.7. 5 ULTIMATE HEAT SINK..................................

3/4.7. 6 ESSENTIAL CHILLED MATER SYSTEM......................

3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM............

3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM............

3/4o 7o 9 SNUBBERS ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

7-13 3/4 7-,.14 3/4 7-15 3/4 7-16 3/4 7-19 3l4 7-21 3/4.7.1O 3/4.7.11 FIRE SUPPRESSION MATER SYSTEM.......

SPRAY AND/OR SPRINKLER SYSTEMS......

C02 SYSTEMS..........................

FIRE HOSE STATIONS YARD FIRE HYDRANTS AND HYDRANT HOSE HALON SYSTEMS..................

~ ~ ~ ~ ~ ~

~ ~ ~

~ ~ ~ ~

~ ~ ~ ~ ~ ~

HOUSES.

SEALED SOURCE CONTAMINATION..................

FIRE SUPPRESSION SYSTEMS 3/4 7-27

~

0 ~ ~ ~

3/4 7-29 3/4 7-32 7-35 7"37 7-40 3/4 7-42 3l4

....-3/4 3/4 3/4.7.12 3/4.7.13 FIRE-RATED ASSEMBLIES...........;...................

SHUTDOWN COOLING SYSTEM....,..............

~ ~ ~ ~

3/4 7-43 3/4 7"45 3/4.7. 14 CONTROL ROOM AIR TEMPERATURE...... -...

~ -. - - - -.. -.. -.

3/4.8 ELECTRICAL POWER SYSTEMS

~ ~ 0 0 3l4 7-46 3/4.8.1 A. C.

SOURCES OPERATING..

SHUTDOWN;..

~~D~.PACKS':VXO~

3/4 8"1 3/4 8-8 3~$

PALO VERDE - UNIT 2 VIII

4I O~

0

BASES INOEX SECTION 3/4.7 PLANT SYSTEMS 3/4.7. 1, TURBINE CYCLE......'.......-....... -... -.. -.....

3/4.7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.........

3/4.7..3 ESSENTIAL COOLING WATER SYSTEM..........................

3/4.7.4 ESSENTIAL SPRAY POND SYSTEM........,...............-..>>..

3/4.7.5 ULTIMATE HEAT SINK......................................

3/4 7o6 ESSENTIAL CHILLED WATER, SYSTEM..........................

~

PAGE B 3/4 7-1 B 3/4 7-3 B 3/4 7-3 B 3/4 7-4 B 3/4 7-4 B 3/4 7-4 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM................

B 3/4'7-5 3/4.7.8 ESF PUMP ROOM AIR EXHAUST CLEANUP SYSTEM................

B 3/4 7-5 3/4.7. 9 SNUBBERSo

~

~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ o ~ ~ ~ ~ o ~ ~ ~

~ o ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~

B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-7 3/4.7.11 FIRE SUPPRESSION SYSTEMS....................,.............

B 3/4 7-7 3/4.7.12 FIRE"RATED ASSEMBLIES...........

B 3/4 7-8 3/4.7.13 SHUTDOWN COOLING SYSTEM.............

3/4.7.14 CONTROL ROOM AIR TEMPERATURE............................

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2',

and 3/4.8.3

.A.C.

SOURCES, D.C.

SOURCES, and

~

OHSITE POWER DISTRIBUTION SYSTEMS........:.......

B 3/4 7"8 B 3/4 7-8 B 3/4 8-1 3/4.8.4 ELECTRICAL EgUIPMEHT PROTECTIVE DEVICES.................

B 3/4 8-3 3/4. 9 REFUELIHG OPERATIONS 3/4. 9. 3 3/4. 9. 4 DECAY TIME........

1 CONTAINMENT BUILDING PEHETRATIONS.

3/4. 9. 5 COMMUNICATIONS 3/4o go 1 BORON CONCEHTRATIONo ~ ~ ~ o ~ ~

~ ~ ~

~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~

3/4. 9. 2 INSTRUMENTATION....

B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 PALO VERDE " UNIT 2 XIII

~

t O~

il~

REACTIVITY CONTROL SYSTEMS 3/4. 1. 3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING.CONDITION FOR OPERATION

3. 1.3. 1 All full-length (shutdown and regulating)

CEAs, and all part-length CEAs which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 6.6 inches

(,indicated position) of all other CEAs in its group.

In addition, the position of the part length CEAs Groups shall be limited to the insertion limits shown in Figure 3. 1-2A.

APPLICABILITY:

MODES 1" and 2".

ACTION:

a.

b.

C.

With one or more full-length CEAs inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With more than one full-length or part-length CEA inoperable or misaligned from any other CEA in its group by more than 19 inches (indicated position),

be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one or more full-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with Figure 3. 1-2B and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned CEA(s) is either:

1.

Restored to OPERABLE status within its above specified alignment requirements, or 2.

Declared inoperable and the SHUTDOWN MARGIN requirement of Specification

3. 1. 1. 1 is satisfied.

After declaring the CEA(s) inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification

3. 1.3.6 provided:

a)

Within 1'hour the remainder of the CEAs in the group with the inoperable CEA(s) shall be aligned to within 6.6 inches of the inoperable CEA(s) while maintaining the allowable CEA sequence and insertion limits shown on Figures

3. 1-3 a

3. 1-4; the THERMAL POWER level shall be restric ed pur-suant to Specification

3. 1.3.6 during subsequent operation. 3 "See Special Test Exceptions

3. 10.2 and

3. 10.4.

'ALO VERDE - UNIT 1 3/4 1-21

il~

TABLE 3.3-1 Continued)

TABLE NOTATIONS "With the protective system trip breakers in the"closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

8The provisions of Specification 3.0.4 are no applicable.

(a)

Trip may be manually bypassed above 10-4X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10-~X of RATED THERMAL POWER.

(b)

Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.

(c)

Trip may be manual.ly bypassed

.below lX of RATED THERMAL POWER; bypass shall'e automatically removed when THERMAL POWER is greater than on equal to. 1X of RATED THERMAL POWER.

(d)

Trip may be bypassed during testing pursuant to Special Test Exception

3. 10. 3.

(e)

See Special Test Exception 3.10.2.

(f)

There are four channels, each of. which is comprised of one of the four reactor trip breakers, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice).

ACTION STATEMENTS ACTION 1 ACTION 2 With the number'f channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the protective system trip breakers.

With the number of channels OPERABLE one less than tne-Tota'l

.Number'i':.Channels STAFTUP and/"<'OWER OPERATION may. conti i-provided the inoperable channel is placed in the bypassed or tripped condition.within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

If the inoperable channel is

bypassed, the desirabi.lity of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5:1.6.j('he channel ehail be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

PALO VERDE - UNIT 2 3/4 3-5

'I il~

il~

O~

TABLE 3.3-2 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT

RESPONSE

TIME II.

RPS LOGIC A.

Matrix Logic B.

Initiation Logic III.

RPS ACTUATION DEVICES A.

Reactor Trip Breakers B.

Manual Trip Not Appl icable Hot Applicable Not Applicable Not Applicable Neutron detectors are exempt from response time testing.

The response time of the neutron flux signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel..

Response

time shall be measured from the output of the sensor.

Acceptable CEA sensor response shall be demonstrated by compliance wi'th Specifica-tion 3.1.3.4.

OThe pulse transmitters measuring pump speed are exempt from response time testing.

The response time shall be measured from the pulse shaper input.

¹¹Response time shall be measured from the output of the resistance temperature detector (sensor).

RTD response time shall be measured at least once per 18 months.

The measured response time of the slowest RTD shall be less than or e

3 secon A gus ments to t e C

a ressa e constants given in Table 3.3-2a s all be made to accomodate current values of the RTD time constants.

If the RTD time constant for a CPC channel exceeds the value corresponding to the penalties currently in use, the affected channel(s)'hall be declared inoperable until penalties appropriate to the new time constant re installed.

¹¹¹Response time s a

1 be measured from the output of the pressure transmitter.

The transmitter response time shall be less than or equal to 0.7 second.,

PALO VERDE - UNIT 2 3/4 3-Z2

TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS

(

m CD m

Z M

FUNCTIONAL UNIT I.

TRIP GENERATION A.

Process 1.

Pressurizer Pressure - High 2.

Pressurizer Pressure

- Low 1

3.

Steam Generator Level - Low 4.

Steam Generator Level - High 5.

Steam Generator Pressure

- Low 6.

Containment Pressure - High 7.

Reactor Coolant Flow - Low 8.

Local Power Density - High 9.

DNBR " Low B.

Excore Neutron Flux S

S S

S' R

R R

D (2, 4),

R (4, 5) 0 (2, 4),

R (4, 5)

M (S),

S (7)

CHANNEL CHANNEL CHECK CALIBRATION M

M M

M' M,

R (6)

M, R (6) 1 2

1 2

1 $

2 1 1 2 g

1 2

3)k 1

2 1

2 1 $

2 1

2 CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST RE VIREO l.

Variable Overpower Trip 2.

Logarithmic Power, Level - High C.

Core Protection Calculator System 1.

CEA Calculators 2.

Core Protection Calculators 0 (2, 4}, M (3, 4)

C (4)

R. (4}

1 2

M and S/U (1) 1, 2, 3, 4, 5

and "

I R ',R(6) 1,2 D (2, 4),

R (4, 5)

';M (9)

R (6) 1, 2

)

M (B), S'(7)

1 Oi

TABLE.4.3-1 (Continued)

REACTOR PR TECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS

(

Pl Kl Cl foal FUNCTIONAL UNIT D.

Supplementary Protection System Pressurizer Pressure - High II.

RPS LOGIC CHANNEL CHANNEL CHECK CALIBRATION CHANNEL MODES IN MHICH FUNCTIONAL SURVEILLANCE TEST RE UIRED 1,

2 1

A; Matrix Logic 8.

Initiation Logic A.

Reactor Trip Breakers III. RPS ACTUATION DEVICES I

B.

Manual Trip N.A.

N.A.

1, 2, 3", 4+, 5" 3A 4*

Pk M, R'-P9,0):;

1, 2, 3", 4*j 5" M

1 2

3A 4A 5A

il~

ik~

TABLE 4.3-1 Continued)

TABLE NOTATIONS (2)

(3)

(6)

(7)

(s)

With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

Each STARTUP or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if ro performed in the previous

.7 days.

Heat balance only (CHANNEL FUNCTIONAL TEST not included),

above 15K of RATED THERMAL POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X.

During PHYSICS

TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

Above 15K of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

After each fuel loading and prior to exceeding 70K of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements.

This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the charm'el as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.

Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate.

The flow measurement uncertainty may be included in the BERRl term in the CPC and is equal to or greater than 4X.

Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differentral pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations.

thl CHANNEL FUNCTIONA vent>cation that~ (~(z t

CPC per-Specification 2.2.2.

. At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the.undervoltage and shunt trips.

PALO VERDE " UNIT 1 3/4 3-X5

O~

0 il

DISCONNECT SMITCHES 2.

3.

4.

5.

7.

8.

9.

10.

12.

13.

14.

15.

16.

17.

QAL'PCS 18.

19.

20.

22.

23..

24.

SG 1 1-ine 2 Atmospheric Dump'dai~~ Qiovc o Alit v Valve~ SGB-HY-178A Ann SOS-H). nS R, SG 2 line 1 Atmospheric Dump Ua~QK 5>lbnlo'~n Alt Valve~ SGB-HY-185A+zp 5c>s-A~- n~ e ZANTi Auxiliary Spray Valve CHB-HV-203 Letdown to Regenerative Heat Exchanger I olation, CHB-UV-515 Reactor Coolant Pump Controlled Bleedoff, CHB-HV-505 Auxiliary Feedwater Pump B to SG 1 Control Valve, AFB-HV-30 Auxiliary Feedwater Pump B to SG 2 Control Valve, AFB-HV-31 Auxiliary Feedwater Pump B to SG 1 Block Valve, AFB-HV-34 Auxiliary Feedwater Pump B to SG 2 Block Valve, AFB-HV-35 Pressurizer Backup Heaters Banks B10, B18, A05 Control Safety Injection Tank 2A Vent Control SIB-HV-613 Safety Injection Tank 2B Vent Control SIB-HV-623 Safety Injection Tank 1A Vent Control SIB-HV-633 Safety Injection Tank 1B Vent Control SIB-HV-643 Safety Injection Tank Vent Valves Power Supply SIB-HS-18A aso~c~~~

SG 1 1 ine 2 AR Axmo~p~~~ OocnpUa~v~ So~ni)a Aim 4'G 2 line 1 ~A~w~P<~'~ ~"~P'4~~<~ &~~~~o ~

SGh HY"185B ano Qy-Hy-LSS 5 X~MAW Control BLDG Battery Room 0 Essential Exhaust Fan

'JB-JOIA'ontrol BLDG Battery Room B

Essential Exhaust Fan

'HJB-JOIB'attery Charger D Control Room Circuits PKQ-Ash ESF Switchgear Room Essential AHU HJB-Z03 LPSI Pump SIB-P01 Breaker Control Diesel Generator B Breaker Control Essential Spray Pond Pump SIB-P01 Breaker Control SMITCH LOCATION RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP PHB-M3205 PHB-M3206 PHB-3209 AND PKD-H14 PHB-3205 PBB-S04F PBB"S04B PBB-S04C PALO VERDE - UNIT 2 3/4 3-49

0

~

i

DISCONNECT SMITCHES 25.

26.

QQOV 27.

28.

29.

30.

31.

5LBHt-+

32.

Mpyt.g 33.

+PJ'S q 34.

35.

36.

37.

38.

39.

40.

41.

42.

43.

44.

45.

46.

47.

48.

49.

Essential Chiller ECB-801 Breaker Con~t ol E-PBB-.S04J~4.16KV Feeder

'c-ms-E-PBB-S04HY4.16KV Feeder Breaker o Load Center~>

iodniB -I e'I E-PBB-S04NK. 16KV Feeder Breaker to Load Center~~3~

PETS-L.SLu Auxiliary Feedwater Pump AFB-P01 Breaker Control Essential Cooling Water Pump EMB-POl Breaker Control E-PGB-L32B2F480V Main Feeder Breaker to Load Center~3PdqS-L:BB E-PGB-L34B2%480V Main Feeler Breaker to Load Center~)

P<iR - L 'b I E-PGB-L36B2-480V Main Fe&er Breaker to Load Center~~3 PC~%-WSLa Charging Pump No.

2 CHB-P01 Supply Breaker CHB-POl Diesel Engine Control Switch MHS-KA Diesel Engine Control Switch M SS-2.B Diesel Generator Control Switch H>- Z Diesel Generator Essential Exhaust Fan HDB-JOl Diesel Generator Fuel Oil Transfer Pump DFB-POl Battery Charger BD Contro1 Room Circuitef PKB-H16 Battery Charger B

Control Room Circuits PKB-H12 125 VDC Battery B Breaker Control Room Circuits 125 VDC Battery D Breaker Control Room Circuits CS Pump B Discharge to SD HX B SI-HV-689 Shutdown Coo 1ng LPSI Suction SIB-HV-656 LPSI-CS&from SD HX B X-.Tie SIB-HV-695 Shutdown Cooling Warmup Bypass SIB-HV-690 LPSI-CSKto SD HX B Crosstie SIB-HV-694 SD HX "B" to Rc Loops 2A/2B SIB-HV-696 SMITCH LOCATION PBB-S04G PBB-S04J PBB-S04H PBB-S04N PBB-S04S PBB-S04M PGB-L32B2 PGB-L34B2 PGB"L36B2 PGB-L32Cl DGB-C01 DGB-C01 DGB-C01 DGB-C01 DGB-C01 PHB-M3425 PHB-M3627 PKB-M4201 PKD-M4401 PHB"M3804 PHB-M3611 PHB-M3810 PHB-M3806 PHB-M3416 P HB-M3416 PALO VERDE UNIT 2 3/4 3-50

(gal ili il~

DISCONNECT SWITCHES 50.

LPSI-SD HX "B" Bypass S -HV-307 51.

SI Pump "B" Recirc

-UV"668

~

52.

SI Pump "B" Suction I 'IIII5~5 53.

SD Cooling LPSI Pump "B" S

I II~UP-g 54.

SD Cooling LPSI Pump "B" Suction SI-UV-654 55.

LP I I 5 ~SIC L I IA 5Igdd-g 56.

LPSI Header "B" to RC Loop 8

2B SI-UV-625 57.

V Outlet Isolation CHN Ol 58.

RWT Grav)ty Feed CH -HV"536 59.

Shutdown Cooling Temperature Control SIB-HV-658 60.

Shutdown Cooling Heat Exchanger Bypass Valve SIB-HV-693 61.

4.16 KV Bus PBB-S04 Feeder from XFMR NBN-X04 62.

4.16 KV Bus PBB-S04 Feeder from XFMR NBN-X03 63.

Electrical Penetr ati on Room B

ACU HAB"Z06 64.

Control Room HVAC Isolation Dampers HJB-M01/HJB"M55 65.

O.S.A.

Supply Damper HJB-M02 66.

O.S.A. Supply Damper HJB-M03 67.

R.C.S.

Sample Isolation Valve SSA-UV-203 68.

R.C.S.'ample Isolation Valve SSB-UV-200 69.

125 VDC Battery A Breaker

-Control. Room Circuits SWITCH LOCATION PHB-M3803'HB-M3611 PHB-M3805 PHB-M3611 PKD-B44 PHB-M3611 PHB-M3640 NHN-M7208 NHN-M7209 PHB-M3416 PHB-M3416 PBB-S04K PBB-504L PHB-M3640 RSP RSP RSP~ SSA- ~9 SSB 404-RSP'KA-M4101 PALO VERDE - UNIT 2 3/4 3-51

il

~

CONTROL CIRCUITS SMITCH LOCATION 2.

3.

4.

5.

7.

8.

9.

10.

12.

13.

x 14.

15.

16.

17.

18.

19.

'20.

21.

~ pgg-5o'lH ~

22.

e~'P~ 50++~23

--PSS 5044~

25.

26.

Auxiliary Feedwater Pump B to S/G 1 Isolation Valve AFB-UV~34 Auxiliary Feedwater Pump B. to S/B 1 Control Valve AFB-HQ30 Auxiliary Feedwater

~ump B to S/G 2 Isolation Vaive AFB-U~35 Auxiliary Feedwater Pump B to S/G '2 Control Valve AFB-H~31 Auxiliary Feedwater

~ump AFB-Pol Charging Pump No.

2 CHB"P01 Pressurizer Auxiliary Spray Valve CHB-HV203 Pressurizer liackup Heater Bank Letdown to Regen HX Isolation

~Valve CHB-UV515 RCP Cont Ble~e off Valve CHB-UVP05 Volume Contr~o ank Outlet Isolation Valve CHH-U~551 RMT Gravity Feed Isolation Valve CHE-HV536 5/G I line 2 Atmospheric Dump Valve Controll~lt SGB-HIC-178B S/G line 2 Atmospheric DumpQAulu. 5ci~hcilo giaZhLATI~

Valve SGB-HY-178A ~>> Sha-Hq-lib'/G 1 line 2 Atmospheric DumpUAiv~ S~~~ p;g~~q~~~

Valve SG -HY-178B AAD 5hb-g,q.~gag S

G 2 line Atmospheric Dump yAi ~~ ~~~~~,.-g

~

SGB HIC-185 S/G 2 1 ine 1 Atmospheric Dump Va~vc So~~oio Aim 2'So.

Valvd SGB-HY-185A Woo SCABS S/G 2 line Atmospheric Dump Ve~c 5m~~~~ pie, %bc.

Valve S

-HY-185B An 5pn-Hy- <gg-c D>ese1 enerator B Output Breaker Diesel Generator Building Essential Exhaust Fan HDB-JOl Diesel Generator B Fuel Oil Transfer Pumo DFB-P01 4.16 KV to 480V kE-~

4.16KV o

80V K~ ~~~ bR ~K.~~

4.16KV to 480V p,g.

f51-Supply Breaker ~ ~~~ gGL>~<<>< > <><

RSP RSP RSP RSP PBB-S04S PGB-L32C4 RSP RSP RSP RSP NHN"M7208 NHN-M7209 RSP RSP RSP RSP RSP RSP PBB-S04B DGB-B01 DGB"B01 PBB-S04H PBB-S04J PBB-S04N PGB-L32B2 PGB-L3482 PALO VERDE - UNIT 2 3/4 3"52 s

il~

0

CON 27.

28.

29.

30.

31.

Es P ~SB 32.

Ess 33.

34.

35.

36.

37.

38.

39.

40.

41.

42.

43.

44.

45 46.

47.

48.

TROL CIRCUITS 48&V-tMHLeb-1I 'll Supply Breaker te mAy curn.~ W8-~>i Battery Charger PKB-H12 Supply Breaker

.Battery Charger PKD-H14 Supply Breaker Backup Battery Charger PKB-H16 Supply Breaker sential Spray Pond Pump

-Pol ential Cooling Water Pump EWB-POl Essential Chilled Water Chi 1 1 er ECB-EOl Battery Room D Essential Exhaust Fan HJB-JOlA Battery Room B Essential Exhaust Fan HJB-J01B ESF Switchgear Room B

Essential AHU HJB-Z03 Electrical Penetration Room B

ACU Fan HAB-Z06 SIT Vent Valves Power Supply SIB-HS-18A SIT 2A Vent Valve SIB-HV613 SIT 2B~ent Valve SIB-HV~623 SIT 1A Vent Valve SIB"HV633 SIT 1B~ent Valve BIB-HV643 LPSI Pump B

SIB-Pol Containment Spray Pump B

Discharger to SD HX "B" Valve SIB-HV~689 LPSI Containment Spray from SD HX "B" X-tie Valve SIB-HV~95 Shutdown Cooling LPSI Suction Valve SIB-656 Shut own oo~ing warmup Bypass Valve SIB-89696 Q%-4 la LPSI Containment Spray to SO HX "B" X-tie Valve SIB-.HV694 SWITCH LOCATION PGB-L36B2-PHB"M3627 PHB"M3209 PHB-M3425 PBB-S04C PBB-S04M PBB-S04G PHB-M3206 PHB-M3207 PHB-M3203

, PHB-M3631 RSP RSP RSP RSP RSP PBB-S04F PHB-M3804 PHB-M3810 PHB-M3605 PHB-M3806 PHB-M3414 PALO VERDE - UNIT 2 3/4 3-53

il~

Q 0

CONTROL CIRCUITS SWITCH LOCATION 49.

50.

51.

'52.

53.

54.

55.

57.

58.

59.

60.

61.

62.

63.

64.

65.

66.

67.

68.

69.

70.

~

Valve SD HX "8" to RC Loops 2A/28 Valve SIB-HV~696 LPSI SD HX "8" Bypass Valve SIB-H~307 LPSI Pump 8 Recirc.

v~1 ve SIB-UV6ee-4 4S LPSI Pump 8 Suction From RWT SIB-HY~92-RC Loop to Shutdown Cooling Valve SIB-U~652 RC Loop to Shutdown Coolin Valve S

-UV~654 LPSI Hea er 8 to RC Loop 2A Valve SIB-UV~615 LPSI Header 8 to RC Loop 28 Valve SIB-UV625 SBC "B" Temperature control Val.ve SIB-HV-658 Control Room Ventilation Isolation

'ampers HJB-M01/HJB-M55 O.S.A. Supply Damper HJB-M02

~

~ ~-

O.S.A.

Supply Damper HJB-M03 - - -

~

Diesel Generator "8" Emergency Start Normal Offsite Power Supply Breaker Alternate Offsite Power Supply Breaker Battery "8" Breaker Battery "D" Breaker RCS Sample Isolation Valve SSA-UV-203 RCS Sample Isolation Valve SSB-UV-200

~

Train "8" Pumps Combined Recirc to RWT SIB-UV"659 Shutdown Cooling Heat Exchanger Bypass Valve SIB-UV-693 Battery "A" Breaker PHB-M3415 PHB-M3803 PHB-M3609 PHB-M3805 PHB-M3604 PKD-844 PHB-M3606 PHB-M3621 PHB-M3412

~

4 QQp

~

~ g.bP eveP PBB-S04K PBB"S04L PKB-M4201 PKD-M4401

~

SSA-~

'~G-woq RSP PHB-M3413 PKA-M4101 PALO VERDE - UNIT 2 3/4 3-54

0

TABLE 3. 3-11'(Continued)

FIRE DETECTION INSTRUMENTS FIRE ELEVATION INSTRUMENT LOCATION ZONE TOTAL NUMBER OF INSTRUMENTS" HEAT FLAME SMOKE (ay)

(x/y)

'x/y) 34A 348 35A 358

'36 37C 37D 378 37A 39A 398 7O'0' 7o'O'0 I

70'&

88'0'&

88'0'o'S'8'CW P 'r(lp '.iTi. - Train A ECW Pump Rm. - Train 8 FACHM~

Shutdown Cooling Ht. a~~".i Train A

~<4A~i+

Shutdown Cooling Ht. ae-&gr.

Train 8 Reactor Makeup and Boric Adddk pk p

Piping Penetration Rm.-

Train A Piping Penetration Rm.

Train 8 Corridors - East Corridors West Pipeways - Train A Pipeways Train B

2/0 2/0 4/0 4/0 1/0 5/0 4/0 11/0 11/0 s/o 8/0-42A 100'lect.

Penetration Rm.

~Tr.

A (Chan.

C) 0/1 0/25 428 42C 1OO'00'lect.

Penetration Rm.

Tr.

8 (Chan.

8) 0/1 Corridors - East 8 Southeast 0/2 0/24 3/35 42D 46A 46B 100'OO'00'00'orridor

- West Charging Pump and Valve Gallery Rm. - Train A Charging Pump and Valve Gallery Rm. - Train 8

Charging Pump and Valve Gallery Rm. - Train E

0/1 2/29 0/3 0/3 0/3 PALO VERDE - UNIT 2 3/4 3-64

0

TABLE 3.6-1 (Continued}

CONTAINMENT ISOLATION VAlVES VALVE NUMBER PENETRATION NUMBER FUNCTION MAXIMUM ACTUATION TIME (SECONDS)

SG-UV 170 ¹ 1

SG-UV 171¹

,2 SGE-UY 169¹ 1

Ec 2 SG-UV 180¹ 3

SG-UV 181¹ 4

SGE-UV 183¹ 3

8( 4 SGA-UY 1133¹ 1-4 SGA-UV 1134¹ 1"4 SGB-UV 1135A¹ 1-4 SGB-UV 1135B¹ 1-4 SGB-UV 1136A¹ 1"4 SGB-UY 1136B¹ 1-4 SGA-UV 174¹ 8

SGB-UV 132¹ 8

SGB-UV 137¹ 10 SGA-UY 177¹ 10 C

SGB-UY 130¹ 11 SGA-UV 172¹ 11 SGB-UV 135¹ 12 F.

NORMALLY OPEN " ESF ACTUATED CLOSED Main steam isolation Main steam isolation Main steam isolation bypass Main steam isolation Main steam isolation Main steam isolation bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam trap/bypass Steam generator feedwater Steam generator feedwater Steam generator feedwater Steam generator feedwater

.Downcomer FIV

~~

.Downcomer FIV Downcomer FIY N.A.*

N.A.~

N.A.

N.A."

N.A.

N. A.

N.A.

N. A.

¹Not Type C tested "Valves also covered by

'3 Specification 3/4:7.

.4 PALO VERDE - UNIT 2 3/4 6-30

il 0

PLANT SYSTEMS HALON SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.6 The following Halon systems shall be OPERABLE.

a.

Train A Remote Shutdown Panel

Room, Zone 10A - Control Building 100 ft. Elevation b.

- -.Train B Remote Shutdown Panel

Room, Zone 10B - Control Building 100 ft. Elevation APPLICABILITY:

Mhenever equipment protected by the Halon system is required to be OPERABLE.

ACTION:

b.

Nth one or more of the above required Halon systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire~

suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.?.118aEach. of the above required Halon systems shall be demonstrated OPERABLE:

ae b.

C.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic} in the flow path is in its correct position.

At least once per 6 months by verifying Halon storage tank weight to be at least 95K of full charge. weight and, pressure to be at least 90K of full charge pressure.

\\

At least once per 18 months by:

2.

Verifying the system actuates manually and automatically, upon,

receipt of a simulated test signal, and S

Performance of g flow test through headers and nozzles to assule no blockage."

PALO VERDE - UNIT 2 3/4 7-42

ll~

il ik

ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 4.

Verifying the diesel starts from ambient condition and acceler-ates to at least 600 rpm in less than or equal to 10 seconds."

The generator voltage and frequency shall be 4160 + 420 volts and 60 1.2 Hz within.lO 'seconds after the start signal.

The diesel generator shall be started for this test by using one of the following signals:

a)

--b) c}

d)

Manual.

Simulated loss-of-offsite power by itself.

Simulated loss-of-offsite power in conjunction with an ESF actuation test signal.

An ESF actuation test signal by itself.

5.

Verifying the generator is synchronized, loaded to greater than or equal to 5500 kW in less than or equal to 5 minutes, and operates with a load greater than or equal to 5500 kW for at least an additional 60 minutes, and 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b.

A t once per 31 days and after each o

1 where the peri reater than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by or and removing accumulated water rom e

a nks.

Sa.q

<<Sa.r c;

By sampling new fuel oil in accordance with ASTM D4057-81 prior to addition to the storage tanks and:

1.

By verifying in accordance with the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:

a)

An API Gravity of within 0.3 degrees at 60 F or a specific gravity of within 0.0016 at 60/60'F, when compared to th.=..

supplier's certificate or an absolute specific gravity at 60/60 F of greater than or equal to 0.83 but less tha;.

oJ equal to 0.89 or an API gravity at 60'F of greater than or equal to 27 degrees but less than or equal to 39 degrees, b)

A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by comparison with the supplier's certification, The diesel generator start (10 seconds) from ambient conditions shall, be per-formed at least once per 184 days in hese surveillance tests.

All other.en-gine starts for the purpose of surveillance testing may be preceded by an engine prelube period and/or other warmup procedures recommended by the manu-facturer so that mechanical stress and wear on the diesel engine is minimized.

PALO VERDE - UNIT 2 3/4 8-3

Ii 0

kAS a.r paxnKb

0 0

ELECTRICAL POMER SYSTEM SURVEILLANCE RE UIREMENTS (Continued

~ <~i "-t.~Y ther properties specified i of ASTM-D975-19?7 ~akim~

and Reg ory Guide 1.

evision 1, October 1979, Posi-tion 2.a.,

whe in accordance with ASTM-D975-1977; analysis 's e comp within 14 days after obtaining

'e ut may be performed a

addition of new fuel o l.

A swgg Sos..rr.,

/A-t least once Per 18.months during shutdown by

1.

". Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its.manufacturer's recommendations for this class of standby service.

2.

Verifying the generator capability to reject a single largest load of greater than or equal to 839 kM (Train B AFW pump) or 696 kM (Train A HPSI pump) while maintaining voltage at 4160 + 420 volts and frequency at 60 + 1.2 Hz.

3.

Verifying the generator capability to reject a load of 5500 kM without tripping.

The generator voltage shall not exceed 6240 volts during and following the load rejection.

4.

Simulating a loss-of-offsite power by itself; and:

a)

Verifying deenergization of the emergency busses and load shedding from the emergency busses.

b)

Verifying the diesel starts on the auto-start signal, energizes the emergency busses with. permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.

After'ner'gization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 volts and 60 + 1.2/-,0.3 Hz during this test.

5.

Verifying that on an ESF actuation test signal (without loss-of-offsite power) the diesel generator starts on the auto-start signal arid operates on standby for greater than or equal to 5 minutes.

The steady-state

.generator voltage and frequency shall be 4160

+ 420 volts and 60 + 1.2 Hz within 10 seconds after the auto-start signal; the generator voltage and frequency shall be maintained within these limits during this test.

6..

Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and PALO VERDE UNIT 2 3/4 8-5

0

ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 11.

Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross connection lines.

12.

Verifying that the automatic load sequence timer is OPERABLE with the interval between each load bloc'k within + 1 second of its design interval.

13.

.Verifying that the following diesel generator lockout features

. prevent diesel generator starting only when required:

a)

(turning gear engaged) b)

(emergency stop)

At least once per 10 years or after any modifications which covld affect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 600 rpm (steady-state generator voltage and frequency of 4160 + 420 volts and 60 + 1.2 Hz) in less than or equal to 10 seconds.

.'At least once per 10 years by:

1.

Draining each fuel oil. storage

tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or the equivalent, and 2.

Performing a pressure test of those portions of the diesel fuel oil system designed.to Section III, subsection ND of the ASME Code at a test pressure equal to llOX of the system design pi essure.

4.8. 1. 1.3

~Re orts All diesel generator failvres, valid or nonvalid, shall be reported to the Commission within 30 days in a Special Report pursuant to Specification 6.9.2.

Reports of diesel generator failures shall include the information recommended in Regulatory Position C. 3. b. of Regulatory Guide 1. 108, Revision 1, August 1977. If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1. 108, Revision 1, August 1977.

r PALO VERDE - UNIT 2 3/4 8-7

il~

0

ELECTRICAL POWER SYSTEMS A.C.

SOURCES LIMITING CONDITIONS FOR OPERATION 3.8. 1.3 The Cathodic Protection System associated with the Diesel Generator Fuel Oil Storage Tanks shall be OPERABLE.

APPLICABILITY: At al 1 times.

ACTION:

a.

With Cathodic Protection System inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of malfunction and the plans for restoring the system to OPERABLE status.

b.

The provisions of Specification 3; 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.8. 1.3 Ver ify that the Cathodic Protection System is OPERABLE at the follow-ing time intervals:

Verify at least once per 92 days that the Cathodic Protection rectifiers are OPERABLE and have been inspected in accordance with Regulatory Guide 1. 137.

2.

Verify at least once per 18 months that the Cathodic Protection is OPERABLE and providing adequate protection against corrosion in accordance with Regulatory Guide 1. 137.

PALO VERDE - UNIT Z-3/4 8-Ba

ik~

il il

ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS OPERATING LIMITING CONDITION FOR OPERATION 3.8.3.1 The following electrical busses shall be energized in the specified manner with tie breaker open between redundant busses within the unit.

a.

Train "A" A.C. emergency busses consisting of:

1.

4160-volt ESF Bus ¹E-PBA-S03 2.

480-volt ESF Load Center ¹E-PGA-L31 a.

MCC E-PHA-M31 3.

480-volt ESF Load Center ¹EPGA-L33 a.

MCC E-PHA-M33 b.

MCC E-PHA-M37 4.

480-volt ESF Load Center ¹E-PGA-L35 a.

MCC E-PHA-M35 b.

Train "B" A.C. emergency busses consisting of:

1.

2.

3.

4160-volt ESF Bus ¹E-PBB-S04 480-volt ESF Load Center ¹E-PGB-L32 a.

MCC E-PHB-M32 b.

MCC E-PHB-M38 480-volt ESF Load Center ¹E-PGB-L34 a.

MCC E-PHB-M34 480-volt ESF Load Center ¹E-PGB-L36 a.

MCC E-PHB-M36 c.

120-volt Channel A Vital A.C. Bus ¹E-PNA-025 energized from its

,associated inverter connected to D.C.

Channel A."

d.

e.

g.

h.

120-volt Channel B Vital A.C. Bus ¹E-PNB-026 energized from its associated inverter connected to D. C.

Channel B.

120-volt Channel C Vital A.C.

Bus ¹E-PNC-02? energized from its associated inverter connected to D.C.

Channel C.*

120"volt Channel 0 Vital A.C.. Bus ¹E-PND-028 energized from its associated inverter connected;to D.C.

Channel D."

125-volt D.C.

Channel A energized from Battery Bank E-PKA-Fll.

125-volt D.C.

Channel B energized from Battery Bank E-PKB-F12.

125-volt D.C.

Channel C energized from Battery Bank E-PKC-F13.

125-volt D.C.

Channel D energized from Battery Bank E-PKD-Fl4.

"Two inverters may be disconnected from thei~ Q.C.

bus for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , as necessary, for the purpose. of performing an equalizing charge on their associ-ated battery bank provided (1) their vital busses are energized, and (2) the vital busses associated with the other battery bank are energized from their associated-inverters and connected to their associated D.C. bus.

PALO VERDE - UNIT 2 3/4 8"16

i~

4k 0

TABLE 3. 8-2 (Continued}

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE NUMBER E-NHN-M1533 E-NHN-M1534 E-NHN"M1517 E-NHN-M1902 E-NHN-M1904 E-NHN-M1907 E-NHN-M1911 E-NHN-M1912 E-NHN-M2008 E-NHN-M2003 E-NHN-M2004 E-NHN-M2006 E-NHN-M2007 E"NHN"M2803 E-NHN-M2804 BACKUP DEVICE NUMBER E-NHN-M1502B E-NHN-M1535 E"NHN-M1535 E-NHN"M1917A E-NHN-M1917B E-NHN-M1917 E-NHN-M1917 E-NHN-M1917 E-NHN-M2010 E-NHN"M2010 E-NHN"M2010 E-NHN-M2010A E-NHN-M2016 E"NHN-M2827A E"NHN-M2827A SERVICE DESCRIPTION REACTOR CAVITY FAN D DISCH DAMPER M-HCN-M02D CTMT BLDG MONO HOIST 1 TON M-ZCN-~

CgOQ REACTOR COOLANT OIL LIFT PUMP M-RCN-P02A REACTOR CAVITY NORM CLG FAN M-HCN-A03A REACTOR CAVITY NORM CLG FAN M"HCN-A03C CEDM NORM ACU-A HEXCH OUTLET VLV J"NCN-HV-485 CTMT NORM ACU"C CHILLED WTR INLET VLV J-WCN-HV-59 CTMT NORM ACU-A CHILLED WTR INLET VLV J-WCN-HV-57 CEDM NORM ACU-B HEXCH OUTLET VLV J"NCN-HV-486 CTMT NORM ACU-B CHILL WATER INLET VLV J-WCN-HV-58 CTMT NORM ACU-D CHILL WATER INLET VLV J-WCN"HV-60 REACTOR CAVITY NORM CLG FAN M-HCN"A03B REACTOR CAVITY NORM CLG FAN M-HCN-A030 CEDM ACU C INTAKE DAMPER M-HCN-M03C CEDM ACU D INTAKE DAMPER M-HCN-M030 PALO VERDE " UNIT 2 3/4 8"23

~,

0

TABLE 3.8-2 (Continued)

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIYE DEYICES PRIMARY DEVICE NUMBER E-NHN-H2805 E-NHN-H2806 E-NHN-H2827 E-NHN-H2828 E-NHN-H2809 E-NHN-M2811 E-NHN-M2818 E-NHN-M2817 E"NHN-M2819 E"NHN-M2820 E"NHN"H2821 BACKUP DEVICE NUMBER E-NHN-M2827A E-NHN-M2827B E-NHN-H2827A E"NHN-H2827A E"NHN-M2827C E-NHN-M2832A E-NHN-M2832A E"NHN-H2832B E-NHN-M2832B E-NHN-M28320 E-NHN-M2828C SERVICE DESCRIPTION SGl COLD LEG BLOWDOWN ISO VLV J"SGE-HY-41 SG HOT LEG BLOWDOWN ISOLATION VALVE J"SGE-HY-43 REACTOR COOL PUMP OIL LIFT PUMP lB H"RCN-P02BP REACTOR COOLANT PUMP OIL LIFT PUMP 2B M-RCN-P02DP CONTAINMENT E(UIP HATCH J-ZCN-E02 30A RECEPTACLES FOR CTMT BLDG JIB CRANE g-%CA-C)0"fA)Q 30A RECEPTACLES FOR SEAL CRANE ASSY MOT CTMT BLDG MONORAIL HOIST 1 TON M-ZCN-G03 30A RECEPTACLES FOR CTMT BLDG JIB CRANE~~ Q-EC.Q- (0+ A]Q CTMT BLDG ELEY ¹2 CONTROLLER J"ZCN-E01 MULTIPLE STUD TENSIONER M"ZCN-M15 E"NHN-M2822 E"NHN-M2801A E"NHN"M2833 E"NHN-M2833A E-NHN-M2828B E"NHN-M2827B E"NHN-M2827B E-NHN-M2827B WELDING RECPTS E-NHN"I09 B, C, D

FUEL TRANSFER SYS CONTROL CONSOLE E-PK-002 REFUELING MACHINE E-PC J02 CEA CHANGE PLATFORM E-PC-JQl

~ ll PALO VERDE - UNIT 2 3/4 8-24

~

i 0

TABLE 3.8-2'(Continued)"

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE NUMBER E"PGB"L34D2 E-PGB-L34D3 E-PGB-L36D3 E-PHA-M3318 E-PHA-M3316 BACKUP DEVICE NUMBER E-NGN-B34D2 (FUSE)

E-NGN-B34D3 (FUSE)

E-NGN-B3603 (FUSE)

E-PHA-M3334 E-PHA-M3316A SERVICE DESCRIPTION CEDM NORMAL ACU FAN M-HCN-A01D CEDM NORMAL ACU FAN M-HCN"A02D CTMT NOR ACU FAN M-HCN-A01B SAFETY INJECT TANK 4 ISOL VLV J-SIA"UV"644 SAFETY INJECT TANK 3 ISOL VLV J"SIA-UV"634 E-PHB-M3404

.RAA-L LF E-PHA-M3517 E"PHA-M3503 E"PHB-M3405B 8: PKA-'bzA3o E"PHA"M3521 E-PHA-M350 IA E"PHA-M3508 E"PHA-M3511A E-PHA-M3512 E"PHA"M3513A E"PHB"M3619

%All.

E-PHB-M3641A 6-PKS- 02ZIQ E-PHB-M3622 E"PHB"M3629 E-PHB-M3604 i'.

c E-PHB-M3604A NCMS RET INT CTMT ISOL VLV J-NCB-UV-403 CTMT PRG PMR ACCESS MODE ISO YLY J-CPA-UY-48',

CTMT PRG RFL MODE ISO VLV J-CPA-UY-2B SHUT ON CLG ISOL LOOP 1 VLY J"SIA-UY-651 CTMT/RAD SUMP CTMT INT ISO VLV J-RDA"UV-23 CTMT SUMP ISOL TRAIN A VLV

J-SIA-UV-673 CTMT PRG REFULING MODE ISO VLV J-CPB"UY-3A SHUT DN CLG ISOL LOOP 2 VLV J-SIB-UV-652 SAFETY INJECTION TANK ISOL VLY J-SIB"UY-614 CTMT PRG PMR ACCESS MODE ISO YLY J-CPB-UY-5A PALO VERDE " UNIT 2 3/4 8"26

0 Ib

/

TABLE 3.8-2 (Continued)

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVIC'E NUMBER BACKUP DEVICE NUMBER SERVICE DESCRIPTION E-PHB-M3613 E"PHB"M3613A E-PHB-M3618 E-PHB-M3641 CTMT SUMP ISOL TRAIN B VLV J-S IB-UV"675 SAFETY INJECTION TANK 2 ISO

'VLV J-SIB-UV-624 E"PHA-M3704 E-PHA-M3715 E"PHB-M3816 E-P HB-M3811 E-PKD-B44 E-P KC"B43 E-NNN-D1113 E-NNN-D1213 E-NNN-D1526 E-NNN-D1525 E-NNN-01626 E"NNN-D1625

,E"QAN"D05B E-PHA-M3703A E-PHA-M3719 E-PHB-M3836 E"PHB-M3813A E-PKD-M4411 E-PKC"M4311 E-NNN-D11 E"NNN-012 f-NNN-D15 f-NNN"D15 E"NNN-016 E-NNN-D16 E"QAN-B02 MASTE GAS HEADER CONTAINMENT ISOLATION VALVE BRA'~

Q-@RA,- Ave Hp CONT TRAIN A UPSTM SUP ISO VLV J-HPA"UV"1 Hp CTMT TRAIN B UPSTM SUP ISO YLY'"HPB-UY"2 NORM CHIL WTR RETURN CTMT ISO

- Vl V J"MCB"UV-61 SHUTDOW CLG ISOL VLV J-SID-UV-654 SHUTDOW COOLING ISOL VLV J-SIC-UV"653 MOVABLE INCORE DRIVE SYS ¹I 800VA, M"RIN-M03A VIA E-R IN-J01A MOYABLE INCORE DRIYE SYS ¹II 800VA, M-RIN-M03B VIA E-RIN-J01A RCP INSTM LOCAL PNL J-RCN-E02 RCP.INSTM LOCAL PNL

.J-RCN-E01 RCP INSTM LOCAL PNL J-RCN-E04 RCP INSTM LOCAL PNL J"RCN-E03 LIGHTING PANEL E-QAN-005B CTMT BLDG EL 100'ALO VERDE " UNIT 2 3/4 8-27

il~

il 0

PRIMARY DEVICE NUMBER E-QAN-D05C TABLE 3.8-2 '(Continued}

CONTAINMENT PENETRATION CONDUCTOR I

= LIGHTING PANEL E"QAN-005C CTMT BLDG EL 100'"QAN-B03 OVERCURRENT PROTECTIVE DEVICES BACKUP DEVICE SERVICE NUMBER DESCRIPT ON E-QAN-D05F E-QAN-B05 E"QAN-D05E E-QBN-BOl E-QAN-B06 E-QBN-D91 E-QAN"D05D E-QAN-B04 LIGHTING PANEL E-QAN-D05D CTMT BLDG EL 140'IGHTING PANEL E"QAN-D05F CTMT BLDG EL 140'IGHTING PANEL E"QAN-D05E CTMT BLDG EL 140'IGHTING PANEL E"QBN-D73A CTMT BLDG EL 100'"

QBN-B02 E-NHN-D1514 2

E-RCN-D010$

E-NHN-D2614 E-RCN-D01%

t E-RCN"D030g E-RCN-0030k l

E-RCN-D0202 E"RCN"D020Y

". E-RCN-0040 E-RCN-D040 E-QBN-091 E-NHN-M1526 E"NGN-L11C2 E-NHN-M2618 E-NGN-L11C2 E-NGN-L11C3 E-NGN-L11C3 E-NGN-L12C2 E"NGN"'L12C2 E-NGN-L12C3 E"NGN-L12C3 LIGHTING PANEL E-QBN"D?3B CTMT BLDG EL 140'O OPERATION CAMERA JB¹ 2

PZR BU HTR M"RCE"B07,

B13, A01 TO OPERATION CAMERA JB¹ 1 PZR BU HTR M"RCE-B03, A09, A15 PZR BU HTR M"RCE-B04, All, A16 PZR BU HTR M-RCE-A02, AO?,

A13 PZR BU HTR M-RCE-B06,

B12, A18 PZR BU HTR M"RCE-B16, A04, A08 PZR BU HTR M-RCE-B15, A03, Alo PZR BU HTR M"RCE-A17,

A06, A12 PALO VERDE UNIT 2 3/4 8-28

0 0

TABLE 3.8-2 (Continued)

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY,DEVICE NUMBER E-NAN-SOlM E-NAN-S01L E"NAN-502L X

E-NAN-SO M

E"NGN-L03C2 E-NGN"L03C3 E-NGN-L03D2 E-NGN-L06C2 E-NGN-L09C4 E-NGN-L10C2 E-NGN-LlOC3 f~ ggg e p( jQQQ I

QFu.X

- RH- ~stoa 7-U 'bZ.

BACKUP DEVICE NUMBER E-NAN-S01A E-NAN"S03B E-NAN-S01A E-NAN"S03B E-NAN-S02A E-NAN-S04B f"NAN-S02A E-NAN-S04B FUSE IN BKR.

FUSE. IN BKR.

FUSE IN BKR.

E-NGN-BOGC2 (FUSE)

E-NGN-B09C4 (FUSE)

FUSE IN BKR.

F-Q&,Q-QLZ.C.Q SERVICE

'DESCRIPTION RCP M-RCE-P01A (C.E.

NO. 1A)

RCP M"RCE-Pole (C.E.

NO.

2A)

'RCP M"RCE-P01B (C.E.

NO. 1B)

RCP M"RCE"P01D (C.E.

NO. 2B)

CTMT NOR DUCT HTR M-HCN"Eolc CTMT NOR DUCT HTR M-HCN-E01Q CTMT POLAR CRANE M-ZCN-GOl CTMT PRE-ACCESS NORM AFU FAN M-HCN-F01A CTMT PRE-ACCESS NORM AFU FAN M-HCN-F01B

'CTMT NORM DUCT HTR M-HCN"E01A CTMT NORM DUCT HTR M-HCN" E01B PROPORTIONAL HTR BANK M-RCE"B2, B8 B14 PROPORTIONAL HTR BANK M-RCE-B5, Bll, B17 CEA 06 CB101 CEA 08 CB102 CEA 10 CB103

F101, F102, F103 CEA 06

F104, F105,, F106 CEA 08

F107, F108, F109 CEA 10 PALO VERDE - 'UNIT 2 3/4 8-29

II 0

~O

TABLE 3. 8-2 '(Continued)"

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE NUMBER BACKUP DEVICE NUMBER SERVICE DESCRIPTION CEA 51 CB103 CEA 53 CB104

F107, F108, F109 CEA 51 F110', Fill, F112 CEA 53 CEA 30 CB101 CEA 31 CB102 CEA 32 CB103 CEA 33 CB104 CEA 01 CB101 E-PHA-D33-03

~ E-PHA-D33-04 E-PHA-M3332 E-PHA-M3332 INDICATING LIGHTS FOR VLV J"SIA"UV"634 INDICATING LIGHTS FOR VLV J"SIA-UV"644

F101, F102, F103 CEA 30

F104, F105, F106 CEA 31

F107, F108, F109 CEA 32 F110, Fill, F112 CEA 33

F101, F102, F103 CEA 01 E-P HB-D36-01 E"PHB-D36-02 E"NHN"D28-04 E"NHN-D28-14 E"NHN"028"16 E"NHN"D28"18 E"NHN-D13-04 E"PHA-M3638 E-PHA"M3638 E-NHN-M2830 E-NHN-M2830 E-NHN-M2830 E-NHN-M2830 E"NHN"M1329 INDICATING LIGHTS FOR VLV '-SIB"UV"614 INDICATING LIGHTS FOR VLV J-SIB-UV-624 CONTAINMENT PREACCESS NORMAL AFU MOTOR SPACE HEATER FOR M"MCN-F01AH

'LOW SWITCH J"HCN"FSL-29 FOR DUCT HEATERS M"HCN-E01A AND B A<A CONTAINMENT AH5'UCT HEATERS M-HCN-EOlA AND B TEMPERATURE CONTROL J-HCN-TC-29

'LOW SWITCH J"HCN-FSL"31 FOR DUCT HEATERS M-HCN-Eolc AND 0 CONTAINMENT ACU DUCT HEATERS M-HCN-Eolc AND 0 TEMPERATURE CONTROLLER J-HCN"TC-31 PALO VERDE - UNIT 2 3/4 8"34

il~

li

. TABLE 3'.8-2 (ContinLre@

CONTAINMENT PENETRATION KNPiJK'ffiaff OVERCURRENT PROTECTIVE I%K~

PRIMARY DEVICE NUMBER E-NHN-D13-22 BACKUP DEVICE NUMBER E-NHN-.M1329 SERVICIE DESCRIPTWN STEAM GEiEMh(IGRf N&il'ctQUP RBtttfP MOTE SPMK fHiWiEiRMI.88~KUIH E-NHN-D15-01 "-.

E-NHN-M1526 REACTOR UQKNlfl BUMP.'%ÃSE MRCE HEAKiR FiBKMH&fMI RGKw7JXLB E-NHN-D15-02 E-NHN-D15-06

'E-NHN-D10-01 E-NHN-D10-02 E-NHN-D10-20 E-NHN-D19-05 E-NHN-D19-06 E-NHN-D19-07 E-NHN-D19"08

.)

a E-NHN-D19-10

~4

'e, C

E-NHN-019"12 E-NHN-M1526 E-NHN-M1526 E-NHN-M1027 E-NHN"M1027 E-NHN-M1027 E"NHN-M1914 E-NHN-M1914 E-NHN-M1914 E-NHN-M1914 E-NHN-M1914 E"NHN-M1914

'REACTOR HSluTii'UMP'%ME5FAK HEATERf CM6%5RRf'rRQK-;BflTiiiBQ CONTAINMBffll'ZKGGKGK'HGHIIINLN88 FAN~f SBNCIE &K%%QKA~~'R M-Hcifti~'P'@XSAM

~%

REACTOR. CBV~Q'UMIP M03i'QRf,SNKZ

'HEATEU Gi&Rr@HRHf Ql.RfLi-:HQZLNB REACTOR Cmui. N1li W)PIP tNJTDff %MR HEATER ~FQkQQR hl 963-:H%EDI STEAM GENBQgfM< %fEIl LiAV(8P HUNR'OTOR 5M'RMRH<'~ifhKll!B3 CEDM NORMAl. AQS IiAh'Itel"82i KM%

HEATER BI.IHltff.Nial CEDM NORMAL NUN KMI;h$7i,RRf MME HEATER Qi.Pc(UfHNK'rH CONTAINMENT 0ERNLi. NiBj iRNI.MSIKfR SPACE llFNtlWtiff Ni&N2LNI CONTAIN'IENT NSfHM'Q. 4EQJ llama iViSliXE SPACE. HHKER ti~ftfff-.4%IlZHl REACTOR.CAVITYMIRMLXZEQ3M,FkM:

MOTOR SPRITZ HE2%KRf M"HCN-AQ3NM REACTOR CAVGV( HfafftlM CMIQNEI IF'OTOR SPME I!EAWERf M-HCN"AEKHI PALO VEROE - UNIT 2 3/4 8-35

Il

TABLE 3.8-2 (Continued),

CONTAINMENT PENETRATION CONDUC'HE OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE NUMBER E-ZAB-C06 (FUSE)

E-ZAB-C06 (FusE)

E"ZAB"C06 (FUSE)

E-ZAB"C06 (FusE)

E-ZAB-C06 (FusE)

E-ZJA"C01 (FUSE)

E-ZJA-C03 (FUSE)

E-ZJA"C03 (FusE)

E-ZJA-C03 (FUSE)

E-ZJB-C01 (FusE)

E-ZJB-C01 (FUSE)

BACKUP DEVICE NUMBER E-PKB-D2221 E-PKB-D2221 E-PKB-D2221 E-PKB-D2221 f-PKB-D2221 E-PKA-D2101 E-PKA-D2101 E-PKA-D2111 E-PKA-D2111 E-PKA"D2111 E"PKB"D2201 E"PKB"02201

~

E-PKB-D2201 E-P KB-02201 SERVICE DESCRIPTION SAFETY INJ TAN( lbhK'!RGB'EI SURD.'7<

VAlVE J-SIB-~622 Hv SAFETY INJ TANKVLF Wl!%E J-SIB-HV-613 SAFETY INJ TANK'/GNWVN!VK J"SIB"HV"623 SAFETY INJ TANKVHH'i3'NlVE:

J"SIB"HV-633 SAFETY INJ TANK VGi9% VMS J-SIB-HV-643 SAFETY INJ TANK KGlRQZHHI NRPLV( ViÃVE J-SIA"HV-639 SAFETY INJ TANK MKGlRQEM SMBPlLV( VIVE J-SIA-HV-649 RCP CONTROLLED BllHDSBF 70 Rlott VihD'tE J-CHA-HV-507 LETDOWN LINE TG RGBKS'BE% EXCH!"L'.iM'SO VALVE J" CHA"HV"516 RCP CONTROL'LED B'QiEBGEiF %l VKH %fA'LVE J"CHA"UV"506 SAFETY INJ TANK F311lL NM EMEN MLLE J-SIB"UV-641 SI TANK CHECK VXflMKL!EK~ 299 VALVE J-SIB-UV-648 HOT LEG INJECT XHEKKVALI!IliMfNBEISO VLV J-SIB"UV-322 SAFETY INJ TANK NIHMGBH SERPENS VALVE J-SIB-Pf-632 Hv'ALO VERDE " UNIT 2 3/4 8-37

41

TABLE 3.8-2 (Continued)

CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEYICES PRIMARY'EVICE NUMBER E-ZJB-COl (FUSE) lj '-ZJB-C03 (FUSE)

E-ZJB-C03 (FUSE)

E-ZAA-C03 (FusE)

E-ZAA-C03 (FUSE) gV E-ZAA-C03

~@USE)

E-ZAA-C01 (FusE)

E"ZAA"C01 (FUSE)

E-ZAA-C01 (FUSE)

~~+

E-ZAA-C04 Pn

~(FUSE)

E"ZAA-C05

~~

(FusE)

~f'-ZAA"C05 (FUSE)

E-ZAA"C05 (FUSE)

E-ZAA-C05 (FUSE)

E-ZAA-C06

'FUSE)

BACKUP DEVICE

'NUMBER E"PKB-D2201 E"PKB-D2211 E-PKB-02211

, E"PKA-D2109 E-PKA-02109 E-PKA-D2109

, E-PKA-D2110 E-PKA-02110 E-PKA-02110 E"PKA"D2102 E-PKA-02114 E-PKA"D2114 E"PKA-D2114 E-PKA-02114 E-PKA-02121 SERVICE DESCRIPTION

'AFETY INJ TANK NITROGEN SUPPLY VALVE J-SIP-'8-"42 H4'ETDOWN LINE TO REGEN HEAT EXCH VALYE J" CHB"UV-515 SAFETY INJ TANK FILL AND DRAIN VALVE J"SIB-UY-631 REACTOR DRAIN TANK OUTLET ISOLATION VALVE J-CH UV"560 SI TANK RWT HDR CTMT ISOLATION VALYE J"SIA"UV-682 REGENERATIYE HEAT EXCH TO AUX SPRAY VALVE J-CHA-HV-M 2oS SAMPLE CONTAINMENT ISOLATION VALVE J"SSA-UV-203 SAMPLE CONTAINMENT ISOLATION VALVE J-SSA-UY-204 SAMPLE CONTAINMENT ISOLATION YALVE J-SSA"UV"205 PRESSURIZER VENT VALVE J" RCA-HY"103 STEAM GEN BLO'WDOWN CTMT ISOLATION VALVE J"SGA-UV"500P BLOWDOWN SAMPLE CTMT ISOLATION VALVE J-SGA-UV"204 BLOWDOWN SAMPLE CTMT ISOLATION VALVE J-SGA-UV-211 BLOWDOWN SAMPLE CTMT ISOLATION VALVE J-SGA-UV-220 SAFETY INJ TANK NITROGEN SUPPLY VALVE J-SIA-HY-619 PALO VERDE UNIT 2 3/4 8"38

Il il

!I

w~~r g m

~r, zp-e-~a.

E-z,AA-cd g~us<

~-PKA.1oz>o>

gE.ACToA CooL,Axrt 9 E,~T a-RcR-Hg-l~(

Ipse,vw

~o pg z/+

s->a 6- 'RAP '-co%

( Fu.SGQ K-P~ ~><>G

~~ TR> QhAE.W'T PLDRQG pe~ ER p~e.ss

MoDE, iso>.Av <~

vA~vc-.

z-c.PR -Q V-9A

0

!I 0

TABLE 3.8-2 (Continued)

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE NUMBER E-ZAA-C06 (FUSE)

E-ZAA-C06 (FUSE)

E"ZAA-C06 (FUSE)

E-ZAA-C06 (FUSE).

E-ZAA"C06 (FUSE)

E"ZAA"C06 (FUSE)

E-ZAB-C03 (FUSE)

E"ZAB-C03 (FusE)

E-ZAB-C03 (FUSE)

E-ZAB-C03 (FusE)

E-ZAB"C01 (FusE)

E"ZAB-C01 (FusE)

E-ZAB-C04 (FUSE)

E"ZAB-C04 (FUSE)

E-ZAB-C04 (FUSE) p '4AQ C<h PALO VERDE - UNIT 2 BACKUP DEVICE NUMBER E"PKA-D2121 E-PKA-02121 E-. PKA-D2121 E" P KA-02121 E-PKA-D2121 E" P KA-D2121 E"PKB"D2209 E-PKB"02209 f-PKB-02209 E"PKB"D2209 E-P KB-D2210 E-PKB-D2210 E-PKB"D2202 E-PKB-D2202 E-PKB-D2202 R-pKS-ORE>>.

SERVICE DESCRIPTION SAFETY INJ TANK NITROGEN SUPPLY VALVE J" SIA-HV-629 SAFETY INJ TANK VENT VAL'VE J-SIA-HV-605 SAFETY INJ TANK 'VENT VALVE J"SIA-HV-606 SAFETY INJ TANK VENT VALVE J" S IA-HV-607 SAFETY INJ TANK VENT VALVE J"SIA-HV-608 RC 'SYSTEM VENT TO CTMT VALVE J-RCA-HV"106 REGEN HEAT EXCH TO AUX SPRAY VALVE J-CHB-HV-203 REACTOR COOLANT VENT VAL'VE J-RCB"HV-102 SAFETY INJ: TANK FILL AND DRAIN VAlVE J-S IB-UV-611 SI TANK CHECK VALVE LEAKAGE LINE ISO VALVE J-S I8-UV-618 CTMT ATM RADIATION MONITORING ISO VALVE J-HCB-UV-44 CTMT ATM RADIATION MONITORING ISO VALVE J-HCB-UV-47 REACTOR COOLANT VENT VALVE J-RCB-HV-108 SAFETY INJ TANK FILL AND DRAIN VALVE J-SIB-UV-621 SI TANK CHECK VALVE LEAKAGE LINE ISO VALVE J-SIB-UV-628 Qbk)TA114%4l4T Qci4ha f4 94hCC 4

+04 ~~>ivy, VAav~ g CPS 3/4'-39

0 I

0

TABLE 3.8-2 '('Continued)

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES PRIMARY DEVICE NUMBER E-ZAB-C05 (FUSE)

BACKUP DEVICE NUMBER E-PKB-D2214 SERVICE DESCRIPTION REACTOR COOLANT VENT VALVE J" RCB-HV"109 E-ZAB-C05 (FUSE)

E-ZAB-C05 (FUSE)

E-ZAB-C06 (FUSE)

E-ZJB-C03 (FUSE)'"ZJB"C03 (FUSE)

E-ZAN-COl (FUSE)

E-PKB"02214 E-PKB"D2214 E-PKB-02214 E-PKB-D2221 E-PKB-D2221 E-PKB-02211 E"PKB"D2211 E-NKN-D4226 E-NKN-D4224 E-ZAB-C05 E-PKB"D2214 (FUSE)

STEAM GEN BLOWDOWN CTMT ISOLATION VALVE J-SGB-UV-500R BLOWOOWN SAMPLE CTMT ISOLATION VALVE J"SGB-UV"222 BLOWDOWN SAMPLE CTMT ISOLATION VALVE J"SGB-UV-224 BLOWDOWN SAMPLE CTMT ISOLATION VALVE J-SGB-UV-226 REACTOR COOLANT VENT VALVE J-RCB" HV"105 SAFETY INJ TANK NITROGEN SUPPI Y VALVE J-SIB-UV-612 SI TANK CHECK VLV LEAKAGE LINE ISO VALVE J-SIB"UV-638 HOT LEG INJECT CHECK VLV.LEAKAGE ISO VLV J-SIB-UV-332 SEAL INJECT VALVES TO RCP J-CHE" FV-241 SEAL INJECT VALVES TO RCP J-CHE-FV-242 E-ZAN"C01 (FUSE)

E-ZAN-COl (FUSE)

E-ZAN-C01 (FUSE)

E" ZAN-C01'FUSE)

E"NKN-D4222 E"NKN-D4224 E"NKN-D4224 E-NKN-04224 SEAL INJECT VALVES TO RCP J-CHE-FV-244 POST ACDT SMPLG SYS ISO VALVE J-CHN-HV-923 REACTOR VESSEL SEAL DRAIN TO RDT VALVE J-RCE-HV-403 SI DRAIN TO REACTOR DRAIN TANK VALVE J-SI E-HV-661 PALO VERDE - UNIT 2 3/4 8-40

II

TABLE 3.8-3 MOTOR"OPERATED VALVES THERMAL OVERLSQS PROTECTION AND/OR BYPASS DEVICES YALYE NUMBER J-SIA-UV-647

'-SIA-UY-637 J-SIA-HV-604 J-SIB-HV-609 J-SIA-HV-657 J-SI 8-HV-658 J-SIA-HV-685 J"SIB"HV-694 J-SIA-HV-686 J"SIB-HV-696 J"SIA"HV-688 J-SIB"HV"693 J-SIA-UV-617 BYPASS Ui:VICE Accident Conditions HPSI A Flow Control to Reactor Coolant Yalve HPSI A Flow Control to Reactor Coolant Valve HPSI Pump A Long Term Cooling Valve HPSI Pump B Long Term Cooling Valve Shutdown Clg.

Temp.

Control Train A Valve Shutdown Clg.

Temp.

Control Train B Valve LPSI - Ctmt Spray Pump Cross Connect A Valve LPSI-Ctmt Spray Pump Cross Connect B Valve Ctmt Spray A Cross Connect Valve Ctmt Spray B Cross Connect Valve

.Shutdown Clg. Heat Exchange A Bypass Valve Shutdown Clg. Heat Exchange B Bypass Yalve HPSI A Flow Control To React Coolant 2A Yalve sfslim(,$3 MFKGt28 Sx&@p 3hgert~en StQIHG&nl Dg. 5+5.

Rc&'bp K~WiJc)n

%u5dbwm EH@

5ys.

5afiaCp Rgactann RukMdh'nl K3g 5+s.

SRCL~/ ZAQBUflion

%u55lnvm 6",ilg. Sys.

SMMivg EiqjjaMiea WuWtuvm C:ilg. Sys.

Ra@My Kvg~mt$eni Nu68b%01 Ktlat, S+s SRCh&gt VnjjeW$exa Sdu5dbmn> Cifg., $>ys 9MhNp IInjj~>en

%L'tiltbvNl C,ltd., Syz 9897aM+ ~~g~g<QQ

%Mnltavm Z1ig Sys.

SM~ Kzgertaon

%uMwm (C~Ig. +ys.

Kagact~un XtaC~Cm<a <i;lghays.

~Wg Ztqjacttien

&uCcthurn King hays.

Ka~y Zagecta on 9Bv@a5nvm Cltg Sys.

PALO VERDE - UNIT 2 3/4 8-43

0 is

TABLE 3.S-3 $Ga~ixue~

MOTOR-OPERATED VALVES TFKRAM'. SSRRBD@9 PROTECTION AND/OE( EVPkSS ZEGEi YALVE NUMBER J-SI A"UV-627 J-SIA-UV-645 J-SIA-UV-635 J-SIA-UV-644 J-SIA-UV-634 J" SIB-UV.-616 J"SIB-UV"626 J;SIB-UV"'36 J"SIB"UV"646 J-SIA"UV"655 J-SIB-UV"656 J-SIA-UV"664

~ 0 BYPASS DEVICE Accident Condiikweae, HPSI A Flow Cori&all Te React Coolant '2B Vivre LPSI F,low Contrail Te React Coolant O'R ~3Italiva LPSI Flow Conteeti ifh React Cool ant 'l% '>Jallvm Safety Injecthm 1~k 3$

Isolation, Valve Safety Injectiera Thnk 3k Isolation Valve HPSI B Flow CoxOmli Te React Cool ant 2k '4~allcm HPSI B Flow CorCm~ll ite React, Coolant 29 0'alum HPSI, B F3ow Cmtrell Ye React Coolant 3k '3htzl(ve'.

HPSI B Flow Cmfuuli <te React Coolant 3$ %hfl'm Shutdown.Clg. M~

Isolation Loop 2 @alive~

Shutdown Clg. ZXW Isolation Loop 2 'EMwa Ctmt Spray Pump 4 itIo Refueling Mater Tank Isolation Vlv.

s)7GwBK53 AKFECTi,ED 5zi5edp Eqgecti on

'ShI.@thorn Clg.,Sys.

~i'~ Zmgacti on S5uiMavm Clg.

Sys.

'SiaeTa4y ejecta on SNv@eimvm C3~g.

Sys.

SaiTxtipj ejection SMuNehwn Zlg.'ys.

SzNWy i~sgecti on SMu5zhen. Llg.

Sys.

"'AM@ Zrgecti on Slud'ibsen> ZOg, Sys.

GRAM+ ZKQecti on

$)Mc5uve Clig. Sys..

SMxlgi Zejecti on SWtMuve 'C39.. Sys.

9hcTe~~ Znjecti on SlbM~a iCOg.

Sys.

Sa>SM~y Zxgecti.on Shura

~Clg.

Sys.

Mf~p Zegection Shu~wil Clg. Sys.

~ Rejection SbuMnwn Cl g.

Sys.

1 n

PALO VERDE - UNIT 2

4I 0

TABLE 3.8-3 (Continued)

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES VALVE NUMBER J-SIB-UY"665 J-SIB-UY-615 J"SIB"UV"625 J-SIA-UV-666 J-SIB-UV-667 J"SIA-UV-669 J-SIB-UY-668 J-SIA-UY-672 J-SIB-UY"671 J-SIA-UY-674 J-SIB"UY-676 J"SIA"UY"651 J-SIB"UY"652 BYPASS DEVICE Accident Conditions)

Ctmt Spray Pump B

To Refueling Water Tank Isolation Vlv.

LPSI Flow Control To React Coolant 2A Valve LPSI B Flow Control To React Coolant 2B Valve HPSI.Pump A to Refueling Mater Tank Isolation HPSI Pump B to Refueling Mater Tank IsoIation LPSI Pump A To Refueling Mater Tank Isolation LPSI Pump B, to Refueling Mater Tank Isolation Ctmt Spray Control Train A Yalve Ctmt Spray Control Train B

Yalve Ctmt Sump Isolation

'.; Train A Valve bl.'Ctmt Sump Isolation Train B Yalve Sh'utdown Cl g. Isol ati on Loop 1 Yalve Shutdown Clg. Isolation Loop 2 Yalve SYSTEM(S)

AFFECTED

'afety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg.

Sys.

Safety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg.

Sys.

Safety Ingectson Shutdown Cl g.

Sys.

Safety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg.

Sys.

PALO VERDE - UNIT 2 3/4 8-45

0 0

TABLE 3. 8-3,(Conti nued)

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES VALVE NUMBER J-SIA-UV-673 J-SIB"UV-675 J-SIB-UV-614 J"SIB-UV-624 J-S IA-HV"684 J-SIB-HV-689 J-SIA-HV-683 J"SIB-HV"692 J"SIA-HV-691 J"SIB-HV"'690 J"SIA-HV"698 J"SIB-HV"699 J-SIA-HV"306 BYPASS DEVICE Accident Conditions Ctmt Sump Isolation Train A Valve Ctmt Sump Isolation Train B Valve Safety Injection Tank 2A Isolation Valve Safety Injection Tank 2B Isolation Valve Shutdown Clg. Heat Exchange Isolation Train A Shutdown Clg. Heat Exchange Isolation Train 'B LPSI Pump A Isolation Val ve LPSI Pump B Iso'lation Valve Shutdown Clg.

Loop 2 Warm-Up Bypass Valve Shutdown Clg.

Loop 1 Warm-Up Bypass Valve HPSI Pump A Discharge Valve HPSI Pump B Discharge Valve LPSI Pump A Header Discharge Valve SYSTEM(S)

AFFECTED Safety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg. Sys.

-Safety Injection Shutdown Clg.. Sys.

Safety Injection-Shutdown Clg. Sys.

Safety Injection Shutdown Clg. Sys.

Safety Injection

.Shutdown Clg.

Sys.

Safety Injection Shutdown Clg.

Sys.

Safety Injection Shutdown Clg. Sys.

Safety Ingectson Shutdown Clg. Sys.

Safety Injection Shutdown Clg. Sys.

PALO VERDE " UNIT 2 3/4 8"46

0 il

TABLE 3.8-3 (Continued)

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES VALVE NUYiBER J-SIB-HV-307 J-SIA-HV-687 J-SIB-HV-695 J-SIA-HV-678 J-SIB-HV-679 J-SIC-UV-653 J-SID"UV-654 J-EMA-UV-65 J-EMA-UV-145 J-CTA-HV-1 J-CTA-HV-4 J-SGA-UV-134 J-SGA-UV"138 BYPASS DEVICE Accident Conditions)

LPSI Pump B Header Discharge Valve Ctmt Spray Isolation Train A Valve Ctmt Spray Isolation Train B

Valve Shutdown Clg. Heat Exchange Isolation Train A Shutdown Clg. Heat Exchange Isolation Train B

Shutdown Clg. Isolation Valve Shutdown Clg. Isolation Valve ECM Loop A To/Fi om NCM Cross Tie Valve ECM Loop A To/From NCM Cross Tie Valve Condensate Tank to Aux.

Feedwater Pump Valve Condensate Tank to Aux.

Feedwater Pump Valve SG-1 Aux. Feedwater Pump A

Steam Supply SG-2 Aux. Feedwater Pump A

Steam Supply SYSTEM(S)

AFFECTED Safety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg. Sys.

Safety Injection Shutdown Clg.'Sys.

Safety Injection Shutdown Clg. Sys.

Safety Inject'ion

'hutdown Clg. Sys.

Essential Cooling Mater System Essential Cooling Mater System Condensate Transfer 8 Storage Sys.

Condensate Transfer 6 Storage Sys.

Main Steam System Main Steam System PALO VERDE - UNIT 2 3/4 8"47

II 0

TABLE 3.8-3 (Continued)

MOTOR"OPERATEQ VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES VALVE NUMBER J"NCB-UV-401 J-NCA-UV-402 J-NCB-UV-403 i J-AFB-HV-30 J"AFB-HV-31 J-AFB-UY-34 J-AFB-UV-35 J"AFA-HY"32 J-AFA-UV-37 J"AFC-UV-36 J-AFC-HV"33 J-CPA-UV-2A J-CPB-UV-3B J-CPA"UV-2B BYPASS DEVICE Accident Conditions NCMS Ctmt Isolation Valve NCMS Ctmt Isolation Valve NCMS,Ctmt Isolation Yalve Aux. Feedwater Regulating Valve Aux. Feedwater Regulating Valve Aux. Feedwater Regulating Yalve Aux. Feedwater Regulating Valve Aux. Feedwater Regulating Valve Aux. Feedwater Isolation Valve Aux. Feedwater Isolation Yal ve Aux. Feedwater Regulating Valve Ctmt Purge Refueling Mode Isolation Valve Ctmt Purge Refueling Mode Isolation Valve Ctmt Purge Refueling Node Isolation Valve SYSYEH(S)

AFFECTED Nuclear Cooling Mater System Nuclear Cooling Mater System Nuclear Cooling Mater System Auxiliary Feed-water System '

Auxi1iary Feed-water System "Auxiliary Feed-water System Auxiliary Feed-water System Auxiliary Feed-water System Auxiliary Feed-water System Auxiliary Feed; water System Auxiliary Feed-water System Containment Purge System Containment Purge System Containment Purge System PALO YERDE - UNIT 2 3/4 8-48

4$

~

il 0

TABLE 3.8-3 $C~zatm8)

MOTOR-OPERATED VALVE~iOKLSWiBHIIDMl PROTECTION AND/OR 3FPMS EEKKKS VALVE NUMBER J"CPB"UV"3A J-MCA-UV-62 J"MCB"UV-63

'J-MCB-UV-61 J-ROA-UV-23 J-HPA-UV-3 J"HPA"UV-5 J"HPB"UV-4 J-HPB-UV-6 J-HPB-UV-2 J-HPA-UV-1 J"GRA-UV-1 BYPASS DEVI'CE Accident Cendif%cea Ctmt.Purge RefceTIfng ItIhM Isolation Valve Normal Chill M~Nm Rhtfzen.

Ctmt Isolation Normal Chill 'M~>>,

%pg>TQ~

Ctmt Isolatien Normal Chal Wa5ar FNlmw Ctmt Isolation Ctmt Radwas&

Rmgxs K>CmnaBI Isolation H2 Ctmt Train A RnvaWmsrm Supply Isolation H2 Ctmt Train A R'~me Isolation Valve H2 Ctmt Traaa 3 Hhe~eeam>

,Supply Isolation H2 Ctmt Train B Rhyme Isolation Valve H2 Ctmt Train B U~tmem Supply Isolation H2 Ctmt Train A SIM~naam Supply Isolation Radioactive Draira Zk: Gas Surge Hdr Internal ZunM5mmC Isolation Sifts"iKMQS]}

NFRHKTiiiB (Uanthmznnexft, Purge SpMKHA Gati ITIT!+6 '~Rater Spr@znn CthÃnlt+5 ')Mes Spf$5'ellA GNii'iITIa4%L~~r Sy~

Rhdlii~$vre Maste 9%89llll 5~10 Smdztiimmm<~'ydrogen CaMareil Sygs Gbn5zriizmmdt Pr4rogen FezrWe)TI Syr, GhnNzNrnmanII: Rgdrogen Gmvbr+TI S~.,

GhllCK181~, 39@drogen E'eaCnuN 5gps Emdmmment Bydrogen Eam&eil Sgs.

EB'JCMXIDBllj,hydrogen EmkamTI Sys.

(kheamm Radwaste

~Q'tRfm PALO VERDE - UNIT 2 3/4 8-49

0 Ib 0

3/4. 9 REFUELING OPERATIONS 3/4. 9. 1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1

'Mi h.+he reactor vessel head closure boits less than fully tensioned or with the head

removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is. met:

a.

Either a K ff of 0.95 or less, or eff b.

A boron concentration of greater than or equal to 2150 ppm.

APPLICABILITY:

MODE 6+.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity chagges and initiate and continue boration at greater than or equal to Z4o~gpm of a solution containing

> 4000 ppm boron or its equivalent until K ~ is reduced to less than or equal to 0.95 or the boron concentration is r5ftored to'greater than or equal to 2150 ppm, whichever is the more restrictive.

SURVEILLANCE RE UIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined, prior to:

a ~

b.

Removing or unbolting the reactor vessel

head, and Withdrawal of any full-length CEA in excess of. 3 feet from its,fu!:y inserted position within the reactor pressure vessel.

4.9. 1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be'determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure. bolts less than fully tensione or with the head removed..

PALO VERDE - UNIT 2 3/4 9-1

ji il 0

3/4.10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for mea urement of CEA worth and shutdown ma g n

!3 Qvided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s), or'he reactor is subcritical by at least the reactivity equivalent of the highest CEA worth.

APPLICABILITY:

MODES 2, 3" and 4"¹.

ACTION:

a.

With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-

,,...ately initiate and continue boration at greater than or equal to

~;S&~gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by.

Specification 3.1.1.1 is restored.

b.

With all full-length CEAs fully inserted and the reactor subcritical by less than he above reactivity equivalent, immediately initiate and continue boration at greater than or equal t&f&gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.l.l.l is restored.

SURVEILLANCE RE UIREMENTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdr awn shall be determined at least once per 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s.

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn. position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the. SHUTDOWN MARGIN to less than the limits of Specification 3.1.l.l.

4.10.1.3 When in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA worth is. avail-.

able for trip insertion from OPERABLE CEAs at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by con-sideration of at least the following factors:

a.

Reactor Coolant System boron concentration, b.

CEA position, c.

Reactor Coolant System average temperature, d.

Fuel burnup based on gross thermal energy generation, e.

Xenon concentration, and f.

Samarium concentration.

Operation in MODE 3 and MODE 4 shall be limited to 6 consecutive hours.

Limited to low power PHYSICS TESTING at 'the 320'F plateau.

PALO VERDE - UNIT 2 3/4 10-1'

, ~

Ib 0

m C) m

+1.0 K

I-z uJ (0

U u

llJ0 0 u u)

U)

K

.D cO I-z 0

I

-1.0 Q

40.5 Cl 4 0.22 40.22 x 1 hp/

ALLOWA L MTC FIGURE 3.1 ~ 1 ALLOWABLEMTC MODES 1 AND 2 PALO VERDE UNIT/CYCLE 1 I

I l':

~ jI I

Is I

~ I

~ ~

):

~ I ~,

(595 'F I

I I

II

, 0.0hp /OF I

)

~

~ ~

~ '

~ ~

~ I LUI-0I-K O0

-2.0

~3.0

)I

~4.0 TG TH AVG 2

I ~

I ~'i

) i I

'.t;

,'I:,I I. i

~ <<

~

li:.

(596 F;3.5 x 10'46p/

F j l

~ l!'~ '

~'ll 48o'oo'500 AVERAGE MODERATOR TEMPERATURE, F

coo'

II i/

0

136'.6" (40K) 135'-6" (30K) 135'-10"'(33 5K) ~

(

"134'-6" (20K) 133'-6" (10K) 0

..:133'-3" (7.25K).-

COLD S/D VOLUME 0

200 400 600 AVERAGE REACTOR COOLANTSYSTEM TEMP F

80)io 600,000 GAL. (565 F) 600 RWT LEVEL'NSTRUMENT READING (1) 75/o 70/o 65%

573 744 G 4L (1200 F)

COLD S/D VOL. PLUS MARGIN 575K 55nK MINIMIJniIUSEFUL VOLUME (1)

IEQUIRED IN THE RWT 5nnK 475K 01'2)

ESF VOL. PLUS MARGIN (3) 200 400 AVERAGE RCS TEMPERATURE, F

OK 609 (1) THE TANK LEVEL AND VOLUMC SHQSVN ARE THE USEFUL LEVEL AND VOLUME ABOVE THAT IN THE TANK"YHICH IS REQUIRED FOR VORTEX CQNSIDERATIONS (2) DURING MODE 5 AND 6 ONE OF THESE BORATED SOURCES SHALL CONTAIN A MINIMUMOF 33,NO GALLONS (3) THIS VOLUME'ISNOT REQUIRED DURING MQPE 6 F IGUR E 3.1.2 MINIMUMBQRATED lVATER VOLUMES PALO VERGE - UNITQ 3/4 1"12

O~

!5

FIGUR E 3.1-2A PART LENGTH CEA INSERTION LIMITvs THERMALPOWER 1.00 0.90 112.5" 0.80 0.70 0.60 0

0.50 0.40 Z

0.30 u

0.20 ACCEPTABLE OPERATION INSERTION LIMIT UNACCEPTABLE OP E RATION 50% POWER LINE 0.10 0.00 22.5" 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0

PART LENGTH CEA POSITION, INCHES WITHDRAWN

~i ll~

C7m C) f 4P lA Vl MZ I

lA m(

M Ill C/l m

X7 C)

I CA ln I

4J 1.00 0.90 0.80 0.70 R

0.60 O

0.50 0.40

0. 30 Q.ZO 0:10 M A~

M VI I tn W~

Qg

-M al) 0 C

41 Ag W f g J Cllg

$ J

~M MO en% A f90

~4 0)

+~ fR.

MW TRANSIENT NSE ION LIi<IT QidO

'5U i50 30 f~O

!0 0

)50

!~C

~0 60 gg 0

/BE QXV+~UPf. = Qgggg

~

il 0

FIGURE 3.2-1 DNBR MARGINOPERATING LIMITBASEDOIQlmi.SR (COLSS IN.SERVICE) 100 K

0

~ " 'I-U ~

Z

}

I- 0 LQ m C CL0 g.

CC 0I-

<.o Lfl LU 0

O Ch Z

'0 0 oZ0 C5 80 40 REGION OF ACCEPTABLE OPERATION R EGIN!(DH:

UNA"II:ZPHAGC~E OP ERNKHISNJ 0

0 20 40 60 8m PERCENT OF, RATED THERMALMilSER

~

F,IGURE 3. 2-1 PNBR, MARGIN OPERATING 'LIMIT BASEP:ON UMSK (COL'SS IN SERVICE)

.PALO'ERGE - 'UNIT&

3/4 2-6

ik~

il

FIGURE 3.2-2 DNBR MARGINOPERATING LIMITBASED ON CORE PROTECTION CALCULATOR (COLSS OUT OF SERVICE) 0.60

~ ~ ~ ~ ~

~ ~

~ ~ ~

I t

~

i

~ ~

~

v

~

~ i

REGION OF

~ I 0.55

'I ~

ACCEPTABLE OPERATION

~

~ ~

~

I

~ ~

~ ~ ~

l

~

- ~

-.05, 0.51)

. 'l.......'(.25, 0.51) 0.50 QK Cl g

045

'D z

0.40 I

~

I

~

~ ~

.....I...

a I

~ ~

I

-.30, 0.

""I'

-+

'(

3S):- >'-::.:

~

~ '-

I I

j

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I

~

a

~.

)...~

i:.REGION OF I

OPERATION;:::

-I I

~

~ I

~

I

(.30, 0.46) 0.35

~ ~ ~ ~ ~ ~ ~

~

0.30 -0.3

-0.2

-0.1 0.0 0,1 0.2 0.3 CORE AVERAGE ASI SEE SECTION 3.2.7 FOR THE ASI OPERATING LIMITS fIGURE 3.2-2 PNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS PALO VERDE - UNIT 5'COLSS OUT Of SERVICE) 3/4 2-7

i i

0

FIGURE 3.2-3 REACTOR COOLANT COLD LEG TEMPERATURE vs CORE POWER LEVEL 580 575

u. 570 O

565 cx 560 g 555 Q

O 550 8

570 568 AREA OF ACCEPTABLE OP E RATION 552 568 562 l0 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL,%OF RATEDTHERMALPOWER FIGURE 3. 2-3

~ ~

REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POMER LEVEL PALO VERDE UNIT 2r 3/4 2-10

ib

'FIG UR E 3.3-1 DNBR MARGIN'OPERATING LIMITBASED ON COLSS FOR BOTH CEAC'S INOPERABLE 140 C<

~

~ ~ ~ ~

~

~ ~ ~

~ ~

~

I i

I ~ ~

~

7'

~

~ \\ ~ ~

~

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g 120 lX zaz 100 Q Cu CD CC i-m cL'L~

60 LCJ ~

Bz 0 gg

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~ ~

~

I': ~

s

~

I i ~ ~ ~ ~ e I

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t

~

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~ j-REGION OF ACCEPTABLE:

i'".'::'. OPERATION

I

~

~ (100, 118. 7) 95 112.7 I

I ~

~

4

~ 9 g ~

~ ~ ~ ~ ~

~ ~ ~

e ~ ~

~ >

79.4, 79.4)."

i

~

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I REGION OF UNACCEPTABLE-OP E RATION

.:.(,

) '.: ~::":.:-.':-.

20 0

20

~

40 60 80 100 PERCENT OF RATED THERMALPOWER PALO VERGE - UNITE 3/4 3-10

II 0

0

E o 250 s

s

~

e s

1

~

I

(

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s s

s I

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30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE E UIVALENT I-131.PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POMER MITH THE PRIMARY COOLANT SPECIFIC ACTIVITY > 1.0 Ci/GRAM DOSE E UIVALENT I-131 PALO VERQE - UNITiree'/4 4-28

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8 REJECT Q. G CONT.INNE TESTI N6 @. ~ 0 10 20 '0 40 50'$ V8 $8 90 I00 FIGURE 4.7-1 SAt1PLING PLAN FOR SNUBBER FUNCTliBHRLIlk~i PALO VERDE - UNIT$ 3/4 7-26

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( m Kl C7m 200 Transition Temperature Shift 'F 150 I C) 100 0 hb o~ Q 0 0 CIO 101 10 10 NEUTRON FLUENCE 0 A5338 CL 1 PLATE 0 WELD METAL FIGURE B 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E > 1 MeV) NEUTRON FLUENCE (550 F IRRADIATION)

'LVINTERSBURG ROAD ~'t Pyi 'r i"r Qqt HET TOWER ~. ~ 'i ~ ~ I ~ ILP 2r. ir V ~ J UNIT 1 UNIT 2 UNIT3 ~ 4 ~E,r:. ~', ELLIOT ROAD (V/ARD ROAD) 0 NQA TH LEGEND r//rr.. CENTERLINE'OF CONTAINMENT PROPERTY PURCHASED EXCLUSION BOUNDARY SITE BOUNDARY PROPFRTY PURCHASED OUTSIDE EXCLUSION AREA SCALE t'ai)ifgi) SI TE 'At<D EXCLUSIGH SOU)'CEDAR I Eg I"IGURE 5.1-1 PALO VERDE U"IIT 5-2'

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II ll'l 0

CEO EXECUTIVE V.P. OIR. PROJECT SERVICES HGR. PROJECT. CONTROLS HGR. AOHIN. SERVICES I MGR. EHPLOYEE RELATIONS PVNGS PLANT MANAGER HGR. OPERATIONS V.P. NUCLEAR PRODUCTION ASST. V.P. NUCLEAR PROOUCTION l TRANSITION/ f HGR. NUCLEAR SAFETY ISEG/NSG OIR. TECHNICAL SERVICES HGR. NUCLEAR ENGINEERING l I

PIR, CORPORATE PA ASST.

HGR CORPORATE PA ONSITE HGR. PUAI.ITY SYSTEHS/ ENGINEERING HGR. PROCUREHENT PUALITY HGR. CONTRACTS C PURCHASING MGR. PARTICIPANT SERVICES HGR. MAINTENANCE MGR. OUTAGE MANAGEMENT HGR. NUCLEAR CONSTRUCTION HGR. RECOROS HGR. PUALITY AUOITS/ MONITORING ONSITE HGR. PLANT SERVICES HGR. NUCLEAR FUELS HGR. PUALITY CONTROL HGR. EHERGENCY PLANNING ONSITE FIGURE 6.2-1 OFFS I TE ORGANIZATION HGR. LICENSING

1i il' Cl

TABLE 3.'3 5 (C~~'ltfNÃgQ ENGINEERED SAFETY FEATURES RESPMBE 7KNES INITIATING SIGNAL.AND FUNCTION !Pemmax ~<<,Z Cm SZCONDS 8. Steam Generator Level - High a. Main Steam Isolation 1. MSIS actuated MSIV's 2. . MSIS actuated MFIV's¹ R.S"-/i%i..6"~ M.s //~5JP 9. Steam Generator hP-High-Coincident 'Qith: Mani Kemrrathw Eavelt Kaw a. Auxiliary Feedwater Isolation 35i //Ilsr from the Ruptured Steam Generrtev 10. Control Room Essential Filtration h~a5zorrr 3JMP'~//L89F~'~ 11. 4.16 kV Emergency Bus Undervo)Cage (Degraded Voltage) Loss of Power 90K system voltage 12. 4.16 kV Emergency Bus Undervoltage gloss mt 9/xPjthgp)) Loss of Power TABLE NOTATIONS Diesel generator starting and, sequence loaÃzg @claps inrrcil~

Response

time limit includes movement of valves.and ~imrtmC ~ff guns car Mevter discharge pressure. "~Diesel generator starting delays not inctu5&l. W7~'i'Lw guar ~va~la'b'.l~.

Response

time l.imit includes movement of vailzmr, ~nd adÃm5lrtma& eti pump or. blower discharge pressure. ¹MFIV valves tested at simulated operating cmrmM59mm" wa.lees tt~~ at static flow conditions to 8.6/8.6 seconds. -4+VHu-Qcsponhp. xi~~ Qwb~W<M.,MOA~s~ ~~~~M~ ~z 5Qg-Q<- So ~ %Rip 0& gAOlA l<N gy ~+ ~flCWM~Q 2LTL X<A< )~~~~~s ~ ~~~gugyAC'&5 ~~i+~+ ~ +~A'n+~, ~->~ ~ -,~gg gn,-'~~~~g A PALO VERDE - UNIT 2 3/4 3-.29

il 0

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 ws a minimum, the fire detection instrumentation for each FPER detection zone shown in Table 3.3-11 shall be OPERABLE. APPLICABILITY: Mhenever equipment protected by the fire detection instrument is required to be OPERABLE. ACTION: a. With any, but not more than one-half the total in any fire zone Function X.fire detection instrument shown in Table 3.3-11 inoperable, restore the inoperable instrument(s) to OPERABLE status within 14 days or within the next 1 hour establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours or monitor the containment air temperature at least once per hour at 6 aP the locations listed in Specification 4.6. 1..5. b. C. With more than one-half of the Function X fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Function Y fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour establish a fire watch patrol. to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5. 8oP= The provisie6s of Specifications 3.0.3 and 3.0.4 are not applicable. 'SURVEILLANCE RE UIREMENTS 4.3.3.7. 1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAl TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOMN exceeding 24 hours unless performed in the previous 6 months. 4.3.3.7.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. PALO VERDE - UNIT 2 3/4 3-6O

0 Cl

TABLE 3. 3-13 (Continued) TABLE NOTATION At all times. "" During GASEOUS RADWASTE SYSTEM operation. 0 During waste gas release. N 'n MO ES 1, 2, 3, and 4 or when irradia""d fuel is in the fuel storage pool. ACTION 35-With the number of channels O."EP/'.BLE less than required by the Minimum Channels OPERABLE requirement, the contents of the - tank(s) may be released to the environment provided that prior to initiating the release: a 0 At least two independent samples of the tank's contents are analyzed, and ACTION 36-ACTION,37-b. At least two technically qualified members of. the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (A) or (B) are performed: ACTION 38 " ACTION 39-a. Initiate the Preplanned Alternate Sampling Program of Specification 6.16 to monitor the appropriate parameter(s). b. Place moveable air monitors in-line or take grab samples at 'least once per 12 hours. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the GASEOUS RADWASTE SYSTEM may continue provided grab samples are taken and analyzed daily. With both channels inoperable operation may continue provided grab samples are taken and analyzed (1) every 4 hours during degassing operations, and

(2) daily during other operations.

PALO YERDE - UNIT 2 3/4 3-74

0 ik 0

G S. wlCast HOWVOVWE OATE SUBJECT SWEET No. CHECKED BY DATE JOB NO. Action 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the following action of (A) or (B) are performed: a. Place movable air monitor in-line b. Take grab samples at the mode specific frequencies indicate below. Monitor 6 RU-141 N/A RU-143 M RU-145' Mode 5 4 3 2 1 iV/A D D S S M D D S S M M M M M Vent shall be sampled daily while moving irradiated fuel.

II ~O

TABLE 4.6-1 TENOON 'SURVEILLANCE -,FIRST YEAR Tendon No. Visual Inspection Monitor Forces Oetension Tendon Remove Mire Test Mire V43 X V62 X (,A') V75~ ~ X H13-007< X H13-021 X H21"037 X H21-044 X H32"016 X Q) H32-030' + Ha +'o 4 ga Qb + go ,+Ho + go + g~ No 'No,~ No A( ~ No No No NoP'3o No No pP'~ < Po No No No No No No .~ ADo )do No ,No No No Notes: 2. 3. 4. "X" means the tendon shown shall be inspected for the stated requirements during this surveillance. "A" means the tendon shown shall be inspected for the 'stated requirements during 'the next or second surveil.lance. "No" 'means that inspection is not required for tha't tendon. """ means control tendon. PALO VEROE - UNIT 2 3/4 6-12

, ~, 0

CONTAINMENT SYSTEMS 3/4.6. 2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM h LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with earth spray system capable of taking suction from the RMT on a containment spray actuation signal and automatically transferring suction to the containment sump on a recirculation actuation signal. Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger. APPLICABILITY: MODES 1, 2, 3, and 4." ACTION Mith one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the inoperable spray system to OPERABLE status within the next 48 hours or be in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE RE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE: a 0 b. C. d. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is positioned to take suction from the RMT on a containment spray actuation (CSAS) test signal. By verifying that each pump develops an indicated differential pressure of greater than or equal to 27 psid at greater than or equal the minimum allowable recirculation flowrate when tested pursuant to Specification 4.0.5. At least once per 31 days by verifying that the system pipirg is full.of water to the 60 inch level in the containment spray header (>115 foot level).. At least once per 18 months, during shutdown, by: l. Verifying'that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) and recirculation actuation (RAS} test signal. 2. Verifying that upon a recirculation actuation test signal, .the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established. "Only when shutdown, cooling 'is not in operation. PALO VERDE UNIT 2 3/4 6-15

'I II 0

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-4 shalll he. QHERNBLE APPLICABILITY: Whenever equipment in the areas protected hyg tUim fives hose stations is required to be OPERABLE, except that fire hose s~ixna ligated in containment sha3-1 .have their containment isolation valves claret firn SIDES 3., 2, 3, 4, and 5'CTION: ao With one or more of the fire hose stations shown %nt liakTk 3.7W inoperable, provide a gated wye on the nearest OPSTtML~Z: ihjse sation. One outlet of the wye shall. be connected to the stfarrdhndf Tfxegfh ef hose provided for the OPERABLE hose station. The sanazdl mC'ice of the wye shall be connected to a length of hose suIi5TKcti~ M ymvide coverage for the area left unprotected by the incqamaDille. Hest s+tion. The above action shall be accomplished within one Nmn'ift'%a >aoper-able fire hose is the primary means of fire supprsasnlarn;; eCtmwise provide the additional hose in 24 hours. The hose for the unprotected area shall be stored.ak N8.OMBRE hose station. Signs identifying the purpose. and 1ama@iiom eT Cibe fire hose and related valves shall be mounted above the Heaei andi at, the inoperable hose station. b. The provisions of Specifications 3.0.3 and 3.Q.4 hei no%; agyliiic Me. SURVEILLANCE RE UIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7W) sfiaiH!ba demonstrated OPERABLE: a 0 At least once per 31 days by visual inspection of ti.'ie ~axns accessible during plant operation to assure all re@mnm5 eqntlIpment is at the station. b. At least once per 18 months by: 2. 3. Visual inspection of the stations 'not accessiblle dluriirng ip3ant operations to assure all required equipment is altt Chs ~Coon. l,'I Removing the hose for inspection and rerackinL, ag4 Inspecting all gaskets and replacing any degrMhdl aparkeM in the couplings. ~ t "If 1s to be performed in containment during MODE 5 %m !hre hose stations located in containment shall have their contains@ ho'+worq PALO VERDE UNIT 2 3/4 7"37

I il il I I il

TABLE 3.7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HERE JFKMK LOCATION 150'lant North of Fuel Bldg. 100'lant Mest of Rad !he+a Rldg.- 150'lant Northwest of, F!!ol Bldg. .HRBAWi'MISBER "No hose

house, however, the hose station is used to service ~undam~M transfer pump PALO VERDE - UNIT 2 3/4 7-41

0 il

PIECE NO. 128-101 128-101 128-101 128-101 131-102 131-102 <774-o I F-71)- o L F'-77<- o > F-7~v-o4 '7Q 7-ol P-]4 1-o E CODE NO. H-6703=1 H-6703-2 H-6703-3 H-6703-4 M-4307-1 ~ M-4307-2 MATERIAL SA 508-CLED SA 508-CLg9 SA 508-CL2'3 SA 508-CLED SA 508-CL2'I SA 508-CLZl VESSEL LOCATION In'let Nozzle Inlet Nozzle Inlet Nozzle Inlet Nozzle Outlet Nozzle Safe Outlet Nozzle Safe DROP WEIGHT RESULTS ~Of } -20 30 M Qo W -9o A End ~-3a End W-30 TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS ~(FORGINGS RTNDT(b) ~('F g-gO +K.go C~ QQ e-qo 4R lQ +8-]o TEHPERATURE OF CHARPY V-NOTCH~ ta 30 I 50 ft-lb ft-lb +20 +60 -25 +10 -27 +18 +5 +42 +30 +68 +30 +68 MINIMUM UPPER SHELF C ENERGY FOR LONGITUDINAL DIRECTION-ft lb N.A. N.A. N.A. N.A. N.A. N.A. 128"301 12&-301 131-101 131-101 131-101 131-101 126-101 106-101 ~~i. WL%~ SA 508-CL2 SA 508-CL2 SA 508-CLl SA 508-CLl SA 508-CLl SA 50&-CLl SA 508-CL2 SA 598-CL2 Outlet Nozzle Outlet Noizle Inlet Nozzle Safe End Inlet Nozzle Safe End Inlet Nozzle Safe End Inlet Nozzle Safe End Vessel Flange Closure Head Flange H-4 -1 !1-4304-2 H-6712-1 H-6712-2 H-6712-3 H-6712-4 M-6705-1 M-6706-1 -10 "10 -10~O Z 90 80 So ~mB~~t~sio~~ 08-4 Wet-}}ozr1e-Extenso~~ 35}((* 3 5*}}'10 +10 +7 +7 -78 "80 10}}(* 10}}(}}( +45 +45 +50 +5U "28 "54 N.A. N.A. N.A. N.A. N.A. N.A. N.A. N.A. N.A. = Not Applicable (no minimum upper shelf requirement). Lower bound curve valves. = Average of three test results. (a) = Determined per applicable ASME-BPV-Co'de Sect. III, Subsection NB, Article NB-2331-(a-1,2,3). (b) = 0 and 180 specimens had the same values. g le-ol F. le-O'K F-IL t -0'l

g. tl+eZ F-'4 lo-o'5 F'-'l4s.o t

<- ave,- L F-1 4L-+'L

~i Ik il 0

TABLE B 3/4.4<<1 (Continued). REACTOR VESSEL TOUGHNESS (PLATES) PIECE NO. CODE NO. MATERIAL VESSEL LOCATION DROP TEMPERATURE OF MINIMUM UPPER MEIGHT RT (a) CHARPY V-NOTCH" SHELF C ENERGY RESULTS NDT. 8 30 8 50 . FOR LONGITUDINAL ~ ~F ~(rF ft - 1b ft - 1b DIRECTION-ft 1b 142-102 142-102 142-102 124-102 124-102 124-102 122-102 122-102 122"102 102<<102PC 102<<1029 . 150-102 150-102 "4311-H 4311 H-1 -3 H-6 l-l H-6 1-2 H- -3 H-70 -4 .H 701 5 H 6701-H 6709-H 6709-2 H-6715-1 H-6715-2 SA 533-GRB-CL1 SA 533-GRB-CL1 SA 533-GRB<<CLl SA 533-GRB-CL1 SA 533-GRB-CL1 SA 533-GRB"CL1 SA 533-GRB-CLl SA 533-GRB-CL1 SA 533-GRB-CL1 . SA 533-GRB"CLl SA 533-GRB"CL1 SA 533-GRB-CL1 SA 533-GRB-CLl Lower Shell Plate Lower Shell Plate Lower Shell Plate Intermed. Shell Plate Intermed. Shell Plate Intermed. Shell Plate Upper Shell Plate Upper Shell Plate Upper Shell Plate Closure Head Dome Closure Head Dome Bottom Head Dome Bottom Head Dome ~- (o <<gf <<g'g -8f-4o Bo -Sf'-zo "30 "30 fp -30 W-4o -K-su 25-9p -AtLgp ~ lo 0 A-Qo +W -Ko &JQ +AS lO +$8 cR ~ le +~ o W-Qp $0 "6 +40 "24 "8 "7 +14 +44 +90 +56 +98 +39 +89 +82 +120 +49 +98 +42 +96 +36 +66 +4 +37 +2 +30 +26 +50 JoS 127 %4& /gf ea ))q 9& (g) N.A. N.A. N.A. N.A. N.A. N.A. N.A. (a) = Determined per applicable ASHE-BPV-Code Sect. III, Subsection NB, Article NB-2331-(a-1,2,3). N.A. = Not Applicable (no minimum upper shelf requirement). = Lower bound curve values of transverse specimens. C-Y73-ol F'q1> oZ, f I f$-05 F'- l4b=o~( p-14$ -ob f llp'f.oLr r-z~f'ol 5=)AD 8'-oX P lM.o3 5= 770-o I F-1aoeZ f-Tl)-O1 4= 71<-o2

0

43 TABLE 3.3=3 (Continued) ENGINEERED SAFETY FEATURES ACTUATIOH SYSTEM INSTRUMENTATION ESFA SYSTEM FUNCTIONAL UNIT TOTAL HO.'. OF CHANNELS MINIMUfi CHANNELS CHANNELS APPLICABLE TO TRIP OPERABLE MODES ACTION YI. AUXILIARY FEEDWATER (SG-l)(AFAS-1) B. ESFA System Logic 1. Matrix Logic 2. Initiation Logic 3. Manual AFAS C. Automatic Actuation Logic VII. AUXILIARY FEEDWATER (SG-2)(AFAS-2) A. Sensor/Trip Units 1. Steam Generator 82 Level-Low 2. Steam Generator b, Pressure - SGl > SG2 B. ESFA System Logic 1. Matrix Logic 2. Initiation Logic (Continued) 6 4(c) 4(c) 4(c) 2(d) 2(d} 1 2(d) 1 2 3 1, 2, 3, 4 1, 2, 3, 4 '1,2,3,4 1 2 3 1 2 3 1,2,3 1, 2, 3, 4 17 15 r-.. ~ 16 C 13+ 14J( Dl3 g s 13", 14" ~i a 17 12 3. Manual AFAS C. Automatic Actuation Logic VIII. LOSS OF POWER (LOV) A.

4. 16 kV Emergency Bus Under-voltage (Loss of Voltage)

B.

4. 16 kY Emergency Bus Under-voltage (Degraded Voltage) 4(c) 4/Bus 4/Bus Q'X.

CONTROL ROOM ESSENTIAL 'FILTRATION 2 ~ 2(d) 1 2/Bus 2/Bus P 1 3/Bus 3/Bus 1, 2, 3, 4 1, 2, 3, 4 1 2 3 1'2 3 All Modeh'5 16 13K'4K 13*, 14* 1QA

CD)~1'TROD '::-9 8"f US:~P. TABLE 3. 3-3 (Continued) (d) ACTI TABLE NOTATIONS (a) In MODES 3-6, the value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer pressure and this value is maintained at less than or e ual to.400 si* th p e setpoint, shall be increased automatically as pressurizer or equa pressure is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia. (b) In MODES 3-6, the value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached. (c) Four channels

provided, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice).

The proper two-out-of-four combination. The provisions of Specification 3.0.4 are not applicable. After the initial criticality of Unit 2 or Unit 3~ ACTION STATEMENTS ON 12 - .With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE . status within 48 hours or be in at least HOT STANDBY within,the next 6 hours and in COLD SHUTDOWN within the following 30 hours. ACTION 13 - Mith the number of charm'els OPERABLE one less than the Total Number of Channels, STARTUP andlor POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour. If the inoperable channel is

bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification

6. 5. 1. 6. h.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN. With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below. Process Measurement Circuit l. Steam Generator Pressure-Low Steam Generator Pressure - Low Steam Generator Level 1-Low (ESF) Steam Generator Level 2-Low (ESF) 2. Steam Generator Level (Wide Range) Steam Generator Level - Low (RPS) 'Steam Generator Level 1-Low (ESF} Steam Generator Level 2-Low (ESF) PALO VERDE - 'UNIT 1 3/4 3-23

il 0

INSTRUMENTATION '.~.M'J~l J aE'Q:. Q 3 '2 ~J ~J J'ASES. REMOTE SHUTDOWN SYSTEM (Continued) The parameters selected to be monitored ensure that (lg 15m czrM5tien of the reactor is known, (2) conditions in the RCS are known, (3) dhole Meam generators are available for residual heat removal, (4) a source of watjea iir awa$ 1jable for makeup to the

RCS, and (5) the charging system is available the maMup mat,er to the RCS.

The OPERABILITY of the remote shutdown system insures %he; a imam will not preclude achieving safe shutdown. The remote shutdown sp~em %esXv~menta-tion, control and power circuits and disconnect switches neraszmg M e3iminate effects of the fire and allow operation of instrumentation, ean<~lj and power circuits required to achieve and maintain a safe shutdown mmimitixrn ave independent of areas where a fire could damage systems noma>ljljy/ esa8 ~ shutdown the reactor. This capability is consistent with General Der>firqp> KmMman 3 and Appendix R to 10 CFR 50. The alternate disconnect methods or power or control ciinzuIjj5s mneme that sufficient capability is available to permit shutdown and oaCnOanavme ef cold shutdown of the facility by relying on additional operator aetNenrs ~M caecal control stations rather than at the RSP. 3/4. 3. 3. 6 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrune~4l~Mijam ensures that sufficient information is available on selected plant yenama~taa M monitor and assess these variables following an accident. This cap-tbiiljijdpj f>s consistent with the recommendations of Regulatory Guide 1.97, "Instrunandath'ice f'm K.ight-Mater-Cooled, Nuclear Plants to Assess Plant Conditions During andliFn'~l;lawing an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Leanm@j"jjask farce Status Report and Short-Term Recommendati'ons;" P The containment high range area monitors (RU-148 & RU-lj48)) anil <he main steamline radiation monitors (RU-139 A&B and RU-140 A&B) av. ijrn 'T&1in 3.3-6. The high range effluent monitors and samplers (RU-142, RU-if% zmQ RD-3.46) are in Tab~le 3 g-13. The containment hydrogen monitors are in !gxecii&llea-tionC3//4.6.5.1.'he Post Accident Sampling System (RCS coolly ws im Table

3. 3-6.~

The Subcooled Margin Monitor (SMM), the Heat Junction >1h~ernrgcnuple (HJTC), and the Core Exit Thermocouples (CET) comprise the Inadequate Gene Cooling (ICC) ia strumentation required by Item II.F.2 NUREG-0737, the post '7~,jjIit-2.Action plan. The function of the ICC instrumentation is to enhance the abjj'llij~ef 'the plant operator to diagnose the approach to existance of, and recook~ Imam ZCC. Additionally, they aid in tracking reactor coolant inventory. Mass instruments are included in the Technical Specifications at the request et lVCC Generic Letter 83-37. These are not required by the-accident analysijs rTn< M bring the plant to Cold Shutdown. PALO VERDE - UNIT 1' 3/4 3-4

4 iP 0

( m C7m 't.00 0.90 C) 6 m m IR I l 5 jJ I 0.80 0.70 0.60 ~z1 0.50 y,g m d)30 0 k5 I M Vl IQ f/) lR ~ IA .H C)H M 00 0 J ~a C ~7tPo A g~ fgesa 3 g I',I A GI ION 6BA Mxvl+RAt)AT = vgmfgg

J 4P l1

F IGUR E 3.1-2B CORE POWER LIMITAFTER CEA DEVIATION% zO ~ K ~ LLJ EEE 0 ~ 0 O~ .G l-O ~ O D I-ax UJ LZ: CC u QO ~O Z 30 20 10 0 I ~ ~ I ~ ~ ~ I ~ I t I g (60 MIN, 20%%d) 0 10 20 30 40 50 60 TIME AFTER DEVIATION,MINUTES "WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL. POWER PER THIS LIMITCURPE, FURTHER REDUCTION IS NOT REQUIRED FIGURE 3. 1-2B CORE POMER LIMIT AFTER CEA DEVIATION~ PALO VEROE UNITif 3/4 1-24

ll'

PANGS PLANT MANAGER OUTAGEHANAGEIIENT HAtlAGER TECHHIGAL SUPPORT HAtlAGER OPERATIONS HANAGER HAINTEHAHCE HANAGER PLANT SERVICES HANAGER HAHAGER OPS ENGIIlEERING HRF SUPERIHTEtlDEtlT SUPERVISOR, ttRF HAINTENANCE HANAGER TRAINING SUPERINTEtiDENT UNIT I SUPERINTENDENT ICC HAIHTENAllCE HAtlAGER OPERATIONS SECURITY HAtlAGER RAD. PROT. C CHEN. SUPERINTENDENT UNIT 2 SUPERINTENOEtlT HCC SUPERVISOR FIRE PROTECTIOH SUPERVISOR COHPLIANCE SUPERINTENDEHT UNIT 3 SUPERIHTENDENT ELEC. HAINTENANCE SUPERINTENDENT OPS COHPUTER SYSTEH SUPERVISOR OPERATIONS SUPPORT SUPERINTENDENT STATION SERVICES SUPERINTENOEHT HECHANICAL HAINTENANCE FIGURE 6.2-2 ONSITE UNIT ORGANIZATION

0 C

MAINSILAMSUIYUHTSTHUCIUNE ~ ~ ~ CONTAINMENTULUG AUXILIARYBLDG FUEL BUILDING E XHAUST POINT r TNIIAO T POINT ~ VACUUMPUMP EXHAUST ITUI(BINEBUILDING FUELBLDG>> Ia RADWASTE BUILDING a r I r S+ rr 9'.2'IESEL GEN 'UILDING CONTROL BUILDING LAUNDRY'ECONTAMINATION FACILITY(UNIT I ONLYI PL CONT PLAN'T NORTH ~ I ~ PL CONT'5 .0" 112' I2a'.0 - - '246'4" I I L Palu Vaadr Nuakaa Iiaucaaling Slaliw ExoausT poiNTs HEY pLaw TYI'ICAL POML'R BIDCK IJI I Ira (elevation of exhaust point above grade) Plant Vent 145'uel Building 116'acuum Pump 84'O-I"-86 I I

~7 i. XF C 0, 0}}

v t e Letter Sequence '
TAC:60706, (Open)
Initiation Request Acceptance... Administration Meeting Questions Answers Results Approval... Other: ML17299A490, ML17299B011, ML17299B110
MONTHYEAR1985-08-12 [Table View]

ML17299A468

Text

SUBJECT:

Subject:

Reference:

Dear Mr. Knighton:

RESPONSE

Response

Response

Response

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