Text

Amends 72 & 71 to Licenses DPR-80 & DPR-82,respectively, Revising TSs to Remove cycle-specific Info That Is No Longer Applicable
	ML20099F357
Person / Time
Site:	Diablo Canyon
Issue date:	08/06/1992
From:	Quay T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20099F360	List: ML20099F357; ML20099F363;
References
	NUDOCS 9208130012
	Download: ML20099F357 (70)
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lnl UNITED STATES- <

II (NUCLEAR REGULATORY COMMISSION N

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'D

. WASHINoTON, D.C. 20666 lb t

J PACIFIC' GAS-AND ELECTRIC C0& ANY' DOCKET N0. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO 1

-AMENDMFNT-TO FACILITY-OPERATING LICENSE Amendment No. 72 License.No. DPR-80

[1E The Nuclear Regulatory Commission (the Commission) has found that:

A.=

The-. applicationi for amendment-by Pacific Gas & Electric Company 1

(the licensee) dated February 4, 1992, complies with the_ standards-

_and requirements _of;the Atomic Energy Act of 1954, as amended (the-lAct),<and the Commission's regulations-set forth in--10 CFR Chapter I ;-. -

B.

The_ facility will operate in conformity with the-application, the--

< provisions;of the Act,'and the rules and regulations' of the-Commission; C.

Thereits reasonable assurance-(1) that the' activities authorized

.by;thislamendmentican be conducted 1without endangering-the health land safety of. the public, and_ (ii) that such activities will be conductedrin: compliance-with:the Commission'stregulations;.

D.

Thetissuance of this amendment will not be inimic'al to the common

~

i defense: and security or~ to the health and_ safety-of the public;.

Landf EE.

The issuance of this amendment:.is inzaccordance with 10 CFR Part 1

51Lof the Commission's regulations and all applicable requirements

?have been satisfied.

.2L

Accordingly, the license _is' amended by: changes to the Technical Specifications = as indicated in the attachment to this license amendment,

and paragraph 2.C;(2): of;Facili_ty:0perating: License No.!DPR-80 is hereby'

~ amended tot read { as follows:

~

9208130012 920806 7

PDR.ADOCK 05000275;

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, (2)

_ Technicel Soecifications

'The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 72, are _ hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical _ Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

-3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION M

k Theodor

. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

' Specifications Date of Issuance:

August 6, 1992 e

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4' ' '

UNITED STATES n

E

_i NUCLEAR REGULATORY COMMISSION WAsHlNGTON, D.C, 20GSs A..* /

PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT N0. 2

@ ENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 71 License No. DPR-82 1.

The Nuclear Regulatory Commission (the Commssion) has found that:

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated February 4, 1992, complies with the standard.

and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

.The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragrsph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended tc. reao as follows:

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Technical 'Soecifications The Technical Specifications contained-in Appendix A and the Environmental Protection Plan contained in Appendi.: B, as revised through Amendment No. 71, are hereby incorporated in the

-- l i cens e.

Pacific. Gas & Electric Company shall operate the.

facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where.othemise stated _ in

. specific license conditions.

3. -

This license amendment is effective as of-the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION rw Theodore 1. Quay, Director Project Directorate V Division _of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

'Attachmenti Changes to-the Technical Specifications JateofIssuance:

August 6, 1992

+

ATTACHMENT TO LICENSE' AMENDMENTS AMENDMENT N0. 72 - TO FACILITY OPERATING LICENSE NO. DPR-80 AND' AMENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical-Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by

'the captioned amendment number and contain marginal lines indicating the area of. change.- Overleaf pages are also included, as appropriate, REMOVE JNSERT ix ix xii xii

.2-2a

--- 4 2-4 2-5 2-5 2-7 2-7 2-8 2-8 2-9 2-9 B-2-7 8 2-7 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3

( '4 1 3/4 1-7 3 4 1-8 3/4 1-8

/

3/4 1-9 3/4 1-9

-3/4 1-12 3/4 1-12 3/4 1-13 3/4 1-13 3/4 1-20 3/4 1-20

-3/4 1-23 3/4 1-E4 3/4-2 3/4 2-2I 3/4 3-3 3/4 3-3 3/4'3-8 3/4 3-8 3/4 3-11 3/4 3-11' 3/4 3-23 3/4 3-23 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-30 3/4 3-30 3/4 3 3/4 3-31 3/4 3-31a 3/4 4-8 3/4 4-8 g

3/4 5-1 3/4 5-1 L

3/4 5-6 3/4 5-6 l

3/4 5-9 3/4 5-9 L

3/4 5-10 3/4 5-10 l

3/4 7-9a 3/4 7-9a 3/4 9 3/4 9-1

. _ ~._ -,. _ _ _ _

i

...p 2-REMOVE lhSERT 3/4 10-1 3/4 10-1

~B 3/4--l-2 B 3/4 1-2 B 3/4.5-2a B 3/4 5-2a l

..<m l'

-INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

_SECTION PAGE

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUM"LAT0RS..................................

3/4 5-1 3/4.5.2 -ECCS SUBSYSTEMS - T,yg GREATER THAN OR EQUAL TO 350"E..

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350'F..................

3/4 5-7 i

avo 3/4.5.4 DELETED l

3/4.5.5 REFUELING WATER STORAGE TANK........

3/4 5-11 3/4.6 CONTAINMENT. SYSTEMS 3/4.6.1 CONTAJNMENT Co.tainment Integrity........................

3/4 6-1 Containment Leakage..............

3/4 6-2 Containment Air Locks...................................

3/4 6-5 Internal Pressure.....................

3/4 6-7

-Air Temperature.......................................

3/4 6-8 Containment Structural Integrity.............

3/4 6-9 Containment Ventilation Sy3 tem.......................

3/4 6-10 3/4.6.2 DEP_RESSURIZATION AND COOLING SYSTEMS.

' Containment Spray System...............................

3/4 6-11 Spray Additive System...................................

3/4 6-12 Containment Cooling System..............................

3/4 6-13 3/4.6.3 CONTAINMENT ISOLATION VALVES................

3/4 6-15

TABLE 3.6-1 CONTAINMENT ISOLATION VALVES.........................

3/4 6 3/4.6.4:

COMBUSTIBLE GAS CONTROL-Hydrogen Analyzers / Monitors...........................

3/4 6-26 Electric Hydrogen Recombiners..............

3/4 6-27--

DIABLO CANYON - UNITS 1 & 2 ix Amendment Nos. 72 & 71 1

_ _ _ _ _ _ _ _ - _ _ = _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _

_ - _ _ _ _ _ _ _ ~

Reissued September i9, 1991

-a INDEX LIMITING CONDITIONS-FOR OPERATION AND SURVEILLANCE REQUIREMENTS-

'3/4.-7I ~ PLANT SYSTEMS m

'3/4.7.I' TURBIht CYCLE Safety Va1ves............................................

3/4 7-1 TABLE 3.7-It MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INDPERABLE STEAM LINE SAFETY VALVES.......3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PERLD0P....................

3/4 7-3 Auxiliary Feedwater System..........;........

3/4 7-4

Condensate Storage Tank.................................

3/4 7.....

Specific Activity.................................

3/4 7-7 TABLE 4.7-l'. SECONDARY COOLANT SYSTEM: SPECIFIC. ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.............................

3/4-7-8 Main Steam Line Isolation Va1ves........................

3/4 7-9 Stean, Generator 10% Atmospheric Dump Val ves.............

3/4 7-9a 3/4. 7. 2 -- STEAM: GENERATOR PRESSURE / TEMPERATURE' LIMITATION.........

3/4-7-10 l

.- 3/4. 7. 3 '-

VITAL COMPONENT COOLING WATER SYSTEM....................

3/4 7-11 3/4.7.'4/ LAUXILIARY SALTWATER SYSTEM..............................

3/4 7-12 l3/4.7.5 - CONTROL ROOM-VENTILATION SYSTEM.........................

3/4 7-13

-3 /4! 7. 61:

AUXILIARY BUILDING SAFEGUARDS AIR FILTRATION SYSTEM.....

3/4 7-16 3/4.7.7? SNUBBERS -

3/4 7-18

FIGURE 14L7-11 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST..........3/4 7-23 a

. TABLE:4.7-21 SNUBBER VISUAL INSPECTION INTERVAL....................

3/4 7-23*

3/4. 7. 8f ' SEALED SOURCE CONTAMINATION............................. 3/4-7,

3/4.7.9.

FIRE SUPPRESSION SYSTEMS Fire Suppression Water Systas.........................

3/4 7.

Spray and/or Spri nkl er. Systems..........................

3/4.7-28 C0 Systas..............................................

3/4L7-30 f

TABLE 3.7-3C0[ SYSTEM............................................

3/4 7-31

-.Malon System............................................

3/4 7-32 F i re Hose Sta ti ons.......................................

3/4 7-33 DIABLO CANYON - UNITS 1 &-2~

x Amendment Nos. 66 and 65 V

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. Reissued Septecer;19,: 1991; c

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INDEX 4

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LIMITING ~ CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENTS-SECTION[

PAGE-V M 3/4'.7 ' PLANT SYSTEMS:(continued) i LTABLEi3.7-!41 FIRE-.HOSESTATION$h.....!...........................

3/4 7-34 13/4.7.10: _-FIRE BARRIER PENETRATIONS...............................

3/4 7 o 13/4;7.11-LAREA TEMPERATURE MONITORING.............................

3/4 7-37

TABLE 3.7-5D AREA TEMPERATURE MONIT0 RING..........................

3/4 7-38

'3/4.7.12! < ULTIMATE HEAT SINK......................................

3/4 7-39 3/4.7.13? FLOOD PROTECTION........................................

3/417-40 3/4.8 ELECTRICAL' POWER SYSTEMS 3/4.8.1- ~ A.C.-SOURCES-

'Operatingh.............................................

3/4 8-l'

.-: TABLE 4. 8-1. DIESEL GENERATOR TEST SCHEDULE.......................

3/4-8-8 TABLE T4. 8-2a ?t0AD SEQUENCING TIMERS - ESF TINERS.................

3/4 S-9 Y

TA8LE;4.'8-2b; LDAD SEQUENCING TIMERS - AUTO TRANSFER TIMERS.......

3/4 8 ~

Shutdown................................................

'3/4 8-11:

3/4.8.2-ONSITE-POWER DISTRIBUTION'

>0perating...............................................

3/4 8 Shutdown.................................................

3/4-8 3/4;8.3LLD.CUSOURCES-Operating...............................................

3/4 8 15 S TAB LE : 4. 8 ' BATTERY ; 5URVEILLANCE REQUIREMENTS....................

3/4 8-17

Shutdown.................................................

3/4 8-18

3/4.8.4 1 ELECTRICAL EQUIPMENT PROTECTIVE: DEVICES Motor-Dperated Valves: Thermal Overload Protection.

s

.and Bypass' Devices......................................

3/4 8 TABLE 3.8-1 MDTOR-0PERATED VALVES THERMAL OVERLOAD PROTECTION LAND BYPASS-DEVICES.....................................

3/4 8-20 Containment: Penetration Conductor Overcurrent Protective Devices......................................

3/4 8 ?DIABLO: CANYON ~--UNITS 1 1 2 xi Amendment Nos. 66 and 6 rv-a y

m.

INDEX lLIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS

-3/4.9.1 BORON-CONCENTRATION....................................

3/4 9-1 l

3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3L /4.9.3 DECAY' TIME..............................................

3/4 9-3 l

3/4.9.4 CONTAINMENT PENETRATIONS.................

3/4 9-4 i

3/4.9.5: -COMMUNICATIONS....................................

3/4 9-5 3/4.9.6 ~ MANIPULATOR CRANE.......................................

3/4 9-6 1

'3/4.9.7 CRANE: TRAVEL - FUEL HANDLING _ BUILDING..............

3/4 9-7 3/4.9.8_

RESIDUAL _ HEAT REMOVAL AND COOLANT CIRCULATION-High Water Level................

3/4 9-8 Low Water Level.......................................

3/4 9-9 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM..........

3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VE5SEL...........

3/4 9-11 Fuel-Assemblies.................................

3/4 9-11 Control Rods..........................................

3/4 9-11a 1

3/4.9.11 WATER LEVEL - SPENT FUEL P00L.....

3/4 9-12 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM...............

3/4 9-13 3/:4.9.13 SPENT FUEL SHIPPING CASK M0VEMENT.......................

3/4 9 l

'3/4.9.14 ' SPENT FUEL-ASSEMBLY-ST0 RAGE.............................

3/4 9 i v

3/4.10' SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.........................................

3/4 10-1 3/4.10.2_ GROUP HEIGHT,_ INSERTION AND POWER DISTRIBUTION LIMITS...

3/4 10-2

~3/4.' 10. 3 PHYSICS TESTS...........................................

3/4 10-3 3/4.10'.4-. POSITION' INDICATION SYSTEM - SHUTD0WN...................

3/4 10-4 DIABLO CANYON - UNITS 1 & 2 xii Amendment Nos. 39 & 38, 72 & 71

e

. eL SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS J

REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1..The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY:

As shown for each channel in Table 3.3-1.

ACTION:

With a Reactor Trip System Instrumentation or Interlock Setpoint less con-servative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Trip Setpoint adjusted consistent with the Trip Setpoint value.

DIABLO CANYON - UNITS 1 & 2 2-3

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-TABLE 2.2-1 b

REACTOR TRIP SYSTEM INSTRlI6NTATION TRIP SETPOINTS 9

i FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E

1. Manual Reactor Trip N.A.

N. A.

i C

ii

2. Power Range, Neutron Flux d

a.

Low Setpoint

< 25% of RATED THERMAL POWER

< 26% of RATED THERMAL POWER s

b.

High Setpoint

{109%ofRATEDTHERMALPOWER

_E 110% of RATED THERMAL POWER

~

o.

3. Power Range, Neutron Flux

< 5% of RATED THERMAL POWER with

< 5.5% of RATED THERMAL POWER m

High Positive Rate a time constant > 2 seconds Gith a time constant _> 2 seconds

4. Power Range, Neutron Flux

< 5% of RATED THERMAL POWER with

< 5.5% of RATED THERMAL POWER High Negative Rate a time constant > 2 seconds With a time constant _> 2 seconds

5. Intermediate Range, Neutron i 25% of RATED THERMAL POWER 1 30% of RATED THERMAL POWER

'?

Flux 5

5

6. Scurce Range, Neutron Flux i 10 counts per second i 1.3 x 10 counts per second

7. Overtemperature AT-See Note 1 See Note 2

8. Overpower AT See Note 3 See Note 4

9. Pressurizer Pressure-Low

> 1950 psig

> 1940 psig P

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10. Pressurizer Pressure-High 1 2385 psig i 2395 psig 1

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S

11. Pressurizer Water Level-High

_1 92% of instrument span i 93% of instrument span

=

8

12. Reactor Coolant Flow-Low

> 90% of minimum measured

> 88.9% of minimtmi measured Tiow** per loop Tiow** per loop E

- Minimum measured flow is 89,800 gpm per loop for Unit I and 90,625 gpm per loop for Unit 2.

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j; TABLE 2.2-1 (Continued).

~

E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 9

SE EE FUNCTIONAL UllIT TRIP SETPOINT

' ALLOWABLE VALUES c

13. Steam Generator Water

> 7.2% of narrow range instrument > 6.2% of narrow range instrument

{}

Level-tow-Low span-each steam generator

" span each steam generator v,

s.

14. del".TED

- e.

15. Undervoltage-Reactor

> 8050 voits each bus

> 7935 volts-each bus n>

Coolant Pumps

16. Underfrequency-Reactor

> 54.0 Hz - each bus

> 53.9 Hz each bus Coolant Pumps

17. Turbine Trip l'

a.

Lcw Autostop Oil

-> 50 psig

~> 45 psig Pressure a.

Turbine Stop Valve

> 1% open

> EE open Closure

18. Safety Injection Input N.A.

N.A.

from ESF BI

19. Reactor Coolant Pump N.A.

N. A.

Breaker Position Trip E

20. Reactor Trip Breakers N.A.

N.A.

Ei

21. Automatic Trip and N.A.

N.A.

T Interlock Logic E

a.

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'j DIAF.LO CANY0k UNITS 1 & 2 2-6 Amendment Hos.30 and 29 y

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TABLE 2.'2-1 (Continued)

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REACTOR TRIP' SYSTEM INSTRUMENTATION TRIP SETPOINTS 9

TABLE NOTATIONS-E NOTE 1:

OVERTEMPERATURE AT d

AT < AT, [K -K 1+t 5 - (T-T ~)+K (P-P ')-f (AI)]

i 2 1

3 i

1+r2S y

w ru Where:

AT, = Indicated AT at RATED THERMAL POWER; T = Average. temperature, "F; T' = < 576.6*F for Unit 1 and < S77.6*F. for Unit 2 Reference T at 4ATED THERMAL POWER;

~

"#9 Y

P = Pressurizer pressure, psig; 9

P' = 2235 psig'(indicated RCS nominal operating pressure);

= The function generated by the lead-lag controller for T,yg 2

dyr.amic compensation;-

&Y2 = Time constants utilized in the lead-lag controller for T ti I2 = 4 s; avg. It = 30 s,

^s l

5 = Lapiace transform operator, s 1; K3 = 1.200 P

K2 = 0.01'8t7/ F w

[

K3 = 0.000831/psig

=

U

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.E TABLE'2.2-1 (Continued)

Y REACTOR'iWIP., SYSTEM INSTRUMENTATION TRIP SETPOINTS-e-

2 2E

~TA*3tE NOTATIONS (Continued)

EE' NOTE 1 (Continued).

-. and fy (al) is a' function of the. indicated diifference between top and bott.om detectors 1 -of the power-range nuclear ion chambers; with gains to be selected based on seasured l]

instrument response during plant-startup tests lsuch that:

(i) for qt- ~9b between - 19% and.+ 9%, fy (aI) = 0 l

'(where qt and q are percent, RATED THERMAL POWER in the top and bottom b

-halves of-the core respectively, and qt

4 is total THERMAL POWER in

- b percent of RATED THERMAL F0WER).

q, (ii) for each percent that.the magnitude of (q ~ 9 ) exceeds

'19%, the aT t

b

-Trip Setpoint shall be~ automatically reduced by 2.75% of its value at RATED THERMAL POWER.

(iii) for-each percent'that the magnitude of-(q ~ 4 ) exceeds +'TK, the AT Trip t

b Setpoint~shall be automatically reduced by 1.76% of its value at RATED' THERMAL POWER.

gr NOTE 2:

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than

.g 3.2%.

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o-5; TABLE 2.2-1L(Continued) c?

c' REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 9

2E TABLE NOTATIONS (Continued)

E e NOTE 3:

OVERPOWER ai

' 55 Of AT < AT [K -Ks (2 51+t 5) T - Ks (T-T")-f (al)3 '

g 3

2 s.

3 c.

no Where:

AT, = Indicated AT at rated porwr;

'T = Average temperature, *F; T" = < 576.6*F for' Unit I and < 577.6'F' for Unit 2 Reference T at RATED THERMAL POWER; avg S'

K4 = 1.072 e

K5 = 0.0174/*F for increasing average temperature and 0 for decreasing average temperature; Ks = 0.00145/*F for T > T"; Ks = 0 for T $ T";

5

'b y,1 g = The function generated by the rate lag controller for T,yg 37 dynamic compensation; ea 13 = Time constant utilized in the rate laq controller for T g

13 = 10 s; av9 R

S = Laplace transform operator, s 1; and z

3 f (AI) = 0 for all AI.

2 D

NOTE 4:

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.6%.

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-LIMITING SAFETY-SYSTEM SETTINGS BASES Steam Generator Water Level The Steam Generator Water Level Low-Low trip protects the reactor from loss of heat sink in the event of a sustained steam /feedwater flow mismatch resulting from loss of normal feedwater.

The specified Setpoint provides allowances for starting delays of the Auxiliary Feedwater System.

Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Uncerfrequen:y Reactor Coolant Pump Bus trips-provide core protection against DNB as a result of complete loss of forced coolant flow.

The specified Setpoints assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached.

Time delays are incorporated in the Under-frequency and Undervoltage trips to prevent spurious Reactor trips from momen-tary-electrical power transients.

For undervoltage, the delay is set so that the time required for a signal to reach the Reactor trio breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall not exceed 0.9 seconds.

For underfrequency, the delay is set so that the time required for a signal to reach the Reactor trip breakers after the Underfrequen-cy Trip Setpoint is-reached shall not exceed 0.3 seconds.

On decreasing power, the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are automa-tically blocked by P-7 (a power level of approximately 10% of RATED TliERHAL POWER with a turbine impulse chamber pressure at approximately 10% of full power equivalent); and on increasing power, reinstated automr'ically by P-7.

DIABLO CANYON - UNITS 1 & 2 B 2-7 Amendment Nos.

55 & 55, 72 & 71

LIMITING SAFETY SYSTEM SETTINGS I'

BASES Turbine Trio A Turbine trip initiates a Reactor trip.

On decreasing power, the Turbine trip is automatically blocked by P-9 (a power level of approximately 50% of RATED THERKAL POWER); and on increasing power, reinstated automatically by P-9.

Safety injection Input from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which initiates a Safety Injection. The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.

Reetter Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position trip is an anticipatory trip which provides score protection against DNB.

The Open/Close Position trip as-sures a reactor trip signal is generated before the Low Flow Trip Setpoint is reached.

No credit was taken in the safety analyses for operation of this trip.

The functional capability at the open/close position settings is re-quired to enhance the overall reliability of the Reactor Trip System.

Above P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10% of full power equivalent) an auto-matic. reactor trip will occcur if more than one reactor Molant pump breaker is opened.

Below P-7 the trip function is automatically blocked.

Reactor 1 rip System Interlocks The Reactor Trip System Interlocks perform the following functions:

P-6 On increasing power, P-6 allows the manual block of the Source Range trip and de energizing of the high voltage to the detectors.

On de-creasing power, Source Range Level trips are automatically reacti-vated and high voltage restored.

P-7 On increasing power, P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, more than one reactor coolant pump breaker open, reactor coolant pump bus undervoltage and underfrequency, pressurizer low pressure and pressurizer high level.

l On decreasing power, the above listed trips are automatically biccked.

DIABLO CANYON - UNITS 1 & 2 B 2-8 Amendment Nos. 30 and 29 M'

.s

'3/4.1 REACTIVITY CONTROL SYTEMS 3/4.1.I' B0 RATION CONTROL

-SHUTDOWNMARGIN--T,ygGREATERTHAN200'F

_ LIMITING CONDITION FOR OPERATION' 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.6% ak/k.

APPLICABILITY:

MODES 1, 2*, 3, and 4.

ACTION:

I With the SHUTDOWN MARGIN less than 1.6% ok/k, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE-REQUIREMENTS 4.1,1,1,1 The SHUTDOWN MARGIN shall be determined to be greater than or equal

-to 1.6% ok/k:

'Within 1. hour after detection of an inoperable control rod (s) and a.

at'least once-per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereifter while the rod (s) is inoperable.

If the inoperable control rod is immovable.or untrippable, the above

. required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable con-trol:roa(s);

b.

When in MODES.1 or 2 with K,ff greater than or equal to 1, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying-that control ~ bank withdrawal is within the limits of Specification 3.1.3.6;-

When in MODE 2 with K,ff.less than 1, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achiev-c.

ing reactor criticality by verifying that the predictcd critical control rod position is within the limits of Specification 3.1.3.6; d.

' Prior to initial operation above 5% RATED THERMAL POWER after each fuel' loading, by consideration of the factors of Specification

-.4.1.1.1.le., below, with the control-banks at the maximum insertion-limit of Specification _3.1.3.6;_and

5ee.Special'E stiExceptions' Specification 3.10.1.

DIABLO CANYON UNITS 1 & 2 3/4 1-1 Amendment Nos.

53 & 52, 72 & 71

REACTIVITY CONTROL = SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)-

When in MODES 3_ or_4, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of e.

the following factors:

1)-

Reactor Conlant System boron concentration, 2)- -Control rod position.

[

3)

Reactor Coolant Syster: average temperature, 4),

Fuel burnup based on gross thermal energy generation, a

5)

Xenon concentration, and h

6)

Samarium concentra-4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to ~ demonstrate-agreement within i 1% Ak/k at least once per 31 Effective _ Full Power Days.(EFPD).

those factors-stated in Specification 4.1.1.-l.le., above.This comparison sha The predicted 1 reactivity _ values shall be adjusted (normalized)~to correspond to the-actual core conditions prior to exceeding a fuel burnup of 60 EFPD_after each. fuel loading.

t f

t r

m l

i t

.:DIABLO CANYON -; UNITS 1 & 2 3/4 1-2

-~

r

$a EREACTIVITY CONTROL SYSTEMS, SHUTOOWN MARGIN -lT,ygjLESS THAN OR EQUAL-TO 200'F-m N

-LIMITING CONDITION FOR OPERATION i

3rl.li2.The SHUTDOWNLMARGIN shall be greater than or equal to 1% Ak/k.

- APPLICABILITY:

MODE 5.

! ACTION:.

!With:the SHUTOOWN MARGIN less than 1% Ak/k,.immediately initiate and continue.boration at greater than t.r equal to 30 gpm of a solution containing greater than or equal to 7,000.;

Soron or equivalent until the required

-SHUTDOWN MARGIN-is restored.c 1

LSURVEILLANCE REQUIREMENTS 4.1.1.-2 The SHUTDOWN MARGIN =shall be determined to be greater than or equal Lto:l% Ak/k.

c La.1 ~Within 1-hourfafterLdetection-of an inoperable control-rod (s) and at'least once-per'12: hours. thereafter while'the. rod (s) is inoperable.

IfL the inoperable control rod is immovable or.untrippable, the SHUTDOWN-MARGIN shall be verified acceptable with an increased allowance for the J

-withdrawn-worth =of.the'imcovable or untrippable control rod (s);-and b.

At11 east!once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of.the following factors:

1)

Reactor Coolant System boron'concentravion,.

-l2)-. Control _ rod pesitfon, 13).

Reactor Coolant System average temperature,.

(4)'

Fuel!burnup based on gross-thermal energy; generation-

-5)

Xenon: concentration, and-

'6)

Samarium concentraticr..

DIABLO CANYON =--UNITS:1 & ?

-3/4 2-3 AMENDMENT N05.

52 & 52, 72 & 71 p

y Q,

3-W m.

,. =-.----

, c REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a.-

-Less positive than +5 x 10 8 AVU'F for 05 to 701 RATED THERMAL POWER, and for > 70% to 100% RATED THERMAL POWER the MTC decreases linearly to 0 AK/R/'F for the all rods withdrawn condition, beginning of cycle life (80L); or 4

b.

Less negative than -3.9 x F AVU'F for all rods withdrawn, and of cycle life (EOL), RATED THERMAL POWER condition.

APPLICABILITY:

Specification 3.1.1.3a.

MODES I and 2* onlyf.

Specification 3.1.1.3b. - MODES 1, 2, and 3 onlyf.

ACTION:

With the MTC more positive than the limit of Specification 3.1.1.3a.

a-above, operation in MODES I and 2 may proceed provided:

- 1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than the limit of l

i-Specification-3.1.1.3a within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6. hours. These withdrawal limits shall'be in addition to the insertion limits of Specificatibn 3.1.3.6; 2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation veriffes that the MTC has been restored to within its limit for the all rods withdrawn condition; and-3.

A Special Re.nort is prepared and submitted to the Consission pursuant to Specification 6.9.2 within 10 days describing' the value of the measured MTC, the interim control rod withdrawal limits and the predictto average-core burnup-necessary for m

- restoring the positive MTC to within its limit for-the all rods withdrawn. condition, b.

With the MTC sore negative than the limit of Specification 3.1.1.3b.

above..be in HOT SHUT 00WN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3.0.4 are not applicable.

c.

l

With K,ff greater t;an or equal to 1.

-#See Special! Test Exceptions-Specification 3.10.3.

1 DI ABL O CANYON - UNITS ~1 & 2 3/4 1-4 Amendment Nos.10, 8

t

_4' 4.

REACTIVITY CONTROL SYSTEMS

-3/4.1.2 BORATION' SYSTEMS FLOW PATH - SHUTDOWN LIM' TING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE with motor-operated valves required to change position and pumps f required to operate for boron injection capable of being powered from an OPERABLE' emergency power source:

A'. flow path from the boric acid tanks via a boric acid transfer pump a;

and' charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.Sa. is OPERABLE, or b.

The flow path frora the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5b. is OPERABLE.

APPLICABILITY:

MODES 5 and 6.

ACTION:

.With none.of the above flow: paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operatiens involving CORE

-ALTERATIONS or positive' reactivity changes.

-SURVEILLANCE REQUIREMENTS 4,L 2.1 At least one of the above requirto flow paths shall be demonstrated

_OPiRABLE:

-At least once per.7 days _by verifying that the temperature of the flow a.

path is greater than or equal to 65*F when a flow path from the boric a'cid'. tanks is~used, and.

2 b.

At least once per 31. days by verifying that each_ valve (manual,

-power-operated or automatic) in the flow path that is not locked, sealed or.otherwise securied in pisition, is in its correct position.

DIABLO CANYON - UNITS 1 & 2-3/4 1-7 Amendment Nos.

53 & 52, 72 & 71

REACTIVII' CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 Each of the following boron injection flow paths shall be OPERABLE:

a.

The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System (RCS), and b.

The flow path from the refueling weter storage tank via a charging pump to the RCS.

APPLICABILITY:

MODES 1, 2, 3 and 4#,

ACTION:

a.

With the flow path from the boric acid tanks inoperable, restore the inoperable flow path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1% Ak/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the flow path to OPERABLE status within the next 7 days or be in COLD SHUTDOWN withfu the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the flow path from the refueling water storage tank inoperable, restore the flow path to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANLE RE0VIREMENTS 4.1.2.2 Each of the above required flow paths shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the temperature of the flow path from tt.e. boric acid tanks is greater than or equal to 65 F, b '.

At least once per 31 days by verifying that each valve (manual, power-operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position, c.

At least once per 18 months by verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test

. signal, and d.

At least once per 18 c.; ^ 5y verifying that the flow path required by Specification 3.1.2 2r e /.ivers at least 30 gpm to the RCS.

l

0nly_one boron injection flow path is required to be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 323'F.

I DIABLO CANYON - UNITS 1 & 2 3/4 1-8 Amendment Nos.

52 & B2, 72 & 71

4 4

4 THIS PAGE WAS INTENTIONALLY LEFT BLANK DIABLC CANYON - l' NITS 1 & 2 3/4 1-9 Amendment Nos.

53 & B2 72 & 71

i

. REACTIVITY CCNTROL'5YSTENS CHARGING PUMP - $HUTDOWN-I LIMITING CONDITION FOR OPERATION _

i i

i 3.1.2.3 At least one charging pump in the boron injection flow path regi: fred

- by Specification 3.1.2.1 shell be OPERABLE and capable of'being powered from an OPERA 8LE emergency power source.

APPLICABILITY:

MODES 5 and 6.

L ACTION:.

With no. charging _ pump OPERABLE or capable of being powared from en OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or

. positive. reactivity-changes.-

SURVEILLANCE REQUIREMENTS 4.1.2.3.1 At 1 east the above required chirging pump shall be demonstrated-s OPERABLE when tested' pursuant to specification-4.0.5.

In addition. when-the above required charging pump.is e centrifugal charging pump, verify that, on

recirculation. flow,-the-centrifugal charging pump develops a differential i

pressure of greater than or-equal to 2400 psid.

4.1.2.3.2 LEA 11 centrifugal. charging pumps, excluding the above required OPERABLE pump, shall-be demonstrated inoper6ble*<at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,-except when thez reactorivessel-head is removed,'by verifying that the motor breaker D.C.

-control: power is--de-energized.

n L'Anqinoperable ' pump may.be made OPERA 8LE;for testing per Specification 4.0.L fprovidedithe: discharge of:the: pump-has.been: isolated from the Reactor Coolant System-by an: isolation valve with power; removed from the valve operator, or byfa sealed cloced manual isolation valve,

~

DIABLOLCANYONL: UNITS 1 & 2-3/4 1-10

^ A t

l' 1

2

_. _ _, -. -, _ - -, - -. ~,,. - _. - -

_;-__-.._-_--._-~..-.,m_--,.------_a,,,,,,-..,u.....;-;,.

REACTIVITY CONTROL SYSTEMS CHARGING ' UMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.

APPLICABILITY: H0 DES 1, 2, 3 and 4#.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1% Ak/k at 200'F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next-7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5.

In addition, when the above required charging pumps include a centrifugal charging pump (s), verify that, on recircu-lation flow, each required centrifugal charging pump (s.' develops a differential pressure of greater than or equal to 2400 psid.

4.1.2.4.2 All centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable" at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the Reactor Coolant System (RCS) cold legs is less than or equal to 323*F by verifying that the motor breaker D.C. control power is de-energized.

A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 323'F.

An inoperable pump may he made OPERABLE for testing per Specification 4.0.5 provided the discharge of the, pump has been isolated from the Reactor Coolant System by an isolation valve with power removed from the valve operator, or by a sealed closed manual isolation valve.

DIABLO CANYON - UNITS 1 & 2 3/4 1-11 j

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

l a.

A Boric Acid Storage System with:

1) A minimum contained borated water volume of 2,499 gallons,

2) A boron concentration between 7,000 and 7,700 ppm, and

3) A minimum solution temperature of 65*F.

b.

The Refueling Water Storage Tank (RWST) with:

1) A minimum contained borated water volume of 50,000 gallons,

2) A minimum boron concentration of 2300 ppm, and

3) A minimum solution temperature of 35'F.

APPLICABILITY:

MODE' 5 and 6.

ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required burated water r.ource shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration of the water, 2) v6*yingthecontainedboratedwatervolume,and 3)

VerPMng the boric acid storage tank solution temperature when it'is the source of borated water, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the source of borated water and the Outside ambient air temperature is less than 35'F.

l l

l DIABLO CANYON - UNITS 1 & 2 3/4 1-12 Amendment Nos.

53 & BZ, 72 & 71

l-REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING MHITINGCONDITIONFOROPERATION 3.1. 2. 6 Each of the following borated water source (s) shall be OPERABLE:

I a.

A Boric Acid Storage System with:

1)

A minimum contained borated water volume of 14,042 gallons, 2)

A boron conceatration between 7,000 and 7,700 ppm, and 3)

A minimum solution temperature of 65*F.

b.

The Refueling Water Storage Tank (RWST) with:

1)

A contained borated water volume of greater than or equal to 400,000 gallons, 2)

A boron concentration between 2300 and 2500 ppm, and 3)

A minimum solution temperature of 35 F.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the Boric Acid Storage System inoperable, restore the system a.

to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 borated to a SHUTDOWN MARGIN equivalent to at least 1% Ak/k at 200*F; restore the Boric Acid Storage System to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the RWST inoperable, restore the tank to OPERABLE status within I hour or be in at least h0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and ir.

COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

DIABLO CANYON - UNITS 1 & 2 3/4 1-13 Amendment Nos.

59 & 58, 72 & 71

i

s..,

r,..

Gyid'lj,..urROLSYSTEMS

.y[

i, yc'l-Lfj~IILLANCEREQUIREMEPTS cc 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration in the water.

2)

Verifying the contained borated water volume of the water st. cree, and 3)

Verifying the Boric Acid Storage System solution temperature.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the.RWST 1 sture when the outside air temperature is less than 35'F.

DIABLO CANYON - UNITS 1 & 2 3/4 1-14

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 One digital rod position indicator (excluding demand position indi-cation) shall be OPERABLE and capable of determining the control rod position within i 12 steps for each shutdown oi control rod not fully inserted.

APPLICABILITY:

MODES 3*#, 4*# and 5*#.

ACTION:

With less than the above required position indicator (s) OPERABLE, immediately open the Reactor Trip System breakers.

SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when exercised over the full range of rod travel at least once per 18 months.

?.

With the Reactor Trip System breakers in the closed position.

See Special Test Exceptions Specification 3.10.4 DIABLO CANYON - UNITS 1 & 2 3/4 1-19

REACTIVITY CONTROL SYSTEMS R0D DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length shutdown and control rod drop time from the fully withdrawn position shall be less than or equal to 2.7 seconds from beginning l

of decay of stationary gripper coil voltage to dashpot entry with; T,yg greater than or equal to 541'F, and a.

b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES I and 2.

ACTION:

With the drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods.following each removal of the reactor vessel head, b.

For specifically affected individual rods following any main-tenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and c.

At least once per 18 months.

DIABLO CANYON - UNITS 1 & 2 3/4 1-20 Amendment Nos. 37 & 38,72 & 71

POWER DISTRIBUTION LIMITS 3/4.~2.5 DNB PARAMETERS.

I LIMITING CONDITION FOR OPERATION i

3.2.5 The'following DNB related parameters shall be maintained within the

-limits shown on Table 3.2-1:

l

a..

Reactor Coolant System T,yg, and b.

Pressurizer Pressure.

APPLICABILITY:

MODE 1.

ACTION:

~With any of'the above parameters exceeding its limit, restore the parameter to-

-4 within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 5% of RATED.. THERMAL. POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .-

SURVEILLANCE REQUIREMENTS-

.4!2.5.1 Each of the-parameters of Table 3.2-1 shall be verified to be'within

-their limits at least once per'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

DIABLO CANYON - UNITS 1 & 2 3/4 2-21 Amendment Nos. 37 and.36

. Effective at end of Unit 1 Cycle 3

,y u

6 TABLE 3.2-1 t

DNB PARAMETERS PARAMETER' LIMITS Actual Reactor Coolent System T

< 584.3"F avg Actual Pressurizer Pressure

> 2212 psia

l 1

i

/

k i

. )

2

- 4

-1.n ei k'

,';3.,

u either a THERMAL POWER ramp-in' excess of 5% RATED

" Limit-not applicable.~during'a THERMAL. POWER step in excess of 10% RATED

^

THERMAL POWER per minute or.

POWER.>

+

TDIABLO CANYON UNITS 1 & 2-

'3/4 2 Amendment Nos. 37 &-36, 72.& 71 1

7U~

.L.

_.4.._,

..a g.

TABLE 3.3-1 (Continued)

. REACTOR TRIP SYSTEM INSTRUMENTATION E'

~

MINIMUM

3!

' TOTAL NO.

CHANNELS CHAMMELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP.

OPERABLE:

' h00ES -

. ACTION e

c

.12.- ' Reactor. Coolant Flow-Low 5$

'a.

Single Loop 3/ loop' 2/ loop-in

2/ loop in.

1 6

(Above P-8)'

-;one loop each loop cp b.

Two Loops 3/ loop

2/ loop.in 2/ loop in-1 6

m.

.(ehove P-7 and below P-8)

.two loops each loop 13.

Steam Generator Water 3/S.G.

2/S.G. in 2/S.G. In 1, 2 6

Level-Low-Low.

one S.G.

each S.C R

14.

DELETED Y 15. Undervoltage-Reactor Coolant 2/ bus 1/ bus 1/ bus' 1

6

'd Pumps both busses

16. Underfrequency-Reactor Coolant.

3/ bus 2 on same bus 2/ bus 1

6 Pumps 17.

Turbine Trip k

'a.

Low Autostop 0il Pressure-3 2

2 1

7 k

b.

Turbine Stop Valve' Closure 4

4-4 1

7 5

r E

e 1_54 Oo

~

g

' TABLE 3.3-1 (Continued)-

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM 14

TOTAL NO.

CllANNELS CHANNELS APPLICABLE-l-

3 FUNCTIONAL UNIT Of CHANNELS TO TRIP OPERABLE MODES ACTION

-h

.18 Safety Inject 3on Input from ESF..

2' 1

2.

1, 2

'26 l

V

19. -Reactor Coolant Pump Breaker y

Position Trip aoove P-7

-1/ breaker 2

1/ breaker 1

9 20.

Reactor Trip' Breakers' 2-1 2

1, 2 10, 12 2

1 2

3*, 4*, 5*

11

21. Automatic Trip and Interlock '

2 1

2 1, 2 26 l

Logic' 2

1 2

3*, 4*, 5*

11 R

22.

Reactor Trip System Interlocks w

a.

Intermediate Range Neutron Flux, P 2 1

2 2N 8

b.

Low Power Reactor

~ Trips Block, P-7 P-10 Input' 4

2 3

1 W

'P-13 Input 2

1 2

1 M

c.

-Power Range Neutron Flux, P-8 4

2 3

1 M

[

d.

Power Range Neutron

=

Flux, P-9 4

2 3

1 M

e.

Power Range Neutron Flux, P 4 2

3 1, 2 M

[

f.

Turbine Impulse Chamber

g Pressure, P-13 (Input to P-7) 2 1

2 1

M p

23.

Seismic. Trip

'3 direc-2/3 loca-2/3 loca-1, 2 13 g

tions (x,y,z) tions one Lions all in 3 locations direction

' directions 1

w

TABLE 3.3 1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 9 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 10 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 11 - With the number of OPERABLE channels one less than 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 open the Reactor trip breakers within the next hour.

ACTION 12 - With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 10.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 13 - With tne number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The Minimum Channels OPERABLE requirement is met, and b.

The inoperable channel is placed in the tripped conditions within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, the inoperable channel may be bypassed for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for surveillance testing per Specification 4.3.1.1 or for performing maintenance.

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable Channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel say be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for curveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

DIABLO CANYON - UNITS 1 & 2 3/4 3-7 Amendment Nos.

and

TABLE 3.3-2 i

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 1

FUNCTIONAL UNIT RESPONSE TIME l

1.

Manual Reactor Trip N.A.

l 2.

Power Range, Neutron Flux

$ 0.5 second*

3.

Power Range, Neutron Flux, j

High Positive Rate N.A.

4.

Power Range, Neutron Flux, High Negative Rate 5 0.5 second*

5.

Intermediate Range, Neutron Flux N.A.

'6.

Source Range, Neutron Flux

< 0.5 second*

7.

Overtemperature AT

$ 4 seconds

8.

Overpower AT N.A.

9.

Pressurizer Pressure-Low

$ 2 seconds 10.

Pressurizer Pressure-High 5 2 seconds 11.

Pressurizer Water Level-High.

N.A.

12.

Reactor Coolant flow-Low a.

Single Loop (Above P-8) 5.1 second b.

Two Loops (Above P-7 and bel W P-8) 5 1 second 13.

Steam Generator Water Level-Low-Low

$ 2 seconds-14.~ - DELETED-l 15.

Undervoltage-Reactor Coolant Pumps 5 1.2 seconds 16.

Underfrequency-Reactor Coolant Pumps 1 0.6 second

Neutron detectors are exempt from response time testing.- Response time of

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

DIABLO CANYON - UNITS 1-& 2 3/4 3-8 Amendment Nos. 56 & 55, 72 & 71

_u m_

r-;

.a

-u_

= TABLE 4.3-1-(Continued)-

REACTOR TRIP SYSTEM. INSTRUMENTATION' SURVEILLANCE REQUIREMENTS o-TRIP g

ANALOG ACTUATING MODES FOR ClANNEL DEVICE WHICH

'$l g

CHANNEL CHANNEL OPERATIONAL OPERATIONAL

-ACTUATION SURVEILLANCE FUNCTIONAL UNIT.

CHECK CALIBRATION TEST TEST-LOGIC' TEST IS REQUIRED Cz 13.

Steam Generator M rJ.evel-S

.R Q.

N. A..

N.A.

1, 2 g

Low-Low

[-14.-l DELETED.

l.

15. Undervoltage-Reactor Coolant N.A.

R N.A.

Q N.A.

1:

Pumps

16. Underfrequency-Reactor N.A.

R N.A.

Q N.A.

1 Coolant Pumps l.

l 1

17. Turbine Trip-E a.'

Low Fluid Oil Pressure N.A.

N.A.

S/U(1, 9)

N.A.

I L

-b.

. Turbine Stop Valve N.A.

N.A.

S/U(1,9)

N.A.

1 Closure l

N.A.

N.A R

N.A 1, 2 l

.18.

Safety Injection Input from ESF g

19.

Reactor Coolant Pusp Breaker M. A.'

N.A.

R M.A.

1 g

Position Trip 1

a i

5 20.

Reactor Trip System Interlocks f+

a.

Intermediate Range N.A.

R(4)

R N.A.

N. A.

2M Neutron Flux, P-6 z

il E

b.

Low Power Reactor Trips Block, P-7 N. A; R(4)

R N.A.

N.A.

1

=

c.

Power Range Neutron

[.

Flux,'P-8' N.A.

R(4)

R N.A.

M.A.

-1

=

(<

a-

. _~._

gg iI a,

w Mr, 5

g eg e

+5 W

~

4 4

~

~.

g W

M M.

M M

w M

N 5E c~

d 4

sse s

2 i

i iiW w

i E

e5 m

W w

2 E

g g

W g

4 4

e e

y

$d2 i

i i

E i m ; - 2C i

.iss53

,J

'g EWWh#

E a

a

.=

g I I s"f=%

5

.e 7

m

=

m a

a a

'k 0 8 E

E S

1 2

A i

t.

.2!

E-w 5

5 5

i Sl~g l =!

w a

a a

m x

u a

c5 E

l k

$6 4

4 i $$

3w a

x a

a a

m-a h

C OI e 5

?{.

.a 1

L i

j 4

l v

r E

te e

L W

T ji g g

E-A h T M [L 5

E m{ -

ge_.g~rl s e

. s-as 2

b j

N Ab gy fg jj_jf g

~u E

g.

g u y

r_.x s=.

9 se i e

a 3ll dd dd l

'D]ABLO CANYON - UNITS 1 &-2.

3/4 3-12 Amendment Nos. 48 and 47 b

1

%7.-

~

?E c,-

~

l TABLE 3.3-4.

g

~

7

' ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

~'

m o

'y i FUNCTIONAL UNITL TRIP SETPOINT' ALLOWABLE VALUES E"

~. Safety Injection (Reactor Trip, Feedwater 1.

' Isolation, Start Diese1' Generators,.

e.

5 Containment Fan Cooler Units, and d

-Component Cooling Water)~

.c a.

Manual Initiation N.A.

N. A.

b.'

Automatic Actuation Logic M.A.

N.A.

and Actuation Relays c.

Containment Pressure-High

"$ 3 psig.

5 3.5 psig d.

- Pressurizer Pressure-tow 1 1850 psig 1 1840 psig w

A e.

Differential Pressure 5 100 psi 1 112 psi w

Between Steam Lines-High f..

Steam Flow in Two Steam Lines-

< A function defined as

< A function defined as High follows:- A ap corre-Tollows: A op corresponding sponding to 40% of full to 44% of full steam flow steam flow between 0% and between 0% and 20% load and 20% load and then a Ap in-then a op increasing linearly k

creasing. linearly to a Ap to a op corresponding to g

corresponding to 110% of 111.5% of full steam flow at g

full steam flow at full full load.

g load.

i.

zg Coincident With Either, 1)

T,y9. Low-Low, or

'l 543'F

> 540.2*F y

-Steam Line Pressure-Low-1 600 psig

> 580 psig I

g i

a.

j i

j

y-p a.

TABLE 3.3-4 (Continued)

B B

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SEtPOIMTS 5

n E

FUNCTIONAL UNIT-~

'. TRIP SETPOINT-ALLOWELE VALUES a

8.

2..

Containment Spray E

a. -

Manual Initiation N.A.

M. A.

U b.

Automatic' Actuation Logic and-N.A.

N.A.

Actuation Relays e-c.

Contairupent Pressure-High-High 5 22 psig i 24 psig

' 3.

Containment Isolation

~

a.

Phase "A" Isolation-w1 1)

Manual M.A.

N.A.

w A

2)

' Automatic Actuation Logic M.A.

N. A.

.and Actuation Relavs 3)

Safety Injection-See Item 1. above for all Safety I.3xtion Trip Setpoints and Allowable Values.

b.

Phase d8" Isolation i

s)

Manual N.A.

M.A.

l 2)

Automatic-Actuation Logic M.A.

N.A.

and Actuation Relays 2)

Containment Pressure-High-High 1 22 psig

$ 24 psig i.

i r

.a c w

~-

'; win.

+=

- = - ~ = -

=

.

--?

ypg 97.

N-a^

~

/.

> i

-c 4

2 TABLE'3.3-4 (Continued)2

~ - 1 7g..

) ENGINEERED SAFhTY' FEATURES ACTUATIOM SYSTEM INSTRUMENTATION TRIP SETPOINTS

- g E FUNCTIONAL UN1_T.-

IRIP SETPOINT:

ALLOWABLE '.'ALUES -

i. 3. ' ContainmentL Isolation (Continued)

L

'E c.-

~ Containment Ventilation Isolation e

^1).: : Automatic Actuation.Logicc

. N. A. -

N. A.

.c.

5-andl Actuation Eclaya I

2)

(PlaitVent' Noble' Gas.

Fer the ODCP l.

Activity-High (PJt-14Ai m'

and 148)(a' 3)', Safety -Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

4)' ' Containment Ventilation Per Specification 3.3.3.10 w

l' Exhaust Radiation-High Y

(RM-44A and 448)(b)

E 4.

Steam Line Isolation a.

Manual.

.N.A.

N.A.

b.

Automatic Actuation. Logic N.A.

N.A.

'and Actuation Relays c.

Containment Pressure-High-High

< 22 psig

< 24 psig

,{

w d.

-Steam Flow in Two Steam Lines-

< A function defined as

,,gg-High-Tollows: A ap correspond-Tollows: A op corresponding og ing to.40% of full steam to 44% of full steam flow be-flow between 0% and 20%

tween 0% and 20% load and

g load and then a op increas-then a op increasing linearly E> r ing linearly to a op corre-to a op corresponding to c., %

sponding to 110% of full 111.5% of full steam flow at

o. N steam flow at full load.

full load.

cno

E

, (a)The requirements for Plant Vent Noble Gas Activity-High (RM-14A'and 138) are not applicable following

'm installation of RM-44A and 448.

(b)The requirements for Containment Ventilation Exhaust Radiation-High (RM-44A and 448) are applicable fellowing installation of RM-44A and 448.

1

+

er

=

..-w.

...... ~ -,

y ow~

-.c

---,.,.w.,%,.

4--*

m..,w

,%=.

us.

n ye 9-4 h.

[

2R"*

f

m

..g TABL'E3.3-4(Continued)

~

27 u

y ENGINEERED %FETY FEATURES ACTUATION SYSTEM INSTRUMENTATION' TRIP SETPOINTS

~'

,o 3-

.~

g.

5 FUNCTIONAL UNIT

-TRIP.SETPOINT

- Att0WA8tE 14tUES~

~

9

(

4 I

5

. Coincident With Eitherc

~

^

-E:

T,,g-Low-Low,[or' 1)'

4>_ 543'F.

> F K2*F "I

C-

'5

,2)

Steam Line Pressure-Low-

> 600 psig

> 580 psig 7.

5.

' Turbine Trip ard Feedwater.IsolationL y.

n.

.a.

Automatic Actuation Logic-

- N.A.

. h. A.-

m ar.d Actuation Relays.

b.

-Steam Generator Water level-In.67% of narrew range

< 68K of narrow range

-High-High.

strument span each steam.

Instrument scan each steam o

generator.

k 6.

Auxiliary Feedwater-m4 e

a.

~ Manual N. A.

- N. A..

b.

Automatic Actuation Logic N.A.

N. A.

j g-and Actuation Relays'..

g-c.

Steam" Generator L> 7.2% of narrow range

> 6.2% of narrow range Water level-Low-Low.

Instrument span each Instruaent span each

,g' steam generator.

steam generator.

d.

Undervoltage - RCP

- > 8050 volts-

> 7935 volts

,=

e.

Safety Injection y

See Item 1.' above for all Safety Injection Trip Setpoints and Allowable Values.

E e

N.

.)

-w r.

n y

ma.

.n y -,

r

,,r

-m

-s,~<w

..-ww,-

e e

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACfUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS o

E FUNCTIONAL' UNIT TRIP SETPOINT ALLOWABLE vat 0ES r-

-L Loss of Power n

E (4.16 kV Emergency Bus 8

Undervoltage) z a.

First Level E

1)

Diesel Start

> 0 volts with a

> 0 volts with a Z

E 0.8 second time delay E 0.8 second time delay ind ind

> 2583 volts with a

-7 10 second time delay 5 10 second time delay m

2)

Initiation of Load Shed One relay One relay

> 0 volts with a

{4secondtimedelar

[4secondtimedelay and and

> 2583 volts with a

> 2583 volts with a w1 E 25 second time delay

< 25 second time delay with one relay with one relay w

g

> 2870 volts, instantaneous

> 2870 VJ1ts, irstantaneous b.

Second Level 1)

Diesel Start

> 3600 volts with a

> 3600 volts with a 310secondtimedelay

{10secondtimedelay 2)

Initiation of Load Shed

> 3600 volts with a

> 3600 volts with a k

8.

Engineered Safety Features Actuation g

System Interlocks a.

Pressurizer Pressure, P-11

$ 1915 psig

$ 1925 psig b.

Low-Low T,yg, P-12 increasing 543*F

$ 545.8*F z

decreasing 543 F

_ 540.2*F c.

Reactor Trip, P-4 N.A.

N.A.

%w f?*

n

}1

'if TABLE-3.3-5 ENGINEERED-SAFETY FEATURES RESPONSF TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.

Manual Initiation a.

SafetyInjection(ECCS)

N.A.

1)

Feedwater Isolation N.A.

2)

Reactor Trip N.A.

3)-

Phase "A" Isolatien N.A.

-4)

Containment Ventilation Isolation N.A.

5)

~' Auxiliary Feedwater-N.A.

6)

' Component Cooling Water N.A.

7)

Containment Fan Cooler Units

- N. A.

8)

Auxiliary Saltwater Pumps N.A.

b.

Phase "B" Isolation-1)

Containment Spray (Coincident with SI Signal)

N. A.

2)

Containment Ventilation Isolation N.A.

c.

Phase "A" Isolation

- 1)

Containment Ventilation Isolation N.A.

-d[

Steam Line Isolation N. A.

2.

Containment Pressure-High' a,

Safety Injection-.(ECCS)

< 270)/250) 1)

Reactor Trip-72 I'63((2) 2)

Feedwater Isolation 7 18 I)/28(3) i.

3)

Phase "A'! Isolation

- (,-

4). ' Containment Ventilation Isolation H.A.(3) _

- 5)

Auxiliary Feedwater

< 60 6)- -Component Cooling Water 7 38(3)/48(3).

1) 7 40(

7)

-Containment Fan Cooler Units 8)

Auxiliary Saltwater Pumpt 548(1)/58(3) 13.

Pressurizer Pressure-Lot Safety; Injection (ECCSi

< 27(7)/25(4)/35(5)

a.

. 1). 1Reector Trip 7 2 (2).

2)

Feedwater :Isolatioi I 63

-3)

~ Phase."A" Isolaticn i 18(1)-

4)-

Containment Ventilation Isslation N.A.(3)

' 5)

Auxiliary F6edwater

< 60 7 48(3)/38(1) 3)

6)

Component Cooling Water 7 40(

' 7).

Containment Fan holer Units 8)L -Auxiliary Saltwater Pumps 358(3)/48(1) 201ABLO CANYON - UNITS-1-&'2 3/4 3-28 Amendment Nos.

II & Is, 72 & 71

)

vy w

,em' gag g-s 4

gu

TABLE 3.3-5 (Continued) l-

{NGINEERED SAFETY FEAh/RE$ RESPONSE TIMES INIT]AT[NG SIGNAL _AND FUNCTION

_RE$PONSE TIME IN SECONDS 4.

Differential Pressure Setween Steam Lines High Safety Injection (TCCS) i 25(4)/35(5) l a.

1)

Reactor Trip

<1 2)

Feedwater Isolation I 63(2 3)

Phase "A" Isolation i 14II /24II) l 4)

Containment Ventilation Isolation 5)

Auxiliary Feedwater R.A.gg)

< 60 6)

Component Cooling Water i 34gg /44g3) 7)

Containment Fan Cooler Units i 40(I 8)

Auxiliary Saltwater Pumps 348(I /58II) 5.

Steam Flow in Two Staan Lines - High Coincident with T,y,-Low Low

a..

SafetyInjection(ECCS) 1 25I4)/35(5) l 2)

Reactor Trip

<4 2)

Feedwater Isolation I $5(2) 3)-

Phase "A" Isolation i 20(I)/30II) l 4)

Containment Ventilation Isolation R.A.

5)

Auxiitary Feedwater

< 60 6)

Component Cooling Water i 40

/50(I) 7)

Containment Fan Cooler Units 7 40 8)

Auxiliary Saltwater Pumps 550

/60II) b.

Steam Line Isolation

< 10 6.

Steam Flow in Two Steam Linas High Coincident with 5 team Line Pressure Low Safety Injection (ECCS)

-a.

i 25I4}/35(5) l 1)

Reactor Trip

<2 2)

Feedwater Isolation

'I 53fIf II) 3)

Phase "A" Isolation-I la I /2t l

4). Containment Yantilation Isolation 5)

Auxiliary Feedwater R.A. I)

< 60 6)

Component Cooling Water i 34

/44I3) 7)

Containment fan Cooler Units i 40

8). Auxiliary Saltwater Pumps i44

/54I3) b.

Steam Line Isolation i8 DIABLO CANYON - UNITS 1 & 2 3/4 3-29 Amendment Nos. 51 and 50

h N

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 7.

Containment Pressure-High-High a.

Containment Spray

< 48.5(6) b.

Phase "B" Isolation N.A.

c..

Steam Line Isolation

<7 8.'

Steam Generator Water Level-High-High

-a.

Turbine Trip

< 2.5

_ 66(2) b.

Feedwater Isolation-9.

Steam Generator Water Level j

_ Low

Low h

?'

a.

Motor-Driven Auxiliary Feedwater Pumps

< 60(3) b.

Turbine-Driven Auxiliary.

~

Feedwater Pump.

5 60

- 10. 'RCP Bus Undervoltage

. Turbine-Oriven Auxiliary Feedwater Pump 5 60 11.

Plant Vent. Noble Gas Activity-Higb(a).

Containment Ventilation-Isolation

< 11-12.

Containment Ventilation Exhaust Radiation-High (b)

Containment Ventilation Isolation

's 11

(a)The requirements for' Plant Vent Noble Gas Activity-High are not applicable fol. lowing installation of-RM-44A'and 448.

(b)The requirements for Containment Ventilation Exhaust Radiation-High are

, applicable following installation of RM-44A and 44B.

I DIABLO CANYON - UNITS 1 & 2 3/4 3-30 Amendment Nos.

70 & 89, 72 & 71 4

e 5

2 w

---ww_ew<

%r w-9

T TABLE 3.3-5 (Continued)

TABLE NOTATIONS (1) Diesel generator starting delay not included because offsite power available.

(2) Feedwater System overall response time shall include verification of each individual feedwater System valve closure time as shown below:

Closure Time (not including Valve instrumentation delays)

FCV-438

< 60 seconds 439 7 60 seconds 440 7 60 seconds 441 7 60 seconds 510 7 5 seconds 520 7 5 seconds 530 7 5 seconds 540 7 5 seconds 1510 7 5 seconds 1520 7 5 seconds 1530 7 5 seconds 1540

,7, 5 seconds (3)' Diesel generator starting and loading delays included.

(4) Diesel generatc, starting delay not included because offsite power is available.

Re.sponse time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps (where applicable).

Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

l (5) Diesel generator starting and sequence loading delays included.

0ffsite power is not available.

Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.

Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

I (6) The maximum response '.ime of 48.5 seconds is the time from when the con-tainment pressure exceeds the High-High Setpoint until the spray pump is started and the discharge valve travels to the fully-open position assuming off-site power is not available.

The time of 48.5 seconds includes the 28-second maximum delay related to ESF loading sequence.

Spray riser piping fill time is not included.

The 80-second maximum spray delay time does not include the time from LOCA start to "P" signal.

-(7) Diesel generator starting and sequence loading delays included.

Sequential transfer of charging pump-suction from the VCT to the RWST (RWST valves open, then.VCT valves close) is not included.

Response time

--limit includes opening of valves to establish SI flow path and attainment of discharge pressure for centrifugal charging pumps, SI, and RHR pumps

-(where applicable).

DIABLO CANYON - UNITS 1 & 2 3/4 3-31 Amendment Nos.

52 & EZ, 72 & 71

q) i L

REACTOR COOLANT SYSTEM j

.3/4.4.2 SAFETY VALVES SHUTDOWN

. LIMITING CON 04.'ON FOR OPERATION m

-3.'4.2.1 A minimum of one pressurizer Code safety valve shall be OPERABLE with a lift setting of 2485 psig i 1%.*

APPLICABILITY:. MODES 4-and 5.

TACTION:

With no: pressurizer Code safety valve OPERABLE, immediately suspend all

_. operations: involving positive reactivity changes and place a residual heat

. removal train into operation.

c-SURVEILLANCE REQUIREMENTS

['

4.4.2.1 No additional requirements other than those required by Specifica-s tion 4. 0.5.

-s W-

The lift setting pressure shall correspond to ambient conditions of the salve lat nominal:~perating. temperature and pressure.

u

'DIABLO CANYON 1-UNITS.1 & 2 3/4 4-7

~

4

.4,-

.-_,.....,y--

w w.

.~v.,--

.L,

, +, w @,r

,7w%,,-#,.,y,y.

,,-%.w w

rs.,m,,,

,e-

.,,,,,___,,,+,w,-,.

c,

' REACTOR COOLANT-SYSTEM OPERATING-LIMITING-CONDITION FOR OPERATION 3.4.2.2 All pressurizer Code safety valves shall be OPERABLE with a lift setting of 2485 psig t 1%.*

l b

APPLICABILITY:

MODES 1. 2 and 3.

ACTION:

o

//

a.

With one pressurizer Code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at ! east HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUT 00WN within the fo11owing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

The provisions of Specification 3.0.4 may be suspended for up to

.10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months per valve for entry into and during operations in MODE 3

-for the purpose of setting the pressurizer Code safety valves under ambient (hot)--conditions provided a preliminary cold setting was made prior:to heatup.

SURV'EILLANCE REQUIREMENTS 4;4.2.2-No additional requirements other than those required by Specifica-tion 4. 0. 5.=

L

The lift setting' pressure shall correspond to ambient conditions of the L

1 valve-at nominal, operating; temperature and pressure.

I l

- DIABLOLCANYON N UNITS 1 &~2 3/4.4-8 Amendment Nos.

49_& #8, 72 & 71

.- + -. -

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3/4.5 'ENERGENCY: CORE COOLING SYSTEMS L

3/4.5.'1 ACCUMULATORS

' LIMITING CONDIT10N FOR OPERATION 3.5.1 Each Reactor Coolant System accumulator ^ ?ll be OFERABLE with:

h; a.-

The isolation valve open and power removed.

- b.

'A. contained borated water volume of between 836 and 864 cubic feet of borated water,

.c.

A boron concentration of between 2200 and 2500 ppm, and i

.'d.

A-nitrogen cover pressure of between 595.5 and 647.5 psig.

l APPLICABILITY:

MODES 1, 2 and 3.*-

i

ACTION:

a.-

With'one accumulator inoperable, except as a result of a closed

isolation valve, restore the inoperable accumulator to OPERABLE status'within-.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 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 in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

-b.-

With-one accumulator inoperable due to the isolation valve being..

closed, either immediately open the isolation valve or be in HOT STANDBY-within 6: hours and in HOT SHUTDOWN within the following' 1

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

!SURVEILLANCEkiQUIREMENTS-

~

4.5.1.1'.Each accumulator shall be demonstrated OPERABLE:

a.

At-least once^per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1)-

Verifying the contained borated water volume.and nitrogen cover pressure in the tanks, 'and

2)l Verifyirg that..each. accumulator isolation valve is open.

Press'urizer. pressure abo' ve'.1000. psig.

p

.DIABLO CANYON - UNITS'1 & 2 3/4 5-1 Amendment Nos-Z4 & Z3,.72 & 71 h

}

]

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE' REQUIREMENTS (Continued)

-b.-

At least once per 31-days and within G hours after each solution volume increase o~.' greater than or rqual to '% of tank volume by verifying the boron concentration of the accumulator solution; and

-At least once per 31 days when the RCS pressure is above 1000 psig-c.

by verifying that power to the isolation valve operator is discon-ected by sealing the breaker in the open position.

4.5.1.2 Each accumulator pressure and water ievel channel shall bn demonstrated OPERABLE:

a.

- At least once per 31 days-by the performar.ce Of a CHANNEL FUNCTIONAL TEST, and b.

At least once per 18 months by the performance of a CHANNEL CALIBRATION.

L c-l DIABLO CANYON - UNITS 1 & 2 3/4 5-2

i

' EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

By a visual inspection which verifies that no loose debris (rags, c.

trash, clothing, etc.) is present in the containment which could be transported to the contair. ment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1)

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2)

Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

'd.

At least once per 18 months by a visual inspection of the containment sump and verifying that.the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.)

show-no evidence of structural distress or corrosion; At least once per 18 months by:

e.

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection actuation test signal.

2)

Verifying that each of the following pumps start automatically upon-receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b).

Safety Injection pump, and c)

Residual Heat Removal-pump.

f.

By verifying that-each of the following pumps develops the indicated diffsrential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrif ugal charging pump 12400 psid, 2)

Safety Injection pump 1 1455 psid, and 3)

Residual Heat Removal pump 1 165 psid.

DIABLO CANYON - UNITS 1 & 2 3/4 5-5

4 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g.

By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:

1)

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking opera-tion or maintenance on the valve when the ECCS subsystems are re-quired to be OPERABLE, and 2)

At least once per 18 months.

Charging Injection Safety Injection Throttle Valves Throttle Valves 881CA 8822A 8810B 8822B 8810C 8822C 8810D 88220 h.

By performing a flow balance test, during shutdown, following comple-tion.of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:

For Unit 1 Cycle 5 l

1)

For centrifugal charging pump lines, with a single pump running:

a)

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 346 gpm, and b)

The total pump flow rate is less than or equal to 550 gpm.

2)

For safety injection pump lines, with a single pump running:

a)

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 463 gpm, and b)

The total pump flow rate is less than or equal to 650 gpm.

For Unit 1 Cycle 6 and a'ter, and Unit 2 Cycle 5 and af ter:

1)

For centrifugal charging pumps, with a single pump running:

a)

The sum of injection line flow rates, excluding the highest flow rate, is greater than or equal to 299 gpm, and DIABLO CANYON - UNITS 1 & 2 3/4.5-6 Amendi,.ent Nos.

65 & 64,72 & 71

4.-

s c-

..?

U l: t_.

O

.(

4 THIS PAGE WAS INTENTIONALLY DELETED.

s.

t-w DIABLO CANYON - LINITS 1 & 2~

3/4 5-9 Amendment Nos. 52 & 51, 72 & 71

1 I

i I

I i

t THIS PAGE WAS INTENTIONALLY DELETED.

1 l

I i

DIABLO CANYON - UNITS 1 & 2 3/4 5-10 Amendment Nos. 52 & 51, 72 & 71

T A'%

iPLANT SYSTEMS

STEAM GENERATOR 10% ATMOSPHERIC DUMP VALVES LIMITING CONDITION-FOR OPERATION' 3;7.1.6 Fouristeam generator 10% atmospheric dump valves.(ADVs) with the associated block. valves lopen and associated remote manual controls, including uthe backup air bottles, shall-be OPF.RABLE.

APPLICABILITY:

MODES.1,J2, and 3.

. ACTION:

With one.less-thanithe required number of 10% ADVs OPERABLE,1 restore:

- a.

the inoperable: steam generator'10% ADV to OPERABLE status within 7 days; or be-irtat least HOT-STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT 5HUTDOWN within-the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

.With:twoolesssthanEthe required numbered of'10% ADVs OPERABLE, restore atileast one of the-inoperable steam' generator 10% ADVs to-

-0PERABLE-status'within_.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ;.or be in'at least HOT' STANDBY

-within the'next:6 hours and in HOT SHUTDOWN ~within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

LSURVEILLANCE REQUIREMENTS =

4.7.1.6 Eachtsteant generator 10% ADV, associated block: valve and associated

~

3 4 remote manual.'controlsfincluding the backup air bottles shall be demonstrated -

OPERABLE:

- a.'

Atfleast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that-the ~ backup air bottle -

for each steam generator 10% ADVshas'a pressure' greater than or zequal;to;260 psig,-Land

' b.-

/At. leas _t once'per 31 days by verifying:the the st'eam generator 10%

i s

1ADV block valves are/open, Land c.

!At least once per 18 months by verifying that all steam _ generator

-10% ADVs will-' operate using the remote manual controls and the

. backup air bottles.

/

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'DIABLO CANYON -! UNITS-1 & 2 3/4 7-9a Amendment Nos.

6# & 63 72 & 71 y

4 4

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e r-m e

g w-'

-9 p

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q-e:rwy

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=3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 -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 either:

A K,ff of 0.95 or less, which includes a 1% Ak/k conservative a.

allowance for uncertainties, or b.

A boron concentration of greater than or equal to 2000 ppm, which includes a 50 ppm conservative allowance for uncertainties.

APPLICABILITY:

MODE 6*.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or its equivalent until K,ff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2,000 ppm, whichever is the more restrictive.

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

a.

Removing or unbolting the reactor vessel head, and b.

-Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor 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 each 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 vessel head closure bolts less than fully tensioned or with the head removed.

I DIABLO CANYON - UNITS 1 & 2 3/4 9-1 Amendment Nos.

53 & 52, 72 & 71 I

m_

7 3

-REFUELING OPERATIONS?

3/4l 9. 2 - ' INSTRUMENTATION

1

-LIMITING ~. CONDITION F'OR"0PERATION-3.9.21 As a minimum,.two Source Range Neutron Flux Mo'nitors shall--be OPERABLE each with continuous visual indication in the control room and.one with audible p

~

l indication in containment and-the control room.

APPLICABILITY:

MODE : 6..

ACTION:

With'onelof-the above required monitors inoperable or not operating, a.

'innediately_ suspe'nd 'all operations involving CORE ALTERATIONS or positive: reactivity changes except for latching the control rod drive mechanism shaft to_the rod cluster' control assemblies'and friction testing of individual _ control rods.

b.

With both of the above required monitors 1 inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once-per 12: hours.

p 1 SURVEILLANCE REQUIREMENTS

'4.9/2 Each:So;urce Range. Neutron Flux Monitor'shall be demonstrated OPERABLE by. performance ofi 7

- a'.

lA? CHANNEL CHECK at least'once-per 12-hours..

. An ANALOG CHANNEL;0PERATIONAL TEST within.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the' initial

b.

start offCORE ALTERATIONS,_and

~

-ch ;An: ANALOG CHANNEL OPERATIONAL TEST at least once per'7 days.

x~

4

.. I r;

~

i A

j_.r H

DIABLO CANYON - UNITS 1 & 2-3/4 9-2 AMENDMENT NOS. 46 AND 45

Os 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 measurement of control rod worth and shutdown margin provided reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

APPLICABILITY:

MODE 2.

ACTION:

a.

With any full-length control rod not fully inserted and with less than the above reactivity equivalent available for the trip insertion immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored, b.

With all full-length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppro boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.-

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full-length control rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full-length control rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% 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

-5pecification 3.1.1.1.

t DIABLO CANYON - UNITS 1 & 2 3/4 10-1 Amendment Nos.

53 & 52, 72 & 71

a

[

e-

...g SPECIAL TEST EXCEPTIONS-3/4 10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS i

. fLIMITING-CONDITION FOR OPERATION E

3.L10. 2 The group height, insertion and power distribution _ limits of Specifica-

.tions23.1.3.1, 3.1.3.5,13.1.3.6,~3.2.1,.and 3.2.4 may be suspended during the performance:of_ PHYSICS-TESTS provided:

'a.

The THERMAL POWER is maintained less than or equal-to_85% of'RATEu THERMAL _ POWER, and b.

The limits of Specifications 3.2.2 and 3.2.3 are n.aintained and deter-

[

4 mined at the-frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: LMODE 1.-

LACTION:--

With any ofsthe limits of Specifications 3.2.2 or 3.2.3 being exceeded while l

Lthe requirements;of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1 and 3.2.4

-are suspended, either:

Ta.

Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or

[

- b'.

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

' SURVEILLANCE-REQUIREMENTS 4.10.2.1 The THERMAL-POWER shall be determined to be less than or equal to 85%

L tof7RATEDiTHERMAL= POWER:at least once per hour during_ PHYSICS TESTS.

4.10.2.2 L The requirements = of. the below: listed specifications shall be performed at least.once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months _during. PHYSICS _ TESTS:

. a.-

1 Specifications 4.2.2.2 and 4.2.2.3, and l

'b.

Specification 4.2.3.2.

H, li DIABLO CANYON-- UNITS 1 & 2 3/4 10-2 Amendment Nos. af &' 36,'71 & 70

,.m..

+<4 e-

y 4l

O 3/4.1 ' REACTIVITY ' CONTROL : SYSTEMS ff[

~ BASES 3/4.1.1 - BORAT!0,N CONT 40L 1

- 3/4.1.1.1 and 3/4.1.1.2 '$ NUT 00WN MRGlN

'T

_ A sufficient NAFTDOWN MARGIN enspres that:

(1) the-reactor can be made -

-suberitical from all operating conditions, (2) the reactivity transients asso-cisted with postulated accident conditions are' controllable within acceptable limits, and (3) tho' eenctor will be maintained sufficient)y suberitical to-proclede inadvertent criticality in the shutdown conditten.

SHUTDOWN MARGIN requirements vary throughoJt core life as a " unction of fuel depletion RC5 boron concentration, and RCS T,y. :The most restrictive

. condition' occurs et-EOL ; with T,yg at no load operat<ng temperature, and is L

essociated with' a' postulated steam line br4ak accident 'and resulting uncontrolled

~

'RCS cooldown._ Init h analysis of this' accident,-a minimum GNUTDOWN MARGIR of-1.65 t

+

1 Ak/k is initially required to control the reactivity transient.

Accordingly.

the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FsAR safety analysis assumptions. With T,,,

less than 200'F.

the reactivity transients resulting from a postulated steam line break cod $own are minimal and a'1% Ak/k shutdown margin provides adequate protection.

=

- 3/4.1.1. 3 MODERATOR TEMPERATURE C0 EFFICIENT

' [<

The limitations _ on moderator temperature coefficient (MTC) are provided to f

ensure that the value of this. coefficient romains within the limiting conditions

-. assumed in the FSAR accident and transient' analysis. -

The EC values of. this' specification-are applicable to a specific set of plant: conditions; = accordingly, verification of. MTC values at conditions other -

than those explicitly ~ stated will require extrapolation to _those conditions in Lorder to permit an accurate comparison.-

The most negative MC value equivalent to the most-positive moderator density: coefficient'(MDC).was1obtained by incrementally correcting the M C

.used in the'FsAR analyses to nominal operating conditions.' These corrections involved subtracting the incremental change in.the MC associated with.a core -

-1

~

condition of a111 rods 11nserted (most positive WC) to an all rods withdrawn

. condition, and a' conversion for the rate of change of moderator density with

. temperature at RATED THERMAL' POWER conditions.

This value of the EC was then transformed'into tne limiting MTC value _-3.9 x 10 8 Ak/k/*F. The NTC.

b

- value of -3.0 x 10 4 -Ak/k/*F represents a conservative:value (with corrections

for burnup and soluble boron) ~at a core condition of 300 ppe equilibrium boron

(

concentration and is"obtained by making these corrections to the limiting MTC i;

value of -3;9 x110-4 Ak/k/*F.

p

'The Surveillance Requirenents for measurement of the MTC at the beginning-n Land near the and of. each fuel cycle are adequate to-confirs that the MTC ressins R

within its-limits since this coefficient' changes slowly due principally to the:

L

reduction in RCS boron concentration associated with fuel.burnap.

In addition, J,

- verification during startup testing 'at beginning 'of life hot zero power for each i4 1 cycle validates _ that the MTC parameters are within the limits specified for all

. i1

_other_ power levels.

DIABLO CANYON -: UNITS'1 & 2 B 3/4 1-1 Amendment Nos.10, 8 Ly

,4

_..-_.__..a.,_._._.._._._~,..._.__,_____

~

e-

'REAC11VITY-CONTROL-SYSTEMS BASES 3/4.E l 4~ MINIMUM-TEMPERATURE FOR CRITICALITY.

This specification ensures that the reactor will-not be made critical with-the: Reactor Coolant System average temperature less than 541*F.

This

-c flimitation is required to ensure:

(1) the moderator temperature coefficient is

within'=itt1unalyzed temperature range,,(2) the protective instrumentation is within its. normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with aL steam bubble,.and (4) the reactor vessel is above its minimum RTNDT'. temperature.

3/4.1.2--BORATION' SYSTEMS

- he boron injection system. ensures that negative reactivity control is T

available:during each mode of facility operation. -The components required to perform this function include:

(1) boratea water sources, (2) charging pumps,

-(3) separate flow'. paths, (4) boric acid transfer' pumps, and (5) an emergency power srpply'.from OPERABLE' diesel generators.

=With the RCS? average temperature abov'e'200 F, a minimum of two boron

? injection flow peths?are: required to ensure single functional capability in the event:aa assumed-failure renders onevof the flow paths: inoperable.

The boration capability of-either flow path is sufficient-to providt a-SHUTDOWN iMARGIN from expected operating-conditions of L6% ak/k after xenon decay and cooldown to 200 F.

The maximum expected boration capability requirement occurs at

BOL when1 borating;from hot:zero power to COLD SHUTDOWN and requires 14,042 Jgallons_of-7,000 ppm: borated water from the boric acid storage tanks or 65,784

. gallons of 2300 ppm borated water from the refueling water storage tank.

-With;the RCS-temperature below 200 F, one Boron Injection System is acceptable without single: failure consideration;on the basis ofithe stable

. reactivity-condition of the reactor and the additional restrictions prohibiting 1 CORE ALTERATIONS and positive reactivity _ change in the event _the single.injec-tion: system becomes inoperable.

,The'. boron. capability required below 200 F is sufficient to provide a

SHUTDOWN MARGINLof: 1% ak/k after xenon: decay-and cooldown from 200'F to 140 F.

This: condition requires either 2,499 gallons of 7,000' ppm borated water from the boric-! acid storage tanks or 17,865 gallons of_2300 ppm borated water from

_the" refueling-water storage tank.

The limits.on~ contained' water volume and boron concentration of the RWST also ensure a pH value of between 8.0 and 9.5 for the solution recirculated' Ewithin containment after a LOCA.

This pH band minimizes the evolution of iodine:and minimizes the effect of' chloride and caustic stress' corrosion on mechanical. systems.and. components.

DIABLO CANYON - UNITS 1 & 2 B 3/4 1-2 Amendment Nos.

53 & 52, 72 & 71

c

0, EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS-(Continued)

_ _ The maximum flow Surveillance Requirement ensures that the minimum injection line resistance assumptions are met.

These assumptions are used to calculate maximum flows to the RCS for safety analyses which are limited by maximum ECCS flow to the RCS.

The Surveillance. Requirement for the maximum difference between the minimum and maximum individual injection line flows ensures that the minimum individual-injection'line resistance assumed for the spilling line following a LOCA is met.

The maximum total: pump flow Surveillance Requirements ensure the pump runout limits of 560 gpm for the centrifugal charging pumps and 675 gpm for the safety injection pumps are met.

The' safety analyses.are performed assuming the miniflow recirculation lines for the ECCS subsystems associated with the centrifugal charging and safety injection pumps are open.

The flow balancing test is, therefore, performed with these miniflow recirculation lines open.

Some of the flow from the centrifugal charging pumps will go to the RCP seals'during ECCS operation.

Therefore, the flow balance test is performed with a simulated flow from the centrifugal-charging pumps to the RCP seals.

.The simulated flow rate-is consistent with the actual RCP seal resistance and the' resistance of the RCP seals assumed'in the calculation of ECCS flows for the safety analyses, t

DIABLO CANYON - UNITS 1 & 2 B 3/4 5-2a Amendment Nos.

65 & gg, 72 & 71 E

e-

EMERGENCY CORE COOLING SYSTEMS BASES

~ 3/4.5.5 REFUELINIl WATER STORAGE TANK' -

_- The OPERABILITY of-the Refueling Water Storage Tenk (RWST) as part'of -the ECCS ensures that a-sufficient supply of borated water is available for injec--

tion by the ECCS in:the-event of either a LOCA or a steamline break.

The

_ limits on RWST minimum _ volume and boron concentration ensure that:

(1) sufficient water is-available within containment to permit recirculation' cooling flow to the core; (2) the reactor.will remain suberitical in the cold condition-(68-to 212' degrees-F) following-a small break LOCA assuming complete-mixing ~of;the RWST, RCS, spray additive tank, containment _ spray system piping

-and ECCS water volumes with all control' rods inserted except the most reactive control rod assembly._(ARI-1); (3) the reactor will-remain subcritical in the cold condition following a large break LOCA (break-flow area greater.than 2

23 ft ) assuming complete mixing of the RWST, RCS, ECCS water and other sources

-of water that may eventually reside in the sump post-LOCA with all control rods assumed to be out (AR0); and (4) long-term subcriticality following a steamline break assuming ARI-1 and preclude fuel failure.

The maximum allowable value for the RWST boron concentration-forms the basis for t.istermining the time (post-LOCA) at which operator action is -

required to switch over the ECCS to hot leg recirculation in order to avoid precipitation of-the soluble boron.

The contained water volume limit includes an allowance for water not usable because of: tank discharge line' location or other physical characteristics.

DIABLO CANYON'- UNITS 1 & 2 B 3/4 5-3 Amendment Nos.

14 and 13

-

ML20099F357

Text

Attachment:

.

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