Text

Amends 60 & 59 to Licenses DPR-80 & DPR-82,respectively, Revising TS to Implement power-dependent RCS Flow Rate Limits & Deleting Selected Unit & Cycle Dependent Nonapplicable Parameters
	ML20070K948
Person / Time
Site:	Diablo Canyon
Issue date:	03/12/1991
From:	Dyer J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20070K950	List: ML20070K948; ML20070K967;
References
	NUDOCS 9103190219
	Download: ML20070K948 (26)
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f PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-80

't 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee)datedDecember 21, 1990, complies with the standards 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 regulations of the Commission; C.

There is reasonable assurance (1) 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 common 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 paragraph 2.C.(2)-of Facility Operating License No. DPR-80 is hereby amended to read as follows:

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P (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised ti rough Amendment No. 60 _, are hereby incorporated in the license.

e 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.

l 3.

This license amendment becomes effective at the date of its issuance.

FOR THE' NUCLEAR REGULATORY COMMISS:0N 4NA f EV I

James E. hyer, Director i

Project Directorate-Y Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation I

Attachment:

Changes to the Technical Specifications Date of Issuance: March 12,1991 1

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PACITIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO. 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59-License No. DPR-82 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated December 21, 1990, complies with the standards 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 f acility will operate in conformity with the application, the-provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance (1) 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 comon 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 paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby.

amended to read as follows:

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l 4 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised thfough Amendment No. 59

, 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 amcr.dment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION su f.

w James E. Dyer, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor-Regulation

Attachment:

i Charges tc the Technical-Specifisations Date of Issuance: March 12, 1991 i

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ATTACHMENT TO LICENSE AMENDMENT NOS. 60 AND 59 FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82 DOCKET NOS. 50-275-AND 50-323 Revise Appendix A Technica! 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 PAGE INSERT PAGE iii iii V

V 2-1 2-1 2-2 2-2 2-2a 2-2a B 2-1 B 2-1 B 2-la B 2-la B 2-lb B 2-ib 3/4 2-13 3/4 2-13 3/.

14 3/4 2 3/4 2-15 3/4 2-15 J/4 2-16 3/4 2-16 3/4 2-17 3/4 2-17 B 3/4 2-4 B 3/4 2-4 B 3/4 2-5 B 3/4 2-5 I

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4 INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION Paa' 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE.....................................................

2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE..................................

2-1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT...................................

2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP01NTS....................

2-3 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS......... 2-4 BASES SECTION PaSe 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE.....................................................

B 2-1

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2.1.2 REACTOR COOLANT SYSTEM PRESSURE..................................

B 2-2 2.2 LIMITING SAFETY-SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0INTS.....................

B 2-3 4

l DIABLO CANYON - UNITS 1 & 2 iii Aaendment Nos. 60 and 59

')

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION

,P_a5L' 3/4.0 APPLICABILITY..............................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T,yg greaterthan250*F...............

3/4 1-1 Shutdown Margin - T,yg less than or equal to 200*F......

3/4 1-3 Moderator Temperature Coefficient.......................

3/4 1-4 Minimum Temperature for Critica11ty.....................

3/4 1-6 3/4.1.2 BORATION SYSTEMS Flow Path - Shutdown....................................

3/4 1-7 Flow Paths - Operating..................................

3/4 1-8 Charging Pump - Shutdown................................

3/4 1-10 Charging Pumps - Operating..............................

3/4 1-11 Borated Water Source - Shutdown.........................

3/4 1-12 Borated Water Sources - Operating.......................

3/4 1-13 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height............................................

3/4 1-15 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R00..................

3/4 1-17 Position Indication Systems - Operating.................

3/4 1-18 Position Indication System - Shutdown...................

3/4 1-19 dod Drop Time...........................................

3/4 1-20 Shutdown Rod Insertion Limit............................

3/4 1-21 Control Rod Insertion L1mits............................

3/4 1-22 i

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D8ABLO CANYON - UNITS 1 & 2 iv

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION P3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................

3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-F (2).....................

3/4 2-5 q

FIGURE 3.2-2 K(Z) - NORMALIZED F HEIGHT............,0.(2) AS A FUNCTION OF CORE 3/4 2-6 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.....................................

3/4 2-13 FIGURE 3.2-3a RCS TOTAL FLOWRATE VERSUS R (UNIT 1)..............

-3/4 2-14 FIGURE 3.2-3b RCS TOTAL FLOWRATE VERSUS R (UNIT 2)..............

3/4 2-15 3/4.2.4 QUADRANT POWER TILT RATI0.............................,

3/4 2-18 3/4.2.5 DNB PARAMETERS.........................................-

3/4 2-21 TABLE 3.2-1 DNB PARAMETERS..................................

3/4 2-22 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.................... 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM' INSTRUMENTATION................. 3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES..

3/4 3-8 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................................

3/4 3-10 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................

3/4'3-14 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.....................................

3/4 3-15 DIABLO CANYON - UNITS 1 & 2 v

Amendment Nos.

60 and 59 l

i INDEX I

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMERIS

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SECTION ElR1 3/4.3 INSTRUMENTATION (continued)

(ABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0!NTS..........................

3/4 3-23 TA?4E 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES............

3/4 3-28 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-32 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations................

3/4 3-36 TABLE 3.3-6 OPERATIONS........................ TION FOR PLANT RADIATION MONITORING IhSTRUMENTA 3/4 3-37 TABLE 4. 3-3 RA0!ATION MONITORING INSTRUMENTATION FOR PLANT OPE RATIONS SURVEI LLANCE REQUIREMENTS.....................

3/4 3-39 Movable Incore Detectors.................................

3/4 3-40 Seismic Instrumentation..................................

1 3/4 3 41 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION....................

3/4 3-42 TABLE 4.3-4 SEISMIC HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3-43 Meteorological Instrumentation...........................

3/4 3 44 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-45 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTAT REQUIREMENTS.............................. ION SURVEILLANCE 3/4 3-46 Remote Shutdown Instrumentation..........................

3/4 3-47 TABLE 3.3-9 REMOTE SHUTOOWN MONITORING INSTRUMENTATION............

3/4 3-48 TABLE 4.3-6 REMOTE SHUT 00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3-49 Accident Monitoring Instrumentation......................

3/4 3-50 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-52 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3-53 DIABLO CANYON - UNITS 1 & 2 vi

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2. 0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, operating icop coolant temperature (T,yg) pressurizer pressure, and the hig shall not exceed the limits shown in Figure 2.1-1.

l APPLICABILITY:

MODFS 1 and 2.

ACTION:

Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and comply with the require-ments of Specification 6.7.

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5.

ACTION:

MODES I and 2:

Whenever the Reactor Coolant System pressure has exceeoed 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and comply with the requirements of Specification 6.7.

MODES 3, 1 and 5:

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes, and comply with the requirements of Specification 6.7.

DIABLO CANYON - UNITS 1 & 2 2-1 Amendment Nos. 60 and 59

i UNITS 1 & 2 660 0

670 UNACCEPTABLE o

660 OPERATION N

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s 2000 PSIA T

W6 690 ACCEPTABLE

OPERATION 600 I

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0 20 40 60 80

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\\20 PERCENT OF RATED THERMAL POW 2R (RTP)

WHEN OPERATING IN THE REDUCEO RTP REGION OF T SPECIFICATION 3/4.2.3 (FIGURE 3.2-3 a FOR UNIT 1 AND FIGURE 3.2-3b FOR UNIT 2) THE RESTRICTED POWER LEVEL MUST BE CONSIDERED 100% RTP FOR TM!S FIGURE.

FIGURE 2.1 1 REACTOR CORE SAFETY LIMIT I

DIABLO CANYON - UNITS 1 & 2 2-2 Amendment Nos. 60 and 59

t THIS PAGE WAS INTENTIONALLY DELETED.

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l DIABLO CANYON - UNITS 1 & 2 2-2a Amendment Nos. 60 and 59

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4 2.1 SAFETY LIMITS BASES 2.1.1 REACTORCOM The restrictions of this $afety Limit prevent overheating of the fuel and possible cladding perforation which would result in the release of fission products to the reactor coolant.

Overheating of the fuel cladding is prevented by restricting fuel operation to within a nucleate boiling regime where the heat transfer coefficient is large and the cladding surface temperature is slightly above the coolant saturation temperature, g

The DNB design basis is as follows:

there must be at least a 95 percent probability that the minimum DNBR of the limiting rod during steady-state opera-tion, normal operational transients, and anticipated transients is greater than.

or equal to the DNBR limit of the DNB correlation being used (the WRB 1 for LOPAR fuel and the WRB-2 for VANTAGE 5 fuel in this application).

The correlation DNBR limit is established based on the entira applicable experimental data set such that there is a 95 percent probability sith a 95 percent confidence level that DNB will not occur when the minimum DNBR is at or greater than the DNBR limit (1.17 for both the WRB 1 and WRB-2 correlations).

In meeting this design basis, uncertainties in plant operating parameters, nuclear and thermal parameters, and fuel fabrication parameters are considered statistically such that there is at least a 95 percent probability with a 95 confidence level that the minimum DNBR for the limiting rod is greater than or equal to the DNBR limit.

The uncertainties in the above plant parameters are used to determine the plant DNBR uncertainty.

This DNBR uncertainty, combined with the correlation DNBR limit, establishes a design DNBR value which must be met in plant safety analyses using values of input parameters without uncertain-ties.

For Diablo Canyon Units, the design DNBP values are 1.33 and 1.37 for thimble and typical cells, respectively, for thPAR fuel, and 1.30 for thimble and 1,32 for typical cells for the VANTAGE 5 fuel.

In addition, margin has been i

maintained in both designs by meeting safety analysis DNBR limits of 1.44 for thimble and 1.4B for typical cells for LOPAR fuel, and 1.68 and 1.71 for thimble and typical cells, respectively, for VANTAGE 5 fuel in performing safety analyses.

The curves in Figure 2.1-1 show the loci of points of THERMAL POWER, Reactor l

Coolant System pressure and average temperature below which the calculated DNBR is no less than the safety analysis DNBR limits, or the average enthalpy at the vessel exit is less than the enthalpy of saturated liquid.

The curves are based on an enthalpy hot channel factor, Fh of 1.56 for LOPAR and 1.59 for VANTAGE 5 fuel, and a reference cosit.e with a peak of 1,55 for axial power shav v allowance is included for an increase in Ffg at reduced l

power based on w expressions:

DIABLO CANYON - UNITS 1 & 2 B 2 Amendment Nos. 60 and 59

2.1 $AFETV LIMITS I

BASES (Continued) i Ffg=1.56[1+0.3(1-P)) for LOPAR fuel i

Fh=1.59[1+0.3(1-P)] for VANTAGE 5 fuel where P is the fraction of RATED THERMAL POWER The 4% measurement uncertainty associated with Fh is accounted for in the DNBR design limit.

These limiting heat flux conditions are higher than those calcutated for the range of all control reds fully withdrawn to the maximum allowable control rod insertion assuming the axial power imbalance is within the limits of the ft (AI) function of the Overtemperature trip.

When the axial power imbalance is not within the tolerance, the axial power imbalance effect on the Over-temperature AT trip will reduce the Setpoints to provide protection consistent with core safety Limits.

L 1

-1 DIABLO CANYON.- UNITS 1 & 2 B 2-la

-Amendment Nos. 60 and 59 l

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l DIABLO CANYON - UNITS 1 & 2 8 2-lb Amendment Nos. 60 and 59 i

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SAFETY LIMITS BASES 3

2.1.2 REACTOR COOLANT SYSTEM PRESSURE l'

The restriction of this Safety Limit protects the integrity of the Reactor Coolant System from overpressurization and thereby prevents the release of radionuclides contained in the reactor coolant from reaching the containment atmosphere.

The reactor vessel and pressurizer are designed to Section III of the ASME Boiler and Pressure Vessel Code which permits a maximum transient pressure of 110% (2735 psig) of design pressure.

The Reactor Coolant System piping and fit-i tings are designed to ANSI B 31.1, which permits a maximum transient pressure of 120% (2985 psig) of component design pressure.

The Safety Limit of 2735 psig is therefore consistent with the design criteria and associated Code requirements.

The entire Reactor toolant System is hydrotested at 3107 psig, 125% of design pressure, to demonstrate integrity prior to initial operation.

l DIABLO CANYON - UNITS 1 & 2 8 2.-

POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

_ LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R shall be maintained within the region of allowable operation shown on Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2 for four loop operation.

Where:

y FAH for LOPAR fuel l

R = 1. 56 [1. 0 + 0. 3 (1. 0 -P)]

a.

N FaH for VANTAGE 5 fuel R = 1.59 [1.0 + 0.3 (1.0 -P)]

THERMAL POWER, and b'

P - RATED THERMAL POWER Ng=MeasuredvaluesofFfg obtained by using the movable incore c.

F detectors to obtain a power distribution map.

The measured valuesofFfH shall be used to calculate R since Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2 include measurement unceptainties of 2.4% for flow and 4% for incore measurement of FAH' APPLICABILITY:

MODE 1.

l ACTION:

With the combination of RCS total flow rate and R outside tne region of accept-able operation shown on Figure 3.2-3a for Unit 1 and Figura 3.2-3b for Unit 2:

l a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

l l

1.

Restore the combination of RCS total fir.w rate and R to within i

the above limits, or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

DIABLO CANYON - UNITS 1 & 2 3/4 2-13 Amendment Nos. 60 and 59 l

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OPERATION REGION 38 -

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UNACCEPTABLE a

OPERATON

.T 37 REGON b

B 36 -

.1 Mot RTP g

(1.0,36.9)

N (1.0,36.6) e (1.0,36.2) k 3

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.1 945 RTP (1.0,34.8)

(1.0,34.6)

.1 90% RTP 34 (1.0,34.1)

WEASUREENT UNCERTANTIES OF 2.4 THERWAL DE80N FLOW FOR FLOW AND M FOR NCORE WASUREWENT OF Ffg ARE NCLUDED IN THS FOURE.

l 33 O.86 0.90 0.96 1.00 1,06 1.10 R. F[g /166(10+0.3(10-P))

R. F[g/ t69(10+0.3(10-P))

LOPAR FUEL WNTAGE 6 FUEL

WHEN OPERATING IN THE RESTRICTED POWER REGION, THE RESTRICTED POWER LEVEL SHALL BE CONSIDERED 00% RTP FOR FIGURE 2.11 FIGURE 3.2-3a RCS TOTAL FLOWRATE VERSUS R(UNIT 1) l DIABLO CANYON - UNITS 1 & 2 3/4 2-14 Amendment Nos.60 and 59

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UNIT 2 ACCEPTABLE

OP E 8L ATION ME GION 36 -

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UNACCEPTABLE OPERATK)N s

I 37 -

REGION 120% RTP (1.0,~36.3) g s

36 -

1 98% MTP (1.0,36.9)

N 196% RTP

.5 (1.0,36.6)

I 94% RTP e

(1.0,36.2)

N 1 92% RTP

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(1.0,S4.8) 190% RTP (1.0,34.4) 34 -

WE ASUREWENT UNCERTANTIES OF 2.4 THERWAL DESIGN FLOW FOR FLOW AND M FOR NCORE hEA.GUREWENT OF Ffg ARE NCLUDED IN TMS FKnURE.

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i 33 0.86 0.90 0.96 1.00 1.06 1.10 R Ffg /166(t0+0.3(10-P))

R. F N Ag /169(10 +0.3(10-P))

LOPAR FUEL VANTAGE 6 FUEL

WHEN OPERATING IN THE RESTRICTED POWER REGION, THE RESTRICTED POWER LEVEL 8 HALL BE CONSIDE. RED 100% RTP FOR FIGURE 2.v1 i

i FIGURE 3.2-3b RCSTOTALFLOWRATEVERSUSR(UNIT 2)

DIABLO CANYON - UNITS 1 & 2 3/4 2-15

/cendment Nos. 60 and 59 L

i TNIS PAGE WAS INTENTIONALLY DELETED l

l DIABLO CANYON - UNITS 1 & 2 3/4 2-16 Amendment Nos. 60 and 59 l

[

l p0WER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION

)

ACTION (Continued) b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that the combination of R and RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , Identify and correct the cause of the out of-limit condition prior c.

to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2 and/or b.,

above; subsequent POWER OPERATION may proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comparison, to be within the region of acceptable operation shown on Figure 3.2-3a for Unit I and Figure 3.2-3b for l

Unit 2 prior to exceeding the following THERMAL POWER levels:

1.

A nominal 50% of RATED THERMAL POWER, t-2.

A nominal 75% of RATED THERMAL POWER, and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The prov41ons of Specification 4.0.4 are not applicable.

4.2.3.2 The combination of indicated RCS total flow rate and R shall be deter-mined to be within the region of acceptable operation of Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2:

Prior to operation above 75% of RATED THERMAL POWER after each fuel a.

loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Figure 3.2-3a for Unit 1 and Figure 3.2-3b for Unit 2 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the value of R, obtained per-Specification 4.2.3.2, is assumed to exist.

-4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

4.2.3.5 The RCS total flow rate shall be determined by measurement at least once per 18 months.

DIABLO CANYON - UNITS 1 & 2 3/4 2-17 Amendment Nos.

60 and 59

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4 POWER DISTRIBUTION LIMITS 3/4.2.4 OUADRANT POWER TILT RATIO 1

l i

LIMITING CONDITION FOR OPERATION s

3.2.4 THE QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY:

MODE I ABOVE 50% OF RATED THERMAL POWER *.

ACTION:

With the QUADRANT POWER TILT RATIO de'termined to exceed 1.02 but s.

less than or equal to 1.09:

i 1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:

i a)

The QUADRANT $0WER TILT RATIO is reduced to within its limit, or i

b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

I 2.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1 a) l Reduce the QUADRANT POWER TILT RATIO to within its limit, or b)

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER i

for each 1% of indicated QUADRANT POWER TILT RATIO in excess of I and similarly redur.e the Power Range Neutron l

Flux High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I 3.

Verify that the-QUADRANT POWER TILT RATIO is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 50% of RA1ED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER

{

within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and 4.

Identify and correct the cause of the out-of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION l

above 50% of RATED THERMAL POWEP may proceed provided that the.

i QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or unii1 verified acceptable at 95%

or greater RATED THERMAL POWER.

1 b.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of-either a shutdown or control rod:

I 1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour i

until eithea aSee Special Test Exceptions Specification 3.10.2 A

DIABLO CANYON - UNITS 1 & 2 3/4 2-18 Amendment Nos. 37 and 36 i

fifective at end of Unit 1 Cycle 3 gay 1013B9-4

I t

i THIS PAGE INTENTIONALLY LEFT BLANK 4

DIABLO CANYON - UNITS 1 & 2 B 3/4 2-3 Amendment Nos.12and 10

i POWER DISTRIBUTION LIMITS BASES HEAT FLL'X HOT CHANNEL FACTOR, and RC3 FLOWRATE AND NUCLEAR ENTHALPY RISE HOT

_CHAhNEL FACTOR (Continued)

Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to ensure that the limits are maintained provided:

i 1.

Control rods in a single group move together with no individual rod insertion differing by more than 1 12 steps, indicated, from the group demand position.

l 2.

Control rod groups are sequenced with overlapping groups as described i

in Specification 3.1.3.6, 3.

The control rod insertion limits of Specifications 3.1.3.5 and

^

3.1.3.6 are maintained, and 4.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

Ffg will be maintained within its limits provided Conditions 1. through 4., above, are maintained.

The relaxation of F as a function of THERMAL POWER H

allows changes in the radial power shTpe for all permissible rod insertion limits.

R, as calculated per Specific 6 tion 't.2.3 and used in Figure 3.2-3a and figure 3.2-3b accounts for F 1ess than of equal to 1.56 for LOPAR fuel and q

1.59 for VANTAGE 5 fuel. gThese values are the values used in the various accident analyses where F influences parameters other than DNBR, e.g., peak 3g clad temperature, and thus are the maximum "as measured' values allowed.

Margin between the safety analysis limit DNBRs (1.44 and 1.48 for the i

LOPAR fuel thimble and typical cells, respectively, and 1,68 and 1.71 for the VANTAGE 5 thimble and typical cells) and the design limit DNBRs (1.33 and 1.37 for the LOPAR fuel thimble and typical cells and 1.30 and 1.32 for the VANTAGE 5 fuel thimble and typical cells, respectively) is maintained.

A fraction of l

t this margin is utilized to accommodate the transition core DNBR penalty of maximum 12.5 percent and thr appropriate fuel rod bow DNBR penalty (less than 1.5 percent for both fuel types per WCAP 8691, Revision 1).

The rest of the-l margin between design and safety analysis DNBR limits can be used for plant design flexibility.

l l

DIABLO CANYON - UNITS 1 & 2 0 3/4 2-4 Amendment Nos. 60 and 59

}

P0tffR DISTRIBUT20N LIMITS BASES HEAT FlVX HOT CHANNEL FACTOR. and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) 1 When an Fg easurement is taken, an allowance for both experimental error m

and manufacturing tolerance must be made.

An allowance of 5% is appropriate for a full core map taken with the incore detector flux mapping system and a 3% allowance is appropriate for manufacturing tolerance.

WhenRCSflowrateandFfg are measured, no additional allowances are necessary prior to comparison with the limits of Figures ?.2-3s and b.

A measurement error of 2.4 percent for RCS flow rate has been allowed for in the determination of the design DNBR values.

A measurement error of 4 per-cent for F has been applied to the DNBR limit.

As itidicated in Figure 3.2-3a H

for Unit 1 and Figure 3.2-3b for Unit 2, RCS flow rate and power may be " traded off" against one another (i.e., a low measured RCS flow rate is acceptable if percent RTP is reduced) to ensure the DNBR will not be below the design DNBR value.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation which could itad to operation outside the acceptable i

region of operation shown on F Qures 3.2-3a and b.

l The hot channel factor F (:) is measured periodically and increased by a cycle and height dependent power factor appropriate to RA00 operation, W(z), to provide assurance that the limit on the hot channel factor F (z) is met.

W(z) q accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.

The W(z) function for normal operation is specified in the CORE OPERATING LIMITS REPORT per Specification 6.9.1.8.

3/4.2.4 QUADRANT POWER TILT RATIO 1he QUADRANT POWER TILT RATIO limit assures that the radial power distri-bution satisfies the design values used in the power capability analysis.

7 Radial power distribution measurements are made during startup testing and periodically during power operation.

The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power tilts.

The limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt, i

DIABLO CANYON - UNITS 1 & 2 B 3/4 2-5 Amendment Nos. 60 and 59

,_._,__..m.___,_.__._,___

p.0VER DISTRIBUTION LIMITS BASES QUADRANT POWER TILT RATIO (Continued)

The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned rod.

In the event such action does not correct the tilt, the margin for uncertainty on F i

q s reinstated by reducing the power by 3% for each percent of tilt in excess of 1.

3/4.2.$ DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in

, the transient and safety analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain the DNBR limits throughout each analyzed transient.

l The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

1 DIABLO CANYON - UNITS 1 & 2 B 3/4 2-6 Amendment Nos.37and 36-Effective at end of Unit 1 Cycle 3 WAY 1013%

ML20070K948

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