ML20028G812

Core Operating Limits Rept, Cycle 8.

ML20028G812
Person / Time
Site:	Pilgrim
Issue date:	08/20/1990
From:	Highfill K BOSTON EDISON CO.
To:
Shared Package
ML20028G806	List: ML20028G805 ML20028G807 ML20028G812
References
NUDOCS 9009050029
Download: ML20028G812 (19)

Text

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Attachment E to BECo 90-101 y

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PILGRIM NUCLEAR POWER STATION' y ,

CORE OPERATING LIMITS REPORT j O CYCLE 8 J i

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n Approved s 7d7/9o Nucl/frAnalysis'DivisionManager' Date Approved W4A*b /~ NF W1l10-Nuclear Engineerifig Department Manager Date i

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/d 3- h b- Operiiitions R deV Committee Date a i s Approved - M

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PNPS CORE OPERATING LIMITS REPORT-

-P-49 TABLE'0F CONTENTS

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- TITLE / SIGNATURE PAGE ................................................ l'

- TABLE OF'CONTENTSL..............................................'..... 2 i RECORD OF REVISIONS ................................................. 3,

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LIST 0F TABLES....................................................... 4 LIST OF FIGURES ......................-............................... '5

. 1.0~ INTRODUCTION .................................................... -6 i 2.0 INSTRUMENTATION TRIP' SETTINGS ................................... 6 .

.< 2.1-APRM Flux' Scram Trip Setting (Run Mode) ..................... 6 2.2 APRM Rod Block Trip Setting (Run Mode)..-.................... 7

-2.3 Rod Block Monitor-Trip Setting .............................. 8 l

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' 3.0 CORE OPERATING LIMITS ...........................................

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$ /T ' 3.1 Average Planar Linear Heat Generation Rate (APLHGR) ......... 9 iV

'3.2 Li near Heat Generation Rate (LHGR) . . . . . . . . . . . . . . . . . . . . . . . . . . 9 3~.3 Minimum Critical Power Ratio (MCPR) ........................ 13 3.4= Power / Flow Relationship .................................... 17 j

' 4.0 REACTOR VESSEL' CORE DESIGN ...................................... 17' 5.0' REFERENCES ......................................................-17 L

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4 > PNPS CORE.0PER4 TING LIMITS REPORT l );..

-RECORD OF REVISIONS Revision _ ' Effective _Qgig Descriotion 0 Initial. issue, applicable ~for use during Cycle 8 operation. Effective date based.

on issuance of license amendment. by NRC.

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, -LIST OF' TABLES:

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3.3 HCPR Operating Limits 15 i

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i' PNPS CORE OPERATING. LIMITS REPORT LIST OF FIGURES Rumbar lille PjLgg 3.1-1 Maximum' Average Planar, Linear Heat Generation 10 Rate (MAPLHGR) for Fuel Types P8DRB282 and BP80RB282

- 3;1 Maximum Average Planar Linear Heat Generation 11 Rate-(MAPLHGR) for Fuel Type P80RB265H 3.1-3 Maximum Average Planar Linear Heat Generation 12 Rate (MAPLHGR)=for Fuel-Type BP8DRB300

- 3.3-1 Kr Factor 16-3.4-1 Power / Flow Operating Map 18 4.0 Reactor Vessel Core Loading Pattern 19 u

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.PNPS CORE OPERATING LIMITS REPORT-

1.0 INTRODUCTION

This report-providesL the cycle-specific limits' for operation of _the -

Pilgrim Nuclear Power Station = (PNPS) during Cycle' 8. .

In this report, Cycle 8 will: frequently be referred to-as the present' cycle.

Although-this: report is' not part of the PNPS Technical Specifications, the.

Technical' Specifications ~ refer to this report.for the applicable values of-c the_following fuel-related parameters:

Reference.

Technical Soecification APRM Flux Scram Trip Setting (Run Mode) Tabl.e 3.1.1 APRM-Rod Block Trip Setting (Run Mode) Table 3.2.C-2:

' Rod Block Monitor' Trip Setting Table 3.2.C-2 Average Planar Linear Heat Generation Rate-(APLHGR)' 3.11.A Linear Heat' Generation-Rate (LhCR) 3. ll .B-

Hinimum Critical' Power Ratio (MCPR) 3.11.C Power / Flow.Reiationship 3.11.D Reactor Vessel Core Design 5.2 If any of the core operating limits in this report are exceeded, actions will be taken as defined in the referenced Technical Specification.

The-core operating limits in this report have'been-established for the present cycle using the NRC-approved methodology provided in the documents O,- listed both in Section 5.0, References, and in Technical Specification 6.9.A.4'. These limits are established such that the applicable limits of the plant safety analysis are met.

2.0 INSTRUMENTATION TRIP SETTINCd 2.1 APRM Flux Scram Trio Settina (Run Mode)

Reference Technical Soecifications: Table 3.1.1, 3.1.B.1 4

When the mode switch is in the run position, the average power range monitor (APRM) flux scram trip setting (Ss ) shall be:

Ss 1 0.58 H + 62%

Where, SS - APRM flux scram trip setting in percent of rated thermal power (1998 MHt )-

H = Percent of drive flow required to produce a rated core flow of 69 Mlb/hr.

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L 2.1 APRM Flux Scram Trio Settina (Run Mode) Continued: i lc.k M In the cvent of. operation with a maximum fraction of limiting power  ;

density (MFLPD) greater than the fraction of rated power (FRP),~.the y

,y APRM. flux =, scram trip: setting.shall be modified as follows:-

, FRP

'S s 1 (0.58 H + 62%) MFLPD -;

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.- Where, FRP - Fraction of rated thermal power (1998 MHt }*

MFLPD - Maximum fraction of limiting power density, where the-limiting power density is 13.4 KH/ft-for'all fuel.

The ratio of FRP to MFLPD shall'be set equal to 1.0 unless the actual' operating-value is less than the design value of 1.0, in which case t o actual = operating value will be used.

As an alternative action, the APRM gain may be adjusted such that th'e APRM readings are greater than or equal to 100% times MFLPD,.provided that the adjusted APRM reading does'not exceed 100% of RATED THERMAL-p, POWER and a' notice of adjustment is posted on the reactor. control ,

3 panel. .

'N' -The APRM flux scram trip setting is valid only for operation using' two d~

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recirculation-loops. Operation with one recirculation loop out of service is restricted by License Condition 3.E.

In -accordance with Technical Specification Table-3.1.1, Note 15 for no combination.of loop' recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of' rated therma! power, j 2.2 APRM~ Rod Block Trio Settina (Run Mode) 'I fleference Technical Soecifications: Tabl e 3.2.C-2, 3.1.B.1 ,

When the mode switch is in the run position, the average power range monitor-(APRM) rod block trip. setting (SRB).shall be: ,

l '

i SRB 1 0.58 H + 50%

i Where, SRB - APRM rod block trip setting in percent of rated thermal power (1998 MHt }-

H - Percent of drive flow required to produce a rated core flow of 69 M1b/hr. -

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. 1 PNPS CORE OPERATING LIMITS REPORT- J 1

,,s L ' APRM Rod' Block Trio Settina (Run Mode). Continuhd ,

In the event of operation with'a' maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power'(FRP), the APRM rod block trip-setting shall be modified as follows. i FRP 1 SRB 1 (0.58 H + 50%) MFLPD I

Hhere, FRP = Fraction of rated thermal power (1998 MHt )-

-l MFLPD = Maximum' fraction of limiting power density, where the limiting power is 13.4 KH/ft for all- fuel.

l The ratio of FRP to MFLPD shall t'e set equal to 1.0:Unless the_ actual ,~

operating value is less than the design value of 1.0, in which case the actual operating value will be used.

-As an alternative action, the APRM gain may be adjusted such that the APRM readings are greater than or equal.to 100% times NFLPD, provided

-that'the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER and a notice of adjustment is posted on the reactor control L panel.

The APRM rod block trip setting is valid only for operation using two

,6l- recirculation loops. Operation with one recirculation loop out of service is-restricted by License Condition 3.E.

2.3 Rod Block Monitor Trio Settina I

Reference Technical Soecification: Table 3.2.C-2 The rod block monitor trip setting (SM) shall be:

FRP Sg 1 (0.65 H + 42%)- HFLPD-Where, Sg = Rod block monitor trip setting in percent of rated thermal power (1998 MHt )-

H = Percent of drive flow required to produce a rated core flow of'69 M1b/hr.

FRP = Fraction of rated thermal power (1998-MHt )-

MFLPD = Maximum fraction of limiting power density, where the limiting power density is 13.4 KH/ft for all fuel.

N For core flows of 100% or greater, the rod block monitor trip setting

=.

shall not exceed 107% power, o

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.,fa, -3.0 CORE OPERATING LIMITS-L3.1 Averaae Planar Linear Heat: Generation' Rate (APLHGR)'

, . , Reference Technical- Soecification: 3.11.A  !

/ During power operation with both recirculation pumps operating, the APLHGR for each type of fuel as a function of average planar exposure' shall not: exceed the applicable limiting value shown in Figuresr3.1-1 through 3'.1-3.- The' top curves on these, figures are applicable-for.

t core flow greater than or equal to 90% of rated core flow. The lower '

curves are applicable for core flow less than 90% of rated core flow. = -

The core loading pattern for each type of. fuel in the reactor vessel-  ;

m -is shown for the present cycle in Figure 4.0-1.

I

'3.2 Linear Heat Generation Rate (LHGR)

', Reference Technical Specification: 3.11.B During reactor power operation, the LHGR.of any rod in any fuel assembly at any axial location shall not exceed 13.4 KH/ft. This limit is applicable for all fuel assemblies loaded in the core in the -

, present cycle. l

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Planar Average Exposure (MWD /ST)

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O FIGURE 3.1 , e, Maximum Average Planar Linear Heat Generation Rate 3 (MAPLHGR) for Fuel Tyhr.. P8DRB282 and BP8DRB282 1

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- FIGURE 3.1-2:

9., Maximum Average Planar Linear Heat Generation Rate G (MAPLHGR) for Fuel Type P8DRB265H

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- U FIGURE 3.1-3 C

2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for Fuel Type BP8DRB300

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PNPS CORE OPERATING LIMITS REPORT 3.3 Minimum Critical Power Ratio (MCPR)

Reference Technical Sor2ification: 3.11.C [

During power operation, MCPR shall be greater than or equal to the MCPR operating limits provided in Table 3.3-1. These MCPR operating .

limits are a function of the average scram insertion time ( 7), which I is calculated as described below. )l For core flows other than rated, the MCPR operating limits in Table  !

3.3-1 shall be multiplied by the factor Kf, which is given in Figure  :

3.3-1. As an alternative method providing equivalent l thermal-hydraulic protection at core flows other than rated the  ;

calculated MCPR may be divided by Kr, with the MCPR operating limits '

in Table 3.3-1 left unchanged.

The value of the average scram insertion time ( 7) in Table 3.3-1  :

shall be equal to 1.0, unless it is calculated from the results .f the  :

surveillance testing of Technical Specification 4.3.C. as follows:  ;

7 ave - 78 7-1.275 - rB ,

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i h) Tj KM re' Tave - Avera e scram time to the - i-1 30% nsertion position n Nj 4-i

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L TB - Adjusted analysis - 4 + 1.65 n i mean scram time yN i i

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1 n - Number of surveillance tests performed to date in the present cycle th Ni - Number of active control rods measured in the i

, surveillance test Revision 0 Page 13 of 19

l PNPS CORE OPERATIN3 LIMITS REPORT q l

,,_ 3.3 Minimum Critical Power Ratio (MCPR) Continued j u) Tj=Averagescramtimetoge30%insertionpositionofall rods measured in the i surveillance test i

-g Mean of the distribution for average = 0.945 sec ]

scram insertion time to the 30%

position i o Standard deviation of the distribution - 0.064 sec  ;

'for average scram insertion time  ;

to the 30% position 1

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+ PNPS CORE OPERATING LIMITS REPORT  ;

i 7%. TABLE 3.3-1 l MCPR OPERATING LIMITS Average Scram Insertion Time ( 7 ) MCPR Operatina Limit ,

For operation .from the Beginning of Cycle (BOC) to'80C + 7,513 MHD/ST:

All values of 7 1.33 for operation from BOC + 7,513 PJ3D/ST to the End of Cycle'  !

7'1 0.0 1.36  !

0.0 < r 1 0.V 1.37 0.1 < 7 1 0.2 'T .

l 0.2s710.3 1.38 i, 0.3 < 7 1 0.4 1.38 0.4 < 7 1 0.5 1.39 l

0.5 < 7 1 0.6 1.39 F 0.6 < 7 1 0.7 '..40 i 0.7 < 7 1 0.8 1.40 0.8 < 7 1 0.9 1.41 ,

0.9 < 7 1 1.0 1.41

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0.90 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 J; Core Flow (%)

o i m FIGURE 3.3-1 e,

l G K 7 Factor i

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

PNPS CORE OPERATING LIMITS REPORT f .

3.4 Egygr/ Flow Relationshio Durina Powr Operation

-) Reference Technical Specification: 3.11.D ,

i The power / flow relationship shall not exceed the limiting values shown i on the Power / Flow Operating Map in Figure 3.4-1. '

i 4.0 REACTOR VESSEL CORE DESIGN v Reference Technical Specification: 5.2 ,

The reactor vessel core for the present cycle consists of 580 fuel  ;

assemblies of the types listed below. The core loading pattern for each 1 type of fuel is shown for the present cycle in Figure 4.0-1.

Fuel Tvoe Cvele Loaded Number Irradiated P80RB282 5 24 P8DRB265H 6 60 P80RB282 6 112 P8DRB282 7 160 ^

BP80RB282 7 32 O

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BP8DRB300 8 122 Total 580 The reactor vessel core contains 145 cruciform-shaped control rods. The.

control materials used are either boron carbide powder (B C) 4 compacted to

. approximately 70% of theoretical density or a combination of boron carbide powder and solid hafnium.

5.0 REFERENCES

5.1 NEDE-24011-P-A-8-US, " General Electric Standard Application for

< Reactor Fuel," May 1986.

5.2 NEDO-21696, " Loss of Coolant Analysis Report for Pilgrim Nuclear Power Station," August 1977, as amended.

5.3 Amendment 14 to NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," December 27, 1987, for MCPR safety limit.

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O 5 10 15 20 25 30 35 40 45 50 55 60 65 69 75 80 ,

2 Core Flow (MLB/HR) ,

=  :

5!, MGURE 3.4-1  :

G Power / Flow Operating Map  ;

PNPS CORE OPERATING LIMITS REPORT O  : HHHHHHH

HHHHHHHHH

HHHHHHHHHHH

3HHHHHHHHHHHH

-MHHHHHHHHHHHH

MHHHHHHHHHHHH

2HHHHHHHHHHHH rHHHHHHHHHHHHH

-HHHHHHHHHHHHH o  :-ggggggggggggg

HHHHHHHHHHH i L HHHHHHHHH I 3 5 7 9 11 41 43 45 47 49 51 Fuel Types Z P8DRB282, Cycle 5 @ BP8DRB282, Cycle 7

@ P8DRB265H, Cycle 6 E P8DRB282, Cycle 7 B P8DRB282,Cyc.e 6 E BP8DRB300, Cycle 8 f FIGURE 4.01 Reactor Vessel Core Loading Pattern Revision 0 Page 19 of 19 f

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