ML20062E923
| ML20062E923 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/05/1990 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20062E852 | List: |
| References | |
| NUDOCS 9011260197 | |
| Download: ML20062E923 (20) | |
Text
. -
PILGRIM NUCLEAC POWER STATION CORE OPERATING LIMITS REPORT CYCLE 8 Approved #. " /Po NucVear Analysis Division Manager Date Approved I"s: IMW . ///[90 HuclearEngineerigDepartmentManager Date 4 Reviewed Md b .
///#/ie Date'
[
Of ations Re' view Committee Approved Yqf flhlfo /M'90 Station Director Date U
Revisior O Page 1 t,f 19 F' F P
hhbbkbhhhhf93 PDC
t PNPS CORE OPERATING LIM 17S REPORT TABLE OF CONTENTS Elitt TITLE / SIGNATURE PAGE ................................................ I TABLE OF CONTENTS ................................................... 2 RECORD OF REVISIONS ................................................. 3 LIST OF TABLES ........................ ............................. 4 LIST OF FIGURES ................. ................................... 5
1.0 INTRODUCTION
.................................................... 6 2.0 INSTRUMENTATION 1 PIP SETTINGS ................................... 6 2.1 APRM Flux Scram 1rio Setting (Run Mode) ................ .... 6 L
2.2 APRM Rod Block Trip Setting (Run Mode)...................... 7
- 2. 3 Rod civ:F Moni tor T ri p Set ti ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.0 CORE OPERATING LIMITS ........................................... 9 3.1 Average Planar Linear Heat Generation Rate (APLHGR) ......... 9 3.2 Linest Heat Generation Rate (LHGR) .......................... 9
~
3.3 hinimum Critical Power Ratio (MCPR) ........................ 13 3.4 Poweriilow Relationship .................................... 17 4.0 REACTOR VESSEL CORE DESIGN ...................................... 17
5.0 REFERENCES
..................................................... 17 Revision 0 Page 2 of 19 1
= ;
PNPS CORE OPERA 71NG LIMITS REPORT RECORD OF REVISIONS Revision Effective Date Descrietion 0 Initial issue, applicable for use during
- Cycle B operation. Effective date based on issuance of license amendment by NRC.
=
Revision 0 Page 3 of 19
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PNPS CORE OPERATING L1 HITS REPORT LIST OF FIGURES
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__ 3,1 1 Haximum Average Planar Linear Heat Generation 10 Rate (HAPLHGR) for Fuel Types PBDRB282 and BP80RB282 3,1-2 Maximum Average Planar Linear Heat Generation 11 Rate (MAPLHGR) for Fuel lype P8DRB265H
(.
3,1-3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for Fuel Type BP80RB300 12 3,3-1 16 Kf Factor 344-1 Power / Flow Operating Map 1B 4.0-1 Recttor Vessel Core Loading Pattern 19 m
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Revision 0 Page 5 of 19 m
E
PNPS LSRE OPERATING LIMITS REPORT
1.0 INTRODUCTION
This report provides 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 the following fuel-related parameters .
l Reference I Technical Soecification APRH Flux Scram Trip Setting (Run Mode) Table 3.1.1 APRH Rod Block Trip Setting (Run Mode) Table 3.2.C-2 Rod Block Honitor Trip Setting Table 3.2.C-2 Average Planar Linear Heat Generation Rate (APLHGR) 3.ll.A Linear Heat Generation Rate (LHGR) 3.11.B Minimum Critical Power Ratio (MCPR) 3.II.C Power / Flow Relationship 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 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 SETTINGS 2.1 APRM Flur Scram Trio Settina (Run Mode)
Reference Technical Soecifications: Table 3.1.1, 3.1.B.1 When the mode switch is in the run position, the average power range monitor (APRH) flux scram trip setting ($3 ) shall be:
l S3 1 0.58 H + 62%
Where, S3 APRH flux scram trip setting.in percent of rated thermal power (199? HHt )-
H Percent of drive flow required to produce a rated core l flow of 69 Hib/hr.
l l Revision 0 Page 6 of 19 l
PNPS CORE OPERATING LIMITS REPORT 2.1 APRM Flux Scram Trio Settina (Run Mode). Continued In the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), the APRM flux scram trip setting shall be modified as follows:
FRP S3 1 (0.58 H + 62%) MFLPD 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 themactual operating value will be used.
The APRM flux scram trip setting is valid only for operation using two recirculation loops. Operation with one recirculation loop out of service is restricted by License Conditio*. 3.E.
In accordance with Technical Specification Table 3.1.1, Note 15, for no combination of loop recirculation feow rate and core thermal power shall the APRM flux scram trip settinj be allowed to exceed 120% of rated thermal power, ,
2.2 APRM' Rod Block Trio Settino (Run Mede)
Reference Technical Soecifications: Table 3.2.C-2, 3.1.B.1 o ,Hhen the-mode switch is in the run position, the average power range monitor (APRM) rod block trip setting (SRB) shall be:
l o
SRB 1 0.58 H + 50%
Where, Sgg - APRM rod block trip setting-in percent of rated thermal i power (1998 MHt )- '
H = Percent of drive flow required to produce a rated core l'
flow of 69 M1b/hr.
Revision 0 Page 7 of 19
PNPS CORE OPERAVING LIMITS REPORT 2.2 APRM Rod Block Trio Settina (Run Mode). Continued 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:
._ERP__
SRB 1 (0.58 H + 50%) MFLPD Where, FRP = fraction of rated thermal power (1998 MHt ).
L HFLPD = Maximum fraction of limiting power density, where the limiting power is 13.4 KH/ft for all. fuel.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual opc ating value is less than the design value of 1.0, in whict case
-the actual-operating value will be used.
1 The APRM rod block trip setting is valid only for operation using two recirculation loops. Operation with one recirculation loop out of service is restricted by License Condition 3.E.
2.3 Rod Block Monitor Trio Settina Reference Technical Soecification: Table 3.2.C-2 The rod block monitor trip setting (Sg) shall be:
FRP SM 1 (0.65 W + 42%) MFLPD Where, SH = 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 Mlb/hr.
FRP = fraction of rated thermal power (1998 MHt )-
HFLPD = Maximum fraction of limiting power density, where the limiting power density is 13.4 KH/f t-for all fuel.
For core flows of 100% or greater, the rod block monitor trip setting shall not exceed 107% power.
- 1 Revision 0 Page 8 of 19
PNPS CORE OPERATING LIMITS REPORT 3.0 CORE OPERATING LIMITS 3.1 Averaae Planar Linear Heat Generation Rate (APLHG Q Reference Technical Snecification: 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 Figures 3.1-1 through 3.1-3. The top curves on these figures are applicable for 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 is shown for the present cycle in Figure 4.0-1, 3.2 Linear Heat Generation Rate (LHGR)
Reference Technical Snecification: 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 KW/ft. This limit is applicable for all fuel assemblies loaded in the core in the present cycle.
l Revision 0 Page 9 of 19 L ,
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- Core Flow < 907c rated 0 Core Flow 2 'Mn rated g, . _ _ _ _ _
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Planar Average Expmure (MWI)/ST) 2?
m FIGURE 3.1-1
[ Maximum Average Planar Linear IIcat Generation Rafe.
g (M APLIIGR) f'or Fuci Types PMI)RIl282 and 1 I'MI)Rit2M2 9
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?_. FIGURE 3.1-2 p., Maximum Average Planar I incar IIcat Generation Rate g (MAPI,IIGR) for FucI Type PSDR15265!I e
W + Core Flow < 907c rated 0 Core Flow 2 9Fo rated 5.
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Y U FIGURE 3.1-3 o
2 Maximum Average Planar I,incar IIcat Generation Rate
. (M API,IIGR) l'or Fuci Type IlP8DRIt300 s
o PNPS CORE OPERATING LIMITS REPORT 3.3 Minimum Critical Power Ratio (MCOR)
Reference Technical Soecification: 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 is calculated as described below.
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 thermal-hydraulic protection at core flows other than rated, the calculated MCPR may be divided by K f , with the MCPR operating limits I 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 of the surveillance testing of Technical Specification 4.3.C. as follows:
7 ave - i B 7=
1.275 - TB n
5 Ng 7g Where, Tave = Average scram time to the - i=1 30% insertion position n 5 Nj i=1 N; ~%
a TB = Adjusted analysis = 4 + 1.65 n mean scram time
.i=1 .
n Number of surveillance tests performed to date in the present cycle th Ng Number of active control rods measured in the i l_ surveillance test l
I, Revision 0 Page 13 of 19
PNPe CORE OPERATING L! HITS REPORT 3.3 Minimum Critical Power Ratio (MCPR). Continued Tj.Averagescramtimetotge30%insertionpositionofall rods measured in the 11 surveillance test
. Mean of the distribution for average 0.945 set scram insertion time to the 30%
position o . Standard deviation of the distribution = 0.064 set for average scram insertion time to the 301 position Revision 0 Page 14 of 19 I
.ii.ii-iii.-
PNPS CORE OPERATING LIMITS REPORT TABLE 3.3-1 ,
1 MCPR OPERATING L1 HITS Average Scram 1 Intertion Time ( 7 ) MCPR Ooeratina Limit for operation from the Beginning of Cycle (BOC) to BOC + 7,513 MWD /ST:
All values of 7 1.33 for operation from BOC + 7,513 MWD /ST to the End of Cycle:
7 1 0.0 1.36 0.0 < 7 1 0.1 1.37 0.1 < 7 1 0.2 1.37 0 ? < 7 1 0.3 1.38
)
0.3 < 7 1 0.4 1.38 0.4 < 710.5 1.39 0.5 < 7 5 0.6 1.39 0.6 < 7 1 0.7 1.40 !
0.7 < T 1 0.8 1.40 0.8 < 7 1 0.9 1.41 1,41 0.9 < 7 1 1.0 Revision 0 Page 15 of 19 i
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m FIGURE 3.3-1 o,
q; K 7 Factor
PNPS CORE OPERATING LIMITS REPORT 3,4 Power /rlew Relationshio Durino Powr Ooeration l
Reference Technical Seetification: 3.11.0 The power / flow relationship shall not exceed the limiting values shown on the Power / Flow Operating Hap in Figure 3.4-1.
4.0 REACTOR VESSEL CORE DESIGN Reference Technical SDecification: 5.2
-The reactor vessel core for the present cycle consists of 580 fuel 1 assemblies of the types listed below. The core loading pattern for each type of fuel is shown for the present cycle in Figure 4.0-1.
Fuel Typ1 Cycle loaded Number l Irradiated P8DRB282 5 24 P8DRB265H 6 60 P8DRB282 6 112 P8DRB282 7 160 BP8DRB282 7 32 New l BP80RB300 8 122 Total 580 !
The reactor vessel core contains 145 cruciform-shaped control rods. The l
control materials used are either boron carbide powder (B C) 4 compacted to l
approximately 707, of theoretical density or a combination of boron carbide j powder and solid hafnium.
1 l
5.0 REFERENCES
5.1 NEDE-24011-P-A-8-US, " General Electric Standard Application for Reactor Fuel," May 1986. !
5.2 NE00-21696. " Loss of Coolant Analysis Report for Pilgrim Nuclear Power l 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.
I Revision 0 Page 17 of 19 i
i
PNPS CORE OPERATING L1hCTS REPORT (d13H %) Janod P81tB Jo luessed E 5 E R S R % R R E
- R. E. -
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L- PNPS CORE OPERATING LIMITS REPORT
- : HHHHHHH
- HHHHHHHHH
- HHHHHHHHHHH )
3HHHHHHHHHHHH
- HH HHHHHHHHHHH ;
- 3HHHHHHHHHHHH '
- M M BB H H H H H H H H H E
- MHHHHHHHHHHHH
'HHHHHHHHHHHHM >
L 3HHHHHHHHHHHE1 :
MHHHHHHHHHH
- ENHHHHHHH :
L : 2+9 EMMpMp 1 3 5 7 9 111315171921232527293133353739414345474951 Fuel Tvpes _
Z PSDRB282, Cycle 5 - @ BP8DRB282, Cycle 7
@ P8DRB265H, Cycle 6 g P8DRB282, Cycle 7 0 P8DRB282, Cycle 6 E BP8DRB300, Cycle 8 FIGURE 4.01 Reactor Vessel Core Loading Pattern Page 19 of 19 Revision 0
._____.m.. , . . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
. . _ - . _ _ . . - _ _ . _ _ _- _ . _ _ _ _ ~ - _- --
l PNPS CORE OPERATING IJMITS REPORT l
- HHHHHHH l : HHHHHHHHH HHHHHHHHHHH 1 .
3HHHHHHHHHHHH
- :2HMHHHHHHHHHH l l18HHHHHHHHHHHH l2MBiHB8HHHHHHHB8 )
3HHHHHHHHHHHH :
- 3MHHHHHHHHHHH i
! ltMHHHHHHHHHHHM i : MHHHHHHHHHH l l MHHHHHHHM
- MERMMME 1 3 5 7 9 11 13 15 17 19 2123 25 27 29 31 33 35 37 39 4143 4$ 47 49 51 Fuel Types l
@ P8DRB282, Cycle 5 @ BP8DRB282, Cycle 7 l @ P8DRB265H, Cycle 6 E P8DRB282, Cycle 7 i
0 P8DRB282, Cycle 6 M BP8DRB300, Cycle 8 FIGURE 4.01 Reactor Vessel Core Loading Pattern Revision 0 Page 19 of 19
,