ML20028H757
| ML20028H757 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/26/1990 |
| From: | Fairland R BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20028H754 | List: |
| References | |
| NUDOCS 9101290396 | |
| Download: ML20028H757 (19) | |
Text
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PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT (CYCLE 8)
Approved
- 7 d /
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Nucleir Analysis Divisi6n Manager Date Approved M
/2 7/#/62 7
Nuclear Engineering Department Manager D' ate Reviewed h
/ 2/d/ /90 OperMfons Review) Committee f
' Date V' ('/O - /46 Approved Y Ib M[>
hi RAA
'2l2Gl 96 StationDirgetor[
t Date Revision 8A Page 1 of 19 9101290306 910122 l
{DR ADOCK 05000293 PDR
PNPS CORE OPERATING LIMITS REPORT TABLE OF CONTENTS Pace TITLE / SIGNATURE PAGE................................................
1 TABLE OF CONTENTS...................................................
2 RECORD OF REVISIONS.................................................
3 LIST OF TABLES......................................................
4 LIST OF FIGURES.....................................................
5
1.0 INTRODUCTION
5 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 Bl ock Moni tor Tri p Se tti ng..............................
8 3.0 CORE OPERATING LIMITS...........................................
9 3.1 Average Planar Linear Heat Generation Rate (APLHGR) 9 3.2 Linear Heat Generation Rate (LHGR) 9 3.3 Minimum Critical Power Ratio (MCPR)........................
13
- 3. 4 Powe r/ Fl ow Rel ati on s hi p....................................
17 4.0 REACTOR VESSEL CORE DESIGN.....................................
17 S.0 REFERENCES....................................................
17 t
(
Revision 8A Page 2 of 19
PNPS CORE-OPERATING LIMITS REPORT RECORD OF REVISIONS Revision Effective Date Descriotion BA Effective date based Applicable for use during on issuance of license Cycle 8 operation, amendment by NRC.
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t Revision 8A Page 3 of 19 l
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PNPS CORE OPERATING-LIMITS REPORT LIST OF TABLES h!bfer Tit 1e PAgt 3.3-1 MCPR Operating Limits 15 i
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Revision 8A Page 4 of 19
PNPS CORE OPERATING LIMITS REPORT LIST OF FIGURES N nhgr Title Pace L
3.1-1 Maximum Average Planar Linear Heat Generation 10 Rate-(MAPLHGR) for fuel Types P8DRB282 and BP80RB282 3.1-2 Maximum Average Planar Linear Heat Generation 11 Rate (HAPLHGR) for fuel Type P80RB265H 3.1-3 Maximum Average Planar Linear Heat Generation 12 Rate (MAPLHGR) for Fuel Type BP80RB300 3.3-1 K Factor 16 r
1 3.4-1 Power / Flow Operating Hap 18 4.0-1 Reactor Vessel Core Loading Pattern 19 Revision 8A Page 5 of 19
PNPS CORE 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 reporc, 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:
Reference Technical Soecification APRM Flux Scram Trip Setting (Run Mode)
Table 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 (LHGR) 3.11.8 Minimum Critical Power Ratio (MCPR) 3.ll.C Power / Flow Relationship 3.11.0 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.
N 2.0 INSTRUMENTATION TRIP SETTINGS 2.1 APRM Flux 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 (APRM) flux scram trip setting (S ) shall be:
s Ss 1 0.58 H + 62%
2
t H - Percent of drive flow required to produce a rated core flow of 69 Mlb/br.
Revision 8A Page 6 of 19 i
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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 t
APRM flux scram trip setting shall be modified as follows:
~ FRP -
S 1 (0.58 H + 62%)
- _MFLPD, 3
t MFLPD = Maximum fraction of limiting power density, where the limiting power density is 13.4 KH/f t 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 the actual 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 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 thermal power.,
2.2-APRM Rod Block Trio Settina (Run Hod.gl Reference Technical Soecifications:
Table 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:
SRB 1 0.58 H + 50%
- Where, SRB = APRM rod block trip setting in percent of rated thermal power (1998 MH )-
t H = Percent of drive flow required to produce a rated core flow of 69 Mlb/hr.
Revision 8A Page 7 of 19
PNPS CORE 0PERATING 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:
~ FRP -
SR8 1 (0.58 H + 50%)
_MFLPD.
Wher'.
FRP - Fraction of rated thermal power (1998 MW )-
t MFLPD - 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 operating value is less than the design value of 1.0, in which case the actual operating value will be used.
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 Honitor Trio Settina Reference Technical Soecification:
Table 3.2.C-2 The rod block monitor trip setting (S ) shall be:
M FRP ~
Sg 1 (0.65 H + 42%)
.MFLPD.
- Where, SM - Rod block monitor trip setting in percent of rated thermal power (1998 MH )-
t H - Percent of drive flow required to produce a rated core flow of 69 Mlb/hr.
FRP - Fraction of rated thermal power (1998 MW )-
t MFLPD - Maximum fraction of limiting power density, where the limiting power density is 13.4 KH/ft for all fuel.
For core flows of 100% or greater, the rod block monitor trip setting I'
shall not exceed 1071 power.
{
Revision 8A Page 8 of 19 l
PNPS CORE OPERATING LIMITS REPORT 3.0 CORE OPERATING LIMITS 3.1 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 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 Soecification:
3.11.8 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.
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Maximum Average Planar Linear Heat Generation Rate o
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FIGURE 3.1-2 k
Maximum Average Planar Linear Heat Generation Rate G
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C FIGURE 3.1-3 O
Maximum Average Planar Linear Heat Generation Rate O
(MAPLHGR) for Fuel Type BP8DRB300
PNPS CORE OPERATING LIMITS REPORT s.
3.3 Minimum Critical Power Ratio (MCPR)
Reference Technical Soecification:
3.ll.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 (t), which is calculated as described below.
For core flows other thar rated, the MCPR operating limits in Table 3.3-1 shall be multiplied by the factor Kr. 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 Kr, with the MCPR operating limits in Table 3.3-1 left unchanged.
The value of the average scram insertion time (t) in Table 3.3-1 shall be equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical S)ecification 4.3.C, as follows:
T ave - TB t -
1.275 - tg n
Ni tj Where, T Average scram time to the i-1 ave 301. insertion position n
Nj 1-1 Nj X
TB - Adjusted analysis p + 1.65 n
o mean scram time
_i-1 n - Number of surveillance tests performed to date in the present cycle th Nj - Number of active cont,*ol rods measured in the i surveillance test Revision 8A Page 13 of 19
[
PNPS CORE Oi ATING LIMITS REPORT 3.3 Minimum Critical Power Ratio (MCPR). Continued tj = Average scram time to tge 30% insertion position of all rods measured in the i t surveillance test p = Mean of the distribution for average
= 0.945 set scram insertion time to the 30%
1 position o - Standard deviation of the distribution
= 0.064 sec for average scram insertion time to the 30% position l
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Revision 8A Page 14 of 19
PNPS CORE OPERATING LIMITS REPORT TABLE 3.3-1 MCPR OPERATING LIMITS-Average Scram Insertion Time ( t )
MCPR Ooeratina Limit For operation from the Beginning of Cycle (BOC) to BOC + 7,953 MHD/ST:
All values cf x 1.48 for operation from BOC + 7,953 MWD /ST to the End of Cycle:
x 1 0.0 1.41 f
0.0 < t 1 0.1 1.42 O.1 < x 1 0.2 1.43 0.2 < t 1 0.3-1.44 0.3 < t 1 0.4 1.45 0.4 < t f. 0. 5 1.46 0.5 < t 1 0.6 1.47 0.6 < t 1 0.7 1.48 0.7 < t 1 0.8 1.49 0.8 < t 1 0.9 1.50 0.9 < t 1 1.0 1.51 Revision 8A Page 15 of 19
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PNPS CORE OPERATING LIM!TS REPORT 3.4 Power / Flow Relationshio Durina Powr Ooeration 4
Reference Technical Soecification:
3.11.D The power / flow relationship shall not exceed the limiting values shown on the Power / Flow Operating Map in Figure 3.4-1.
4 4.0 REACTOR VESSEL CORE DESIGN Reference Technical Soecification:
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 type of fuel is shown for the present cycle in Figure 4.0-1<
fuel Tvoe Cycle loaded Number Irradiated i
P8DRC282 5
24 P80RB265H 6
60 P80RB282 6
112 P80RB282 7
160 BP80RB282
,7 32-New BP80RB300 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) compacted to 4
approximately 70% of theoretical density or a cc;.binatioa of boron carbide powder-and solid hafnium.
5.0 REFERENCES
5.1 NEDE-24011-P-A-8-US, " General Electric Stradard Application for Reactor Fuel," May 1986.
5.2 NED0-21696, " Loss of Coolant Analysis Report for Pilgrim Nuclear Power Station " August 1977 with errata and addenda through No 5 dated j;
October.1986.
5.3 Amendment 14 to NEDE-24011-P-A, " General' Electric Standard Application for Reactor fuel." December 27, 1987, for MCPR safety limit.
Revision BA Page 17 of 19 1
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- F Core Flow (MLB/HR)
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FIGURE 3.4-1 G
Power / Flow Operating Map
PNPS CORE OPERATING LIMITS REPORT MMMBaBBHE MNNNNNNHBi MBRMBRMa+ MMNBRM
- 8 8 H H B I M M H H H M M B R 8+8
- -M M M M M M M ME+2H M M M
- as H DE M M M M M M M M BBBB
- 88M8+ ibis +8M8+8E8+8NE+8B8M
- 8BMMMMMMBBBRMMMM
- MMB8HEMB8MBEM8+ MBE
- -88H HBRMBBBIBEMBEM MR+R M BR Mi+2BRE N BEM BIB 8 MMMMMENMM MEMMMME 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Fuel Types
@ P8DRB282, Cycle 5
@ BP8DRB282, Cycle 7
@ P8DRB265H, Cycle 6
@ P8DRB282, Cycle 7 O P8DRB282, Cycle 6 E BP8DRB300, Cycle 8 FIGURE 4.01 Reactor Vessel Core Loading Pattern l
Revision SA Page 19 of 19
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