ML20137S734
| ML20137S734 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/27/1997 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20137S722 | List: |
| References | |
| NUDOCS 9704150231 | |
| Download: ML20137S734 (26) | |
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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02
)
(CYCLE 12) i
,-3h8/9/
APPROVED:
Operations [pport Department Manager
/ Dafe APPROVED:
N
[
huclear Engineering Services Group Manager Date APPROVED:
AAMf Oltr. Maci.ac,,4 91 3[27/97 Operation @evie' Cordnittee T7 Date w
APPROVED:
i
//
M MR7Date[
P p-Mdiager' '
7 f7 APPROVED:
Station Dfrfector
' Date j
l 9704150231 970409 PDR ADOCK 05000293 P
PDR COLR REVISION 12A PAGE 1 OF 26
i PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 t
TABLE OF CONTENTS PARC TITLE /S I GN ATURE PAGE.......................................................................... 1 TAB LE OF C ONTENTS..................................................................................... 2 RECORD OF REVISION S..................................................................................; 3 LI ST OF TAB LES............................................................................................... 4 LI ST OF FI GURE S.............................................................................................. 5 1
1.0 INTRODU CTI ON................................................................................... 6 1
2.0 INSTRUMENTATION TRIP SETTINGS....................................... 7 1
l 2.1 APRM Flux Scram Trip Setting (Run Mode)............................ 7 2.2 APRM Rod Block Trip Setting (Run Mode)............................. 7 2.3 Rod Block Monitor Trip Setting.................................................... 8 3.0 CORE OPERATING LIMIT S........................................................... 9 3.1 Average Planar Linear Heat Generation Rate (APLHGR).....
..........9 3.2 Linear Heat Generation Rate (LHGR)........................................... 9 1
3.3 Minimum Critical Power Ratio (MCPR).......................................18 3.4 Power / Flow Relationship...............
.. 24 4.0 REACTOR VESSEL CORE DESIGN............
.24
5.0 REFERENCES
..........24 COLR REVISION 12A PAGE 2 OF 26
i
~
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATINGLIMITS REPORT RTYPE: G4.02 1
RECORD OF REVISIONS Revision Effective Date Descriotion l
8A Effective date based on Applicable for use during issuance officense Cycle 8 Operation j
amendment byNRC i
9A Effective date based on Applicable for use during i
issuance oflicense Cycle 9 operation l
i amendment byNRC for i
10A Effective date based on Appl'icable for use during
.i initial startup ofCycle 10 Cycle 10 Operation l
I 11A Effective date based on Applicable for use during i
initial startup ofCycle 11 Cycle 11 Operation 1IB Effective upon final Applicable for use during approval Cycle 11 Opersion 11C Effective upon final Applicable for use during approval Cycle 11 Operation 11D Effective upon final Applicable for use during approval Cycle 11 Operation 12A Effective date based on Applicable for use during issuance officense Cycle 12 Operation amendment byNRC for SLMCFR of1.08 COLR REVISION 12A PAGE 3 OF 26
s PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LP.ETS REPORT RTYPE: G4.02 LIST OF TABLES Number Tit]t East 3.2-1 LHGR Operating Limits 10 3.3-1 MOC MCPR Operating Limits 20 3.3-2 EOC MCPR Operating Limits 21 l
B l
1 COLR REVISION 12A PAGE 4 OF 26 4
PR., GRIM NUCLEAR POWER STATION l'NPS CORT OPERATING LIMITS REPORT RTYPE: G4.02 l
9 LIST OF FIGURES Numhsr Iide Page 3.1-1 Maximum Average Planar Linear Heat Generation 11 Rate (MAPLHGR) for Fuel Type BP8DQB323 3.1-2 Maximum Average Planar.Unear Heat Generation 12 Rate (MAPLHGR) for Fuel Type BP8HXB355 3.1-3 Maximum Average Planar Linear Heat Generation 13' Rate (MAPLHGR) for Fuel Type BP9 HUB 378 3.1-4 Maximum Average Planar Linear Heat Generation 14 Rate (MAPLHGR) for Fuel Type P9 DUB 408-6G5.0nG4.0 3.1-5 Maximum Average Planar Linear Heat Generation 15 Rate (MAPLHGR) for Fuel Type P9 DUB 408-16GZ1 3.1-6 Flow-Dependent MAPLHGR Factor (MAPFACr) 16 3.1-7 Power-Dependent MAPHLGR Factor (MAPFACp) 17 3.3-1 Flow-Dependent MCPR Limits (MCPRr) 22 3.3-2 Power-Dependent MCPR Limits (MCPRp) 23 3.4-1 Power / Flow Operating Map 25 4.0-1 Reactor Vessel Core Loading Pattern 26 COLR REVISION 12A PAGE 5 OF 26
PILGRIM NUCLEAR POWER STATION j
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02
{
1.0 INTRODUCTION
)
This report provides the cycle-specific limits for operation of the Pilgrim Nuclear l
Power Station (PNPS) during Cycle 12. In this report, Cycle 12 will frequently be l
referred to as the present cycle.
j Although this repon is not part of the PNPS Technical Specifications, the i
Technical Specifications refer to this repon for the applicable values of the j-following fuel-related parameters:
i Reference
{
Technical Speci6 cation APRM Flux Scram Trip Setting (Run Mode)
Table 3.1.1 1
APRM Rod Block Trip Setting (Run Mode)
Table 3.2.C-2 Rod Blod Monitor Trip Setting Table 3.2.C-2 AveraFs Planar Linear Heat Generation Rate 3.11. A 1
Lines: Heat Generation Rate (LHGR) 3.11.B Minimum CriticalPower Ratio (MCPR) 3.11.C Power / Flow Relationship 3.11.D Reactor Vessel Core Design 5.2 s
l If any of the core operating limits in this report are exceeded, actions will be taken i
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.
4 o
COL ~R REVISION 12A PAGE 6 OF 26 2
PILGRD.f NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 4
2.0 INSTRUMENTATION TRIP SETTINGS:
i 2.1 APRM Flux Scram Trio Settinn (Run Mode) 3
)
Erfetence Technical Soecifications: Table 3.1.1,3.1.B.1 i
2 When the mode switch is in the run position, the average power range j
monitor (APRM) flux scram trip setting (S.) shall be:
S.s 0.66 W + 69%
with a clamp at 120% ofrated core thermal power and l
S. =
APRM flux scram trip setting in percent ofrated thermal l
power (1998 MW).
i W=
Percent of drive flow required to pseduce a rated core flow of 69 Mlb/hr.
l 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.
I l
In accordance with Technical Specification Table 3.1.1, Note 15, for no combination ofloop 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 Trip Setting (Run Mode)
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 (Sas) shall be:
Saa s 0.66 W + 62%
with a clamp at l'15% of rated core thermal power and Saa = APRM rod block trip setting in percent of rated thermal power (1998 MW).
W=
Percent of drive flow required to produce a rated core flow of 69 Mlb/hr.
COLR REVISION 12A PAGE 7 OF 26
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PILGRIM NUCLEAR POWER STATION j
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
2.2 APRM Rod Block Trio Settina (Run Mode) (Contin =d)
The APRM rod block trip setting is valid only for operation using two i
recirculation loops. Operation with one recirculation loop out of service is i
restricted by License Condition 3.E.
2.3 End Block Monitor Trio Settinn i
2 Reference Technical Soecification: Table 3.2.C-2 i
Allowable values for the power-dependent Rod Block Monitor trip 4
setpoints shall be:
Reactor Power, P Trip Setpoint
(% ofRated)
(% ofReferenceIEvell P s 25.9 Not applicable (All RBM Trips Bypassed) 25.9 < P s 62.0 120 62.0 < P s 82.0 115 82.0 < P 110 The allowable value for the RBM downscale trip setpoint shall be 2 94.0%
of the reference level. The RBM downscale trip is bypassed for reactor power s 25.9% of rated.
COLR REVISION 12A PAGE 8 OF 26 i
m
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.0 CORE OPERATING LIMITS
{
3.1 Averane Planar Linear Heat Generation Rate (APLHGR) l Reference Technical Snecification: 3.11.A During power operation, APLHGR for each fuel type as a function of axial location and average planar exposure shall not exceed the applicable i
limiting value. The applicable lirsting value for eac,h fbel type is the smaller of the flow-and power-dependent APLHOR limits, MAPLHGRr l
and MAPLHGR,. The flow-dependent APIJIGRlimit, MAPLHGRr,is the product of the MAPLHOR Sow factor, MAPFACr, shown in Figure 3.1-6 and the MAPLHGR for rated power and flow conditions. The 4
power-dependent APLHGR limit, MAPLHGRc, is the product of the MAPLHGR power factor, MAPFAC,, shown in Figure 3.1-7 and the MAPLHGR for rated power and flow conditions. The MAPLHGR for rated power and flow conditions for each fuel type as a function of axial location and average planar exposure are based on the approved methodology referenced in Section 5.0 and prograns.cd in the plant process computer. The MAPLHGR for rated power and flow conditions for the limiting lattice in each fuel type (excluding natural uranium) are presented in Figures 3.1-1 through 3.1-5.
The core loading pattern for each type of fuel in the reactor vessel is shown for the present cycle in Figure 4.0-1.
1.2 Linear Heat Generation Rane (LHGR)
Reference Technical Soecification: 3.11.B During reactor power operation, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the limits presented in Table 3.2-1.
i l
)
COLR REVISION 12A PAGE 9 OF 26 s
i
l PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT KTYPE. G4.02 i
Table 3.2-1 LHGR Operatinn Limits l
LHGR Operating Fuel Tvoe Limit (KW/fD 4
BP8DQB323 14.4 BP8HXB355 14.4 BP9 HUB 378 14.4 P9 DUB 408-6G5.0nG4.0 14.4 P9 DUB 408-16GZ1 14.4 i
l COLR REVISION 12A PAGE 10 OF 26
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1 FIGURE 3.1-1 5
Maximum Average Planar Linear Heat Generailon Rate M
(MAPLHGR) for Fuel Type BP8DQB323 l
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my Planar Average Exposure (MWD /ST) wg FIGURE 3.1-2: Max! mum Average Planar Linear Heat Generation g
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FIGURE 3.1-3: Maximum Average Planar Linear Heat Generation y
Rate (MAPLHGR) for Fuel Type BP9 HUB 378
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t Planar AverageExposure (MWD /ST)
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FIGURE 3.1-4: Maximum Average Planar Linear Heat Generation y
Rate (MAPLHGR) for Fuel Type P9 DUB 408-6G5.0/7G4.0 l
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Planar Average Exposure (MWD /ST)
{
FIGURE 3.1-5: Maximum Average Planar Linear Heat Generation g
Rate (MAPLHGR) for Fuel Type P9 DUB 408-16GZ1 l
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R FIGURE 3.1-6 6
I Flow Deperdent MAPLHGR Factor (MAPFAC )
l p
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506 R==d - i s i i l i Itsf < 25%: Me Daninst Manisalse is Regebed (No tamies Speedied)_ E' b V l Q l Far 25E < Pt ASE r P< andh FlowiSOE Rased-i t i MAPFACp= 0.55 +0.005 @-45%) ?- @ 0.3 I For256 s Pt496 P=t and h Pise > SOE # ^ - i g l MAPPACp= 0.50 + 0.006 &-45%) 4-g l Par 25S s Ps45G and Phr h .2 0 I MAPFACp= 1.0 + 0AG52M @- 1006) 2 O i N i i kP>4m m q =1A+ m e-i m i 0.1 I I l l I e i I g m 0.0 0 20 40 "'* b 60 80 100 3 % RA'IED CORE THERMAL POWER (P) j 9., o 1 g9 FIGURE 3.1-7 l Power Dependent MAPLHGR Factor (MAPFAC ) p i PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR) i Reference Technical Soecification: 3.11.C During power operation, the MCPR shall be greater than or equal to the j operating limit MCPR. The operating limit MCPR is the greater of the flow-and power-dependent MCPR operating limits, MCPRr and MCPRe. ? The flow-deper. dent MCPR operating limit, MCPRr, is provided in Figure 3.3-1. For core thermal powers less than or equal to Psy, the power-s dependent MCPR operating limit, MCPRr, is provided in Figure 3.3-2. Above Ps,, MCPRe is the product of the rated power and flow MCPR operating limit presented in Tables 3.3-1 and 3.3-2, and the Ke factor presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value i for Pop. The rated power and flow MCPR operating limits presented in j Tables 3.3-1 and 3.3-2 are functions of t for the indicated MOC and EOC cycle exposures. 4 { The value of t in Tables 3.3-1 and 3.3-2 shall be equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical j Specification 4.3.C, as follows: i j rm - r, j 1.252 - r, Where: Average scram time to tm = l drop out ofNotch 34 4 l [N,e a E.. N' Adjusted analysis mean ta = scram time Nn + 1.65cr = TE,.,N' COLR REVISION 12A PAGE 18 OF 26 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i i 3.3 Minimum Critical Power Ratio (MCPR) (Continued) l Number of surveillance tests performed to date in the n = present cycle N3 Total number of active control rods = Number of active control rods measured in the i* Ni = surveillance test Average scram time to drop *out ofNotch 34 position ti = 1' of all rods measured in the i surveillance test Mean of the distribution for average scram p = insertion time to drop out ofNotch 34 i 0.937 sec = Standard deviation of the distribution for average o = scram insertion time to dropout of Notch 34 i 0.021 sec = COLR REVISION 12A PAGE 19 OF 26 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1 MOC MCPR Ooeratina Limits The MCPR operating limits (OLMCPR) as a function of t for operation from the Beginning of Cycle (BOC) to the End of Cycle (EOC) - 4361 MWD /ST with core flow s107.5% ofrated are: i I OLMCPR M t s 0.0 1.31 0.0 < t s 0.1 1.31 i 0.1 < t s 0.2 1.31 0.2 < t s 0.3 1.31 0.3 < t s 0.4 1.31 0.4 < t s 0.5 1.32 0.5 < t s 0.6 1.33 0.6 < t s 0.7 1.34 0.7 < t s 0.8 1.34 0.8 < t 5 0.9 1.35 0.9 < t s 1.0 1.36 t COLR REVISION 12A PAGE 20 OF 26 l PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 ) 4 TrMe 373-2 ~ EOC MCPR Ooeratinn Limits 2 The MCPR operating limits (OLMCPR) as a function of t for operation from the End of I Cycle (EOC) - 4361 MWD /ST to the EOC with core flow s107.5% ofrated are: I I OLMCPR M t s 0.0 1.36 0.0 < t s 0.1 1.37 0.1 < t s 0.2 1.'J7 0.2 < t 5 0.3 1 38 0.3 < t s 0.4 1 38 0.4 < t s 0.5 1 39 0.5 < t s 0.6 1.40 0.6 < t s 0.7 1.40 0.7 < t s 0.8 1.41 0.8 < t 5 0.9 1.41 0.9 < t s 1.0 1.42 i l COLR REVISION 12A PAGE 21 OF 26
- p l
I I I I I I g. \\ Per F10.40: k b MCPRp=Madneuse(1.21, ApF+B ) g U \\ k b \\ 1.6 Fr F<0.40: \\ \\ \\ McPRp=( ApF+B )(1+0.32(0.40-F)) { y \\ Whem: F= bedenof Ranid Cae Nw \\ \\ Ar =a mp -m.m-ma com _t m g N% h 8 * ": 2 \\ \\ N'\\ ^e "1 2 l \\h los.s .o.57ss 1.sms ( \\ 197A 4.5915 1.7129 s 14 g 112A .o.ans 1.7633 l O, scoop nabe sesposa g 117A .e.6379 1.8259 [ p com== san. / \\ x \\ s u [ h h 4 O 112.0 % 117.0 % g \\ @3 1.2 E I 1.1 2 20 30 40 50 60 'JO 90 90 100 210 COREFIDW(% RATED) M b b FIGURE 3.3-1 p Mew Dependent MCPR Limits (MCPR ) i e F --.- -.. - ~ t e 3.6 i g g g M Operstmg LimitMCPRp a 4~- for Core hw > 50% Rated Operatmg LimitMCPRp =Kp *OtJ4CPR(100) 3 i [ k 3.2 h OLMCPR(100) = 0persing 13mit MCPR Values for 2005 Rased Core 1 hernial Pbwer U 1 Dem Tablem 33-1 and 33-2 { $2 3.0 P= % Rased CoreThermal Power l g= % Rased Core Thermal Power that C@ so sha Seapolut for Bypass of 2.8 i Scran Signals Generased by Closure of Turtdns Soap Velves or Past Closure of.- i i I VerbineControlValves (Meximen Q = 45%) K = Rased MCPR Multipinr as Dermed Below: O 2.6 p 1 f .4-for Core hw 550% Rased 1.imit MCPRp M 2 For P < 255: No Thermal Monisering Is Regidied (No IJslas are Specified) Z h 3 m ] i Par 25% s Ps455 and P
SOS Rased 33 K = 1.28 + OD134 (45% -P) )* ? Par 255sPs455 and P>%vness: p 1.6 i Par 45% < P < 605: Kp = 1.15 +0.00067(80E-P) O -- 1.5 ParP2605: Kp = 1 A + 0.00375 (1905 -P) 7 N i i NI Kp for Pgyp,,,< P S 45% j K p forP>60% i 3 { / i A' N_ / k i I j ' l ' K, for 45% < P< 60% ' f,1 l ^ f.0 p ~ T 20 30 40
- b 50 60 "10 90 90 100 '
% RATED CORE 11IERMALPOWER(P) A Mn FIGURE 3.3-2 Power Dependent MCPR Limits (MCPR ) p e ~ - 0. 1 PILGRIM NUCLEAR POWER STATION 3 PNPS CORE OPERATING LIMITS REPORT R7YPE: G4.02 F 3.4 Power / Plow Relatiomhin Durina Power Ooeration ] m. ,a. ~. ,,e m. Reference Technical Soecification: 3.II.D 1 i The power /dow relationship shall not exceed the limiting values shown on the Power / Flow Operating Map in Figure 3.4-1. 4.0 REACTOR VESSM CORE DESIGN a Referance Tachaial Saaehtion: 5.2 a t l 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 Type CycleLoaded Number 1 4 1 Irradir,ted l BP8DQB323 9 96 ] BP8HXB355 10 140 i BP9 HUB 378 11 136 ( New { P9 DUB 408-6G5.0/7G4.0 12 64 j P9 DUB 408-16GZ1 12 .144 / Total 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid hafnium. /
5.0 REFERENCES
5.1 NEDE-24011-P-A-13 and NEDE-24011-P-A-13-US," General Electric Standard Application for Reactor Fuel", August,1996.
5.2 NEDC-31852-P, " Pilgrim Nuclear Power Station SAFER /GESTR-LOCA Loss-of-Coolant Accident Antlysis", September 1990.
5.3 NEDC-31312-P, " ARTS Improvement Program Analysis for Pilgrim Nuclear Power Station", September 4,1987.
COLR REVISION 1.'!A PAGE 24 OF 26
1 2@
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75 80
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Power / Flow Operating Map i
4 i
PNPS CORE OPERATINGIJMITS REPORT l..,.:..._
_ ggggggggggggy y
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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
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FuelTypes (Cycleleded)
E BP8DQB323 (Cycle 9)
E BP9 HUB 378 (Cycle 11)
E BP8HXB355 (Cycle 10)
E P9 DUB 408-6G5.0nG4.0 (Cycle 12) 3 P9 DUB 408-16GZ1 (Cycle 12)
FIGURE 4.0-1 Reactor Vessel Core Loading Pattern Revision 12A Page 26 of 26