ML20206D897
| ML20206D897 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/22/1999 |
| From: | Mccord R, Mchale J, Robert Wolfgang PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20206D884 | List: |
| References | |
| PECO-COLR-L1R7, PECO-COLR-L1R7-R02, PECO-COLR-L1R7-R2, NUDOCS 9905040274 | |
| Download: ML20206D897 (34) | |
Text
PECO'Nuclocr FuOl & S rvic0c Division PECO-COLR-L1R7 l L1R7 Coro Operating Limits Report Prgo 1, R;v. 2 CORE OPERATING LIMITS REPORT FOR LINERICK GENERATING STATION UNIT 1 REI4AD 7, CYCLE 8
{
1 f!f8!ff Prepared By:
M Date:
f f
/f f
]
Robert J. Wolfgang Engineer I
Reviewed B Mn,,r )l.aM2/eDate:_f/ 2/95 6e U
l John La. McHale Independent Reviewer Reviewed By:
[A Date: Y/o70/99 Richard D. McCord Independent Reviewer Approved By M
Date: Y 2,
9
(/ ~
G r
James M. Carmody Manager Nuclear Design & Materials Branch 9905040274 990427 PDR ADOCK 050
- 3J2, p
PECO'Nucicar Fu01 & Servic30 Divicien PECO-COLR-L1R7 l LlR7 Coro Operating Limita Report Psgo 2, Rev. 2 LIST OF EFFECTIVE PAGES Page(s)
Revision l
1 - 26 i
2
}
i i
t I
t
\\
l i
1
PECd Nuclear FuOl & Servicca Diviaicn 4
PECO-COLR-LlR7 l LlR7 Caro Operating Limito R: port Pcgo 3, Rsv. 2 INTRODUCTION AND St2+fARY
, This, report provides the following - cycle-specific parameter limits for - Limerick Generating Station Unit 1 Cycle 8 (post failed fuel outage, IM32):
- Maximum Average Planar _
Linear Heat Generation Rate (MAPLHGR)
Minimum Critical Power Ratio (MCPR)
- ARTS MCPR thermal limit adjustments and multipliers ARTS MAPLHGR thermal limit multipliers Rod Block Monitor (RBM) data
.MAPLHGR single loop operation (SLO) reduction factor Linear Heat Generation Rate (LHGR)
Turbine Bypass Valve parameters Recirculation Pump Motor Generator (MG)
Set Scoop Tube Stops Reactor Coolant System Recirculation Flow Upscale Trips These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.
This report'is submitted in accordance with Technical Specification 6.9.1.9 of Reference 1.
in accordance with PECO Nuclear, Preparation of this report was performed Fuel & Services Division Procedure EM-300.
The data presented in this report is valid for all points and domains on the operating map, including:
- Maximum Extended Load Line Limit (MELLL) down to 81% of rated core flow during full power operation Increased Core Flow' (ICF) up to 110% of rated core flow Feedwater Temperature Reduction (FWTR) up to 105'F during e
cycle extension operation e Feedwater Heater Out-of-Service (EWHOOS) up' to 60'F feedwater _ temperature reduction at any time during the cycle prior to cycle extension.
Further information on the cycle > specific analyses for Limerick 1 Cycle ~ 8 and their associated operating domains is available in References 2, 15, 17 and 19. Additional information on the inputs used in performing - the Limerick 1 Cycle 8 specific analyses are available in References 3 and 4.
i
PECd Nucicer Fuol & Sorvicca Divioion PECO-COLR-L1R7 l L1R7 Coro OperOting Limits R: port Pag 3 4, R^v. 2 MAPLHGR LIMITS L
I The limiting MAPLHGR value for the most limiting lattice
)
(excluding natural uranium) of each fuel type as a function of
)
average planar exposure is given in Figures 1 through 8.
These j
figures are used when hand calculations are required as specified in Technical Specification 3.2.1.
The MAPLHGR limit curves of Figures 1 through 8 were generated from References 5 through 8.
No reduction in MAPLHGR limits is required under ARTS during single loop operation (Table 3).
The use of the single loop reduction factor, specified in Table 3, is documented in Reference 1
2.
MCPR LIMITS The MCPR value for use in Technical Specification 3.2.3 is
{
given in Table 1.
This table is derived from the Reference 2 analysis and is valid for all Cycle 8 fuel types and operating domains.
Information regarding the treatment of these MCPR limits i
for SLO is also provided.
Bounding MCPR values are also provided for inoperable Recirculation Pump Trip (RPTOOS) and/or inoperable Steam Bypass System (TBVOOS).
These two options represent the Eqpipment Out of Service (EOOS) condition.
Note that in Table 1 the term " EOR" refers to the cycle exposure at which operation at " rated conditions" is no longer possible (i.e.,
the cycle exposure at which cycle extension begins).
The cycle exposure which represents " EOR" is given in the latest. verified and approved Cycle Management Report.
This value can change during the cycle due to changes in operating strategy.
ARTS THERMAL LIMIT ADMINISTRATION ARTS provides for power-and flow-dependent thermal limit adjustments and multipliers which allow for a more reliable administration of the MCPR and MAPLHGR thermal limits.
The flow-dependent multiplier MAPFAC (F) and flow-dependent adjustment MCPR (F) are sufficiently generic to apply to all fuel types and operating domains, including SLO. However, there are two sets of power-dependent MAPLHGR multipliers for with-and without-EOOS conditions.
- Also, there are two sets of power-dependent MCPR adjustments and multipliers for with-and without-EOOS conditions.
The power dependent MAPLHGR multipliers and power dependent MCPR adjustments / multipliers are sufficiently generic to permit both two recirculation loop operation and SLO in the operating domains specified.
I
PECd Nucicer Fu 1 & S rvic0c Divisien p
l-L1R7 Coro Operating Limito R port PECO-COLR-L1R7 Pag 3 5, R0v. 2 The ARTS adjustments and multipliers are shown in Figures 9 through 14.
Thermal. limit monitoring must be performed with the l
more limiting MCPR and MAPLHGR limits resulting from the power-and
.flowebiased calculation.
The use of ARTS multipliers shown in Figures 9 through 14 is documented in References 9 through 11, 16,
{
l 18, and 20.
)
ROD. BIDCK MONITOR SETPOINTS I
The ARTS RBM provides for power-dependent RBM trips.
The trip setpoints/ allowable values and applicable RBM signal filter time constant data. are shown in Table 2. These values are for use with Technical Specification 3.3.6.
The use of the setpoints specified in Table 2 is documented in References 2, 9,
12, and 13.
LINEAR HEAT GENERATION RATES The maximum LHGR value for each fuel type for use in Technical Specification 3.2.4 is given in Table 4.
The LHGR is an exposure dependent value.
Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4.
The LHGR data is listed in Reference 5. (GE proprietary).
1 STEAM BYPASS SYSTEM OPERABILITY i
The operability requirements for the steam bypass system for
}
in Technical Specifications 3.7.8 and 4.7.8.C are found in use Table 5.
If these requirements cannot be met, the MCPR, MCPR(P) and MAPTAC(P) limits for inoperable Steam Bypass System, known as i
Turbine Bypass Valve Out Of Service (TBVOOS), must be used. The turbine bypass valve parameters of Table 5 are documented in References 3 and 4.
RECIRCULATION PUMP TRIP OPERABILITY
'If the recirculation pump trip is inoperable, then the MCPR, MCPR(P) and MAPFAC(P) limits for Recirculation Pump Trip Out Of Service (RPTOOS),
must be used.
Further information about the l
'RPTOOS condition is available in References 9 and 11.
RECIRCULATION PUMP MOTOR-GENERATOR (MG) SET SCOOP TUBE STOPS i
l The electrical and mechanical stops are set to limit the reactor core coolant flow rate during an event in which the recirculation flow rate increases to its maximum value.
Technical Specification Surveillance Requirement number 4.4.1.1.2 requires that _ each pump MG set scoop tube mechanical and electrical stop shall be demonstrated OPERABLE, with overspeed setpoints less than i-'-
or equal to specified values, at least once per 24 months.
The L
l
h[E
.PEC5 Nuclect Fu:1 & SOrvicto Divicicn l L1R7 Coro Operating Limito R port PECO-COLR-L1R7 i
Pcg3 6, Rav. 2 settings of these stops may be changed during the cycle in accordance with changes in operational strategy.
These values are cycle-specific and can be found in Table 6 of this COLR.
Further information as to how the MG set limiting setpoints relate to other parameters in the. Technical Specifications and COLR may be obtained l
from References 9 through 11.
j.
1 CONTROL ROD BIDCK INSTRtMENTATION
[
REACTOR COOLANT SYSTEM RECIRCULATION FIDW UPSCALE TRIP
)
1 Technical Specification Limiting Condition for Operation number 3.3.6 requires control rod block instrumentation channels shall. be OPERABLE with their ~ trip setpoints consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2.
The Reactor Coolant. System Recirculation Flow
- Upscale -Trip is a cycle-specific value and as such is found in Table 7 of this COLR.
Table 7' lists the Nominal Trip Setpoint and Allowable Value.
These setpoints are set high enough-to allow full
{
utilization of the enhanced ICF domain up to 110% of rated core flow.
Further details on these setpoints may be obtained from Reference 14.
j i
l REFERENCES 1.
" Technical Specifications and Bases for Limerick Generating Station Unit 1", Docket No. 50-352, License No. NPF-39.
i 2.
" Supplemental Reload Licensing Report for Limerick Generating Station Unit 1 Reload 7 Cycle 8",
General Electric Company Document No. Jll-03191SRLR, Rev. O, March 1998.
i' 3.
Letter, R. M. Butrovich to J. M. Carmody, " Limerick 1 Cycle 8 i
~ Resolved OPL-3 Revision 1", December 2, 1997.
4.
Letter, R. M. Butrovich to J. M. Carmody, " Limerick 1 Cycle 8 Resolved OPL-3 and Revised FRED Form", November 21, 1997.
- 5.
" Lattice Dependent MAPLHGR Report for Limerick Generating l
Station Unit 1 Reload 7 Cycle 8",
General Electric Company l
Document No.
J11-03191 MAPL, Rev.
O, March 1998 (GE proprietary).
6.
" Lattice Dependent ~ MAPLHGR Report for Limerick Generating Station Unit 1 Reload 6 Cycle 7",
General Electric Company
. Document No. 24A5185AA, Rev. O, ' January 1996 (GE proprietary).
.7.. - Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 1 Reload 5 Cycle 6",
General Electric Company Document No. 23A7232AA, Rev.1, July 1995 (GE proprietary).
L
' PECO Nuclear Fuol & ScrvicOs Divicion PECO-COLR-L1R7 l L1R7 Coro Operating Limito Report Pr.g3 7, Rsv. 2 7
- 8..
" Lattice Dependent MAPLHGR Report for Limerick Generating a
l Station Unit 2 Reload 2 Cycle 3",
General Electric Company
{
Dccument No. 23A7200AA, Rev. 3, July 1994 (GE proprietary).
9.
" Maximum Extended Load Line Limit and ARTS Improvement Program i
Analyses for Limerick Generating Station Units 1 and 2",
GE Nuclear Energy Document'No. NEDC-32193P, Rev.2, October 1993.
i
- 10. Letter, G.
V.
'Kumar to K.
M.
- McGinnis,
" Limerick ARTS
' Application with Equipment Out-of-Service (ECOS) ",
Dec.
10, 1993.
- 11. Letter, R. M.
Butrovich to J. M. Carmody, " Revised Limerick 1 Cycle 8 ARTS Thermal Limits Curves", March 12, 1998.
- 12. " Power Rerate Condition Setpoint Calculations for the Philadelphia Electric Company Limerick Generating Station Units 1 &
2",
GE Document No.
GE-NE-208-20-0993-2, August 1994.
Calculation No. LE-0082, Rev. 5, June 19, 1998.
14.
" Safety Review for Limerick Generating Station Units 1 and 2, 110%
Increased Core Flow-Operation and Final Feedwater Temperature Reduction",
GE Nuclear Energy Document NEDC-32224P, Rev. 1, October 1994.
1
- 15. Letter, R. - M. Butrovich to K.
W. Hunt, " Limerick 1 Cycle 7 Exposure", April 6, 1998.
i
during Limerick l' Cycle 8",
April 10, 1998.
- 17. Letter, P. M. Butrovich to K. W. Hunt, " Limerick 1 Cycle 8 Core Loacing Change", April 30, 1998.
- 18. Letter, J. L. Casillas to G. C. Storey, " Applicability of Flow MCPR Limit to Single Loop Operation", May 5, 1998.
i
- 19. Letter, R. M. Butrovich to K. ' W. Hunt, " Safety Review of the Limerick 1 Cycle 8 Supplemental Reload Licensing Report due'to Licensing Bases Changes", December 10, 1998.
1
--Atomic-Power Station and Limerick Generating Station", NEDC-32847P, June 1998.
(i
' PECO Nucicar Fu:1 & SOrvicca Division PECO-COLR-L1R7 l L1R7 Coro Operating Limito R: port Pcg3 8, Rsv. 2 FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT l
-GENERATION RATE (MAPLHGR) VERSUS t
AVERAGE PLANAR EXPOSURE l
IVEL TYPE P9CTB404-14GZ (GE13) l THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 l
12.0 11.s N
,,e e
~\\
l e.e
\\
e.e
\\
,.e x
i s.e e.e s.e to.e 1s.o me.o as.e me.o as.e 4e.e 4s.e so.e ss.e ee.e AVERAGE PLANAR EXPOeURE (OWd/ST) i Avg Plan Avg Plan Avg Plan F.xposure -
MAPLHGR Exposure MAPLHGR Exposure MAPLHGR t
(GWd/ST)
(kw/ft)
(GWd/ST)
(kw/ft)
(GWd/ST)
(kw/ft) 0.0 10.53 10.0 12.12 40.0 8.96 1.0 10.74 12.5 12.13 45.0 8.31 2.0 10.93 15.0 11.99 50.0 7.64 3.0 11.14 17.5 11.74 55.0 6.94 4.0 11.30 20.0 11.43 57.35 6.60 5.0 11.44 25.0 10.81 6.0 11.59 30.0 10.19 8.0 11.90 35.0 9.58 f
i
PECO Nucicar Fu01 & Servicoo Division PECO-COLR-L1R7 l L1R7 Cora Operating Limita R0 port Pago 9, Rcv. 2 FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE INJEL TYPE P9 CUB 384-12GZ (Gell)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 i
12.0 j
11.0 w
\\,
10.0 I.0 N x 3 s.0 x
7.0 N N 0.0 0.0 0.0 10.0 18.0 20.0 26.0 30.0 35.0 40.0 48.0 50.0 85.0 00.0 AVERAGE PLANAR EXPOSURE (OWd/ST)
Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)
(kwlft)
(GWd/ST)
(kwlft)
_ GWd/ST)
(kwlft)
(
0.0 10.46 17.5 11.41 55.0 6.72 2.0 10.75-20.0 11.10 56.1 6.56 4.0 11.03 25,0 10.50 6.0 11.33 30.0 9.91 8.0 11.63 35.0 9.31 10.0 11.91 40.0 8.71 12.5 11.90 45.0 8.08 15.0 11.71 50.0 7.41
PECO Nuc1ctr FuOl & S rvicca Divicion PECO-COLR-L1R7 l L1R7 Coro Operating Limito R: port Pcg3 10, Rsv. 2 FIGURE 3 MAXIM.24 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 331'-9G5.0 (GE11-LGS 1 Reinsert)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 N
,,'0 f 11.0 s
\\
10.0 10.0 x N \\
0.0
,.0
.\\
0.0 0.0 8.0 10.0 18.0 20.0 20.0 30.0 88.0 40.0 45.0 80.0 88.0 04.0
.WS Planar haposure (Ged/ST)
Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHOR Exposure MAPLHOR (GWd/ST)
(kwlft)
(GWd/ST)
(kwm)
(GWd/ST)
(kw/ft) 0.0 11.76 -
12.5 12.67 35.0 9.95 2.0 12.01 15.0 12.39 40.0 9.30 4.0 12.16 17.5 12.08 45.0 8.62 6.0 12.32 20.0 11.77 50.0 7.90 6.0 12.49 25.0 11.17 55.0 7.16 10.0 12.67 30.0 10.57 58.7 6.52
PECO Nuclear FuG1 & SsrvicO3 Divicion PECO-COLR-L1R7 l L1R7 Coro Operating Limits Report Pago 11, Rtv. 2 l
FIGURE 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPES: P8CIB219-4GZ-100M and P8CIB219-4GZ-80M (GE6)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 110 11.0 4
h 10.0 l
s.0
.0 1.0 6.0 0.0 6.0 10.0 15.0 20.0 25.0 30.0 10 AvrRAoE PLANAR EXPOSURE (OWWST)
Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)
(kwm)
(GWd/ST)
(kwm)
(GWd/ST)
(kw/ft) 0.0 11.90 5.0 12.00 20.0 11.80 0.2 11.90 10.0 11.90 25.0 11.60 1.0 11.90 15.0 11.90 30.0 11.20
PECO Nuclear Fu 1 & S0rvic0c Division PECO-COLR-L1R7 l L1R7 Coro Operating Limits Report Pcgs 12, R0v. 2 FIGURE 5 MAXIMLR4 AVERAGE PLANAR LINEAR HEAT
' GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P8CIB176-4GZ-80M (GE6)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.o 12.o 11.o t o.o o.o o.o 7.o s.o c.o s.o io.o is.o so.o 2s,o so.o ss.o AVERAGE PLANAR EXPOSURE (GWd/ST)
Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)
(kw/ft)
(GWd/ST)
(kwm)
(GWd/ST)
(kwm) 0.0 11.80 5.0 12.00 20.0 11.90 0.2 11.80 10.0 12.00 25.0 11.70 1.0 11.90 15.0 12.00 30.0 10.80 L
PECO NucicSr FuO1 & SOrvicOO Divicion PECO-COLR-L1R7 l L1R7 Cero Operating Limite Rcport Pago 13, R0v. 2 FIGURE 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE EUEL TYPE P9CTB412-13GZ (GE13)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 -
12.0 11.0 N
F
\\
1,,,,
N I s.0 N
s.O N
7.0
'\\
.0 0.0 5.0 10.0 15.0 20.0 28.0 30.0 36.0 40.0 45.0 60.0 54.0 00.0 AVERAGE PLANAA EXPOSURE (GWd/ST)
Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)
(kw/ft)
(GWd/ST)
(kw/ft)
(GWd/ST)
(kw/ft) 0.0 10.89 7.0 11.92 25.0 10.95 0.2 10.95 8.0 12.02 30.0 10.33 1.0 11.04 9.0 12.12 35.0 9.71 2.0 11.18 10.0 12.21 40.0 9.08 3.0 11.33 12.5 12.20 45.0 8.44 4.0 11.49 15.0 12.08 50.0 7.76 5.0 11.65 17.5 11.88 55.0 7.06 6.0 11.78 20.0 11.58 57.9 6.63 i
fl PECO Nuclocr FuS1 & Ssrvicco Divicien PECO-COLR-L1R7 l L1R7 Coro Operating Limito R port Pega 14, Rev. 2 FIGURE 7 MAXIMtM AVERAGE PLANAR LINEAR HEAT i
' GENERATION RATE (MAPLNGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9CTB413-14GZ (GE13)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 l
l 13.6
/
12.o
/
\\
,,.e '
N I o.e
\\
t A
N s.e i
s.e l
}
1.e
\\
i I
s.e o.e s.o is.e is.e 20.s 25.e so.e as.e 40.0 4s.e so.o ss.e sc.o AVERAGE PLANA A EXPoeVRE (OWdleT)
Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)
(kw/ft)
(GWd/ST)
(kw/ft)
(GWd/ST)
(kwm) 0.0 10.76 7.0 11.90 25.0 10.95 0.2 10.83 8.0 12.01 30.0 10.33 1.0 10.97 9.0 12.11 35.0 9.71 2.0 11.18 10.0 1121 40.0 9.08 3.0 11.34 12.5 12.19 45.0 8.44 J0-11.50 15.0 12.07 50.0 7.76 5.0 11.66 17.5 11.87 55.0 7.06 6.0.
11.78 20.0 11.58 57.9 6.63 u
e t
PECO Nucicar Fuci & S rvic;g Divisicn PECO-COLR-L1R7
\\ L1R7 Coro Operating Limits RIport Psgs 15, R0v. 2 FIGURE 8 MAXI 14N AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS i
AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 354-12GZ2 (GE11-LGS 2 Reinsert)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.o 12.0 N
ti.e
\\
j 10.o
\\
s.o
,N s.e
\\ \\
7.0 x
o.o s.e 10.o 1s.0 20.e 2s.o ao.e as.e 40.o 45.o so.o ss.o so.e Anersee Moser tapesare towesT)
Ava Plan Avg Plan Avg Plan eem haruna y-aswusa e
wousa o-(et2/ST)
Dor /ft)
(Gef/ST)
(kw/ft)
(sti/3T)
Otw/ft) 0.0 11.05 7.0 11.98 25.0 10.89 0.2 11.09 8.0 12.13 30.0 20.27 1.0 11.19 9.0 12.30 35.0 S.55 2.0 11.31 10.0 12 42 40.0 E.87 3.0 11.44 12.5 12.38 45.0 t'.24 4.0 11.56 15.0 12.10 50.0 7.62 5.0 11.70 17.5 11.79 55.0 7.00 6.0 11.84 20.0 11.49 57.85 6.60
PECO Nucicar Fuol & S rvicsc Division PECO-COLR-L1R7 j L1R7 Coro Operating Limita Report Pago 16, R0v. 2 l
FIGURE 9 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.2 LO W
g 0 8" N
0.63 1 06 5 00% Flow MAPLHGR(P) = MAPFAC(P)
- MAPLHGRetd 0.53 g 0.55 MAPLHGRetd = Standard MAPLHGR Umits I
0.43,
l For 25% > P : No Thermal Umits Monitoring Required i
F 0^4
No Umits Specified
> 60% Flow j
j For 25% i P < 30% : MAPFAC(P) = 0.55 + 0'wo4(P.30%)
a For100% Core Flow i
MAPFAC(P) = 0.50 + 0.004(P. 30%)
dL For > 60% Core Flow 0.2
j j
For 30% 5 P :
MAPFAC(P) s 1.0+ 0.005224(P 100%)
l 0.0 i
l 0
2 2
2 E
E W
W M
M i
Power (% Rated)
PECO Nucicar Fuci & SOrvicac Divicion PECO-COLR-L1R7 l L1R7 Coro Operating Limits R: port Paga 17, REv. 2 FIGURE 10 PCHER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE IS VALID FOR RPTOOS AND/OR TBVOOS OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.2 1.0-'
g.e-'O.84...................................................................................................
i 0
!iw 0.6
~ 0% Rm
<6 N9 Nm
- N Qo*
MAPLHGRed a W MAPLHOR Umm
- 0.53 0.48 Fw M > P:NoThund Umm Marertrg Rossed 0.4-'
- 0.40 Noumm 8peceed 0.35 Fa 25% 3 P
- M: MACP)
- 0 $3 + GM P.M)
Fw$00%CareFlow a:
> 60% Row MAPFACP) e G4 + am P.3mq 0.2
Fw > 00% Care Flos Fa 30% $ P : MAPFACP)
- G84 + a00414 P.100%)
I 0.0 0
20 2) 30 40 50 60
'JO ilo 90 200 Power (% Rated)
O
F;-
PECO Nuc1 car Fuel & Servicco Division PECO-COLR-L1R7
'l L1R7 Caro Operating Limits R: port Pego 18, Rcv. 2 FIGURE 11 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F) l THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.1 1
LO t
g 0.9 i
u OA E.
g g 0.7 u4euan.uapF4Ce uaeuaeid For Two Loop Operstm n 70% We g
MApFAC(F) = The Maumum of EffHER 1.0 g
CR p.0288 x (W,.70F10 + 0 9732)
- a. 0.6 g
For he Leap opervem s 70% Wr MAPFAC(F) e p 0002 x (W/100) + 0 5066) 0.5 WT = % Roted Core Flow QA 30 e
!D E
'm W
SO 2D 230 Core Flour (% Rated)
?
I 1
l
PECO.NuclCar FuOl & Servicso Division PECO-COLR-L1R7
.l L1R7 Coro Oparating Limits Report Paga 19, Rsv. 2 l
TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)
Use in conjunction with Figures 12, 13, and 14.
- This table is valid for two-loop ot eration.
Add 0.02 to the OINCPR when in Single Loop Operation.
This table is valid for all Cycle 8 fuel types.
This table is referred to by Technical Specification 3.2.3.
TBV In Service TBV Out of RPT Out of Service and Service RPT In Service Opt. B Opt. A Opt. B Opt. A Opt. B Opt. A (Tau =0)
(Tau =1)
(Tau =0)
(Tau =1)
(Tau =0)
(Tau =1)
BOC TO-
)
EOR -
1.31 1.34 1.37 1.40 1.39 1.44 2000 mwd /ST EOR -
)
2000 1.35 1.38 1.42 1.45 1.43 1.51 mwd /ST to EOC Notes:
- 1. When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.
- 2. Applicable domains for this table are: RCF, ICF, MELLL, WHOOS, EWTR, RPTOOS, TBVOOS, and SLO (with corrections as discussed above).
n-PECO Nuclect Fusi & Scrvicca Division PECO-COLR-L1R7 l L1R7 Coro Operating Limita R! port Pags 20, R0v. 2 FIGURE 12 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS, AND EWTR OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.0 CPERATING LMT MCPR(P) = Kp
- CPERATING Uh8T MCPR (100) 2.8 FOR P
- 25% : NO THERMAL LMT MCNTORIPC REQUIRED 2.M NOUMTS SPEOPIED
> 60% FIL1 2.6 l
PcR 2s%
- P * % > = m) 2%l Kp = lMbyp + 0.032 00%. P)] / OLMCPR(1tg
@ 2.4 gv Mbyp = 220 PCR
- 80% CORE PLON
= 2,72 POR
- 80% CORE PLCW
<60% Flow
.D i
g vi PcR m 3P*46%* Kp = 1.28 + 001M (m. P)
POR 48% 3 P
- 80% : Kp = 1.15 + 0.00a67(80%. P)
- u. 2.0~
pog,,gsp g,,,,, g,an37343% p)
Assouns
$ L8 MPUM s
1.
l l
j L6-j l
=
g L4"
$^l zA L2--
E O.
30 2) 30 40 5D 60 W
80 90 20 Power (% Rated) 3 i
PECO Nuclocr Fuol & Ssrvicas Division PECO-COLR-L1R7 l L1R7 Coro Operating Limite R port Pcgo 21, Rev. 2 FIGURE 13 POWER DEPENDENT MCPR LIMIT ADJUSINENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR RPTOOS AND/OR TBVOOS OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.8 3.
3.6 CPERA11NG LA4TMCPR (P) = Kp
- CPERAT1NG LAINCPR (1c@
3.4
- > 60% Rm ['
3.36 P " " ' *8" " " '#'I "I "" ""'
NO Uh4TS SPEOP1ED
~ 3.2
{
{
,c,,,,,,,,,p,,,,,
(,,,,,,, 3,,)
3.0 j
j xp.phyp + acaq30%.Pj / CLMCPR(10@
2.8 z.
gvi
%=te Pe = core m gi2.6 i
o a,*,
f:
24s roR= 5 P =
x, t m. aoi= <=. )
16:,
<60% Row 24 Pan es P = so%:
x, 1.is + acose7(son.P) 3 Pom so% 5 P kp 1.o+omps(1com.P) g;,
2.0-'
ABSOUJTE
{
L8 l
mpug s - L6-l
- . g eat L4 2"k L2 4-LO 0
0 30 23 30 40 50 ED 80 90 200 Power (% Rated)
PECO Nuc1Cor Fu31 & Scrvic3s Division PECO-CJLR-L1R7 l L1R7 Coro Operating Limite R port Prgs 22, R v. 2 FIGURE 14 FLOW DEPENDENT MCPR LIMITS HCPR(F) 1 THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS (INCLUDING SLO AND TWO RECIRCULATION LOOP OPERATION)
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 22 O
For Two Loop operanon, SLMCPR1112,140% Wr MCPR(F) = Tre Mauernan of EITHER 125 CR ( 45764 x (Wv100) + 13073) 1.E For Two Loop Operanorg SLMCPR 11.12,
- 40% We MCPR(F) e ( 45784 x (WW100) + 1.7073} x (1 + 0.0032 r (40.Wr)}
4 W, a % Rated Core Flow C bE g E
E 1.m--
j gg 12 12 12 30 e
!D 5
90 100 11 0 Core Flow (% Rated)
PECO Nuclosr Fu:1 & S rvicas Division l L1R7 Coro Opersting Limits Report PECO-COLR-L1R7 Paqs 23, Rev. 2 I
TABLE 2 ROD BLOCK MONITOR DATA l
l t
Nominal Trip Satpoint Allowable Value l
LTSP 117.1 %
118.3 %
{
i ITSP 112.3 %
113.5 %
I HTSP 107.3 %
108.5 %
j l} TSP 92%
89%
l l
I
~
These setpoints are based on an RWE Rated MCPR limit of 1.31 and are consistent with an RBM filter time constant between 0.1 seconds and 0.55 seconds.
l LTSP -
Low trip setpoint ITSP -
Intermediate trip setpoint HTSP-High trip setpoint DTSP -
Downscale trip setpoint L
r PECO Nuclecr Fucl s. Strvicsa Division PECO-COLR-L1R7 l L1R7 Coro Opernting Limits Report Pega 24, Rev. 2 i
TABLE 3 l
MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR SLO reduction factor = 1.00 for all Cycle 8 fuel types.
TABLE 4 Linear Heat Generation Rate Limits Fuel Tvon Maximum LHGR (kW/ft)
GE13 14.4 GE11 14.4 GE6 l
13.4 NOTE: The LHGR is an exposure dependent value. Due to the preprietary nature of these values, only the maximum LHGR for each fuel type is provided in Table 4. The LHGR data is provided in Reference 5. (GE proprietary).
l
[
L
-PECO Nuclear Fusi & Servic2s Division PECO-COLR-L1R7 l L1R7 Coro Operating Limits Report Pega 25, Rsv. 2 l
TABLE 5 1
TURBINE BYPASS VALVE PARAMETERS L
i TURBINE BYPASS SYSTEM RESPONSE TIME l
I Maximum delay time before start of 0.10 sec bypass valve opening following generation of the turbine bypass valve flow signal Maximum time after generation of a 0.30 sec
(
turbine bypass valve flow signal for bypass valve position to reach 80% of full flow (includes the above delay time)
MINIMUM REQUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY l
Number of valves = 7
(
l l
f
F PECO Nuclocr Fuol'& ScrvicOc Division l L1R7 Ccro Oporating Limito Report PECO-COLR-L1R7 Pago 26, rov 2 l
1 l
1 TABLE 6 i
-Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops Mechanical 5 114%
Electrical 5 112%
1 i
l TABLE 7 l
Control Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip-
)
i i
Nominal Trip Setpoint s 113.4%
t Allowable Value s 115.6%
l l
l l
50 59 Review for Revision 2 of LGSI. C8. COLR: Rev. 0 10CFR50.59 REVIEW FOR REVISION 2 OF THE CYCLE 8 CORE OPERATING LIMITS REPORT LIMERICK GENERATING STATION UNIT 1 REVISION O 1.
SUBJECT This review discusses the acceptability of the Core Operating Limits Report (COLR),
Revision 2, for Limenck Generating Station (LGS) Unit 1 Cyde 8. This COLR revision is necessary due to the incorporation of revised ARTS flow-dependent MCPR and MAPLHGR thermallimit curves for off-rated flow conditions. These new curves were developed assuming the turbine bypass system is out-of-service (TBVOOS) with a newly analyzed concurrent event of a single recirculation pump runout. However, the curves are valid for all operating conditions, induding single loop operation (SLO). Reference 1 provides the basis for the generation of these revised ARTS flow-dependent MCPR and MAPLHGR thermal limit curves.
The fle.v dependent MCPR and MAPLHGR limits were previously established on a generic basis which sufficently covered all fuel types and operating domains, induding Single Loop Operation (SLO) (Ref. 2). The historical design basis event for MCPR(f) and MAPFAC(f) limits is the slow recirculation flow runout of both pumps to the maximum core flow as limited by the mechanical scoop tube setting. The fuel thermal margin requirements for this event were based on the total change in the core thermal power and core flow excursion experienced during this slow transient event.
At present, Reference 1 now establishes plant specific, cyde-independent, flow-dependent
. MCPR and MAPLHGR limits based on the single recirculation pump runout for LGS. This analysis also evaluates a single recirculation pump runout with the bounding assumption of TBVOOS and establishes plant-specific, cyde-independent MCPR and MAPLHGR limits for LGS, which necessitates a revision to the Lim *: 1 Cyde 8 COLR. Based on the new single-loop recirculation pump runout analysis, there wauld exist excessive conservative margin if the current MCPR(f) and MAPFAC(f) curves based on a dual loop runout were keptin place.
The revised ARTS flow-dependent MCPR a xi MAPLHGR thermal limits curves are as follows:
(i)
COLR ngure 11, Flow Dependent MAPLHGR _ Multiplier MAPFAC(f) (Valid for all operating domains).
(ii)
COLR Figure 14, Flow Dependent MCPR Umits MCPR(f) (Valid for all operating domains).
(iii)
.COLR Table 6. Revised Pump Motor-Generator (MG) Set Scoop Tube Stops.
There are no other changes to the other ARTS-based thermal limit curves (or any other
-values) from Revision 2 of the COLR.
Page 1 of 8
50 59 Review for Revision 2 of LGSI. C8. COLR: Rev 0 The ARTS-based power and flow-dependent MCPR and MAPLHGR thermallimits curves within the COLR are clearty marked so that the appropriate curve may be selected in accordance with the operating condition. Administrative controls exist to ensure that plant personnel utilize the appropriate limits within the 3-D MONICORE system based upon plant operating conditions.
As a result of the changes noted above, a revision to the process computer databank is required. This change will be implemented through A/R #A1151947, Evaluation #9.
l The following Determination condudes that a Safety Evaluation is required for the activity of revising the COLR to incorporate the revised ARTS flow-dependent MAPLHGR and MCPR thermal limits curves. The Safety Evaluation for this activity condudes that it does not constitute an Unrevieweo Safety Question, 11.
50.53 DETERMINATION The Technical Specification Sections (induding all accompanying Bases) applicable to this actmty are: 2.1 Safety Umits (SLs), 3.2.1 Average Planar Unear Heat Generation Rate (APLHGR), 3.2.3 Minimum Critical Power Ratio (MCPR), 3.4.1 Recirculation Loops, 3.7.8 Main Turbine Bypass System, and 6.9.1.9 to 6.9.1.12 Core Operating Umits Report.
The portions of the SAR applicable to this activity are: Chapter 4 Reactor, Chapter 15 Accident Analyses, Appendix A to the Operating Ucense (Technical Specifications),
GESTAR 11 (Ref. 3), and the Supplemental Reload Ucensing Report (Ref. 4).
1.
Does the activity involve a Technical Specifications change or other Facility Operating License amendment?
The incorporation of revised ARTS flow-dependent MCPR and MAPLHGR thermal limits curves does not require a Technical Specification change or other Facility Operating Ucense amendment. The flow-dependent thermallimits curves are based upon GE analyses (Refs.1 and 2) and are incorporated in the COLR, Rev. 2. The Technical Specifications (TS) refer to the COLR for these parameters.
Administrative contmls ensure that the correct flow-dependent curves are utilized in the 3-D MONICORE system to calculate thermal limits.
2.
Does the activity make changes to the facility as described in the SAR?
HE The proposed changes require a revision to the Umerick Unit 1 Cycle 8 COLR.
Since the COLR is a SAR document, required by Technical Specification 6.9.1, the actmty of changing the COLR to incorporate revised flow-dependent MAPLHGR and MCPR thermal limits curves changes the facility as described in the SAR.
3.
Does the activity make changes to procedures as described in the SAR?
The incorporation of revised flow-dependent MAPLHGR and MCPR thermal limits curves to allow for administration of thermal limits does not make changes to Page 2 of 8
50 59 Review for Revision 2 of LGS 1. C8. COLR: Rev. O procedures as described in the SAR. Site procedures are currently in place to ensure that the appropriate ARTS flow-dependent thermal limits curves are utilized to calculate thermal limits at off-rated flow conditions and do not need to be changed as a result of this COLR revision.
4.
Does the activity involve tests or experiments not described in the SAR?
NJ This actmty does not involve tests or experiments not described in the SAR. There are no new tests e experiments involved with implementation of the revised ARTS flow-dependent thermal limits curves for Limerick Unit 1 Cycle 8.
Ill. 50.59 SAFETY EVALUATION The activity to be considered by this Safety Evaluation is the revision of flow-dependent ARTS curves in the Limerick Unit 1 Cycle 8 COLR.
A.
The accidents previously evaluated in the SAR which are potentially impacted by this actne are the Anticipated Operational Occurrences (AOOs) specifically analyzed for each operating cycle in the Supplemental Reload Ucensing Report (Ref. 4). The AOOs considered are as follows: a) Load Rejection without Bypass; b) Turbine Trip without Bypass; c) Feedwater Controller Failure; d) Inadvertent High Pressure Coolant Injection; e) Loss of Feedwater Heaters; f) Rod Withdrawal Error, g) idle Loop Startup; and, h) Recrculation Flow Runout (slow and fast increase). All other UFSAR AOO events are bounded by these cases.
Reference 1 evaluates theJmpact of a single loop runout event with TBVOOS on the AOOs. This event bounds all other operating domains and establishes plant-specific, cycle-independent MCPR(f) and MAPFAC(f) limits.
A.1.
?.4ay the proposed activity increase the probability of occurrence of an accident previously evaluated in the SAR7 N_Q The incorporation of revised flow-dependent MAPLHGR and MCPR thermal limits curves to allow for administraton of thermal limits will not increase the probability of occurrence of an sciMent previously evaluated in the SAR. The COLR, and hence the revised ARTS curves to be incorporated into Revision 2 of the COLR, provide the required operating limits to ensure the probability of an accident is bounded by the SRLR (Ref. 4). The revised ARTS limits were determined using GE's standard and NRC approved evaluation methodology (Ref 3) and therefore maintain the validity of the plant design and licensing basis. Operation within the limits identified in the COLR ensure that the probability of an accident previously evaluated in the SAR will not be increased.
i Page 3 of 8
50 59 Review for Revision 2 of LGS 1. C8. COLR: Rev. O A.2.
May the proposed actnnty increase the consequences of an accident previously evaluated in the SAR7
.N_Q.
The purpose of the thermal limits presented in the COLR is to limit tota' bundle power and local bundle power so that the consequences of accidents evaluated in the SAR remain bounded by the SAR analysis safety limits. The thermal limits documented in References 1, 2, and 4 were calculated using NRC-approved methods and will ensure that the consequences of accidents previously evaluated in the SAR are not increased. The flow-dependent MCPR and MAPLHGR thermal limits curves specified in Revision 2 of the COLR allow for administration of thermal limits at off-rated flow conditions. The NRC-approved calculational methods and thermal limit bases have not changed. Thus, there is no potential for an increase in the consequences of any accident previously evaluated in the SAR.
A.3.
May the proposed activity create the possibility of a different type accident than any previously evaluated in the SAR?
N_Q The possibility of an accident of a different type than any previously evaluated in the SAR will not be created. This COLR revision makes r,o physical changes to plant systems. There is no possibility of the COLR revision creating a different type of accident, or affecting any accident initiators. This is due to the fact that the thermal limits provided in the COLR maintain the validity of the original design basis and have been determined in accordance with NRC-approved licensing criteria. The purpose of the ARTS thermal limits is to ensure that the fuel licensing bases will not be violated during a licensing basis event, while operating within the allowed operating domains of the power and flow operation map. The incorporation of the revised flow dependent MAPLHGR and MCPR thermal limits curves to allow for j
administration of thermal limits is consistent with this purpose. The fuel licensing i
bases are mit by not exceeding the SLMCPR, the Maximum 1% Cladding Plastic j
Strain criterion, and the Fuel Centerline Melt Temperature criterion during AOOs.
l Operation in accordance with the limits specified in the Umerick 1 Cycle B COLR, Revision 2, will ensure that these bases are not exceeded.
B.
The equipment important to safety that is potentially impacted by this change is the nuclear fuel.
4 B.1.
May the proposed actnnty increase the probability of occurrence of a malfunction of Equipment important to Safety previously evaluated in the SAR7 NLQ Revision 2 of the COLR contains the tharmal limit parameters for Limerick 1
'i Cycle 8 which will ensure that all AOOs and accident results are bounded by the SAR ana:ysis safety limits. The purpose of the parameter:s in the COLR is to ensure that the fuel is maintained and operated within the bounding conditions of its design i
and licensing analyses. The revised ARTS cutves were determined based upon the satisfaction of this purpose and therefore are specifically established to ensure that no effect on the probability of occurrence of a malfunction of the fuel will occur.
Therefore, the incorporation of the revised flowdependent MAPLHGR and MCPR thermal limits curves to allow for administration of ihermal limits will continue to Page 4 of 8 i
i 50.59 Revkw for Re"is6n 2 of LGSt CQ. COLR: Rev 0 preserve the design basis integnty of the fuel. Thus, this activity will not increase the probability of occurrence of a malfunction of Equipment important to Safety previously evaluated in the SAR.
B.2.
May the proposed activity increase the consequences of a malfunction of Equipment important to Safety previously evaluated in the SAR7 The methodology used in the calculation of the COLR thermal limit parameters (Ref.
- 3) ensures that the consequences of a malfunction of equipment important to safety will be bounded by the SAR analyses. This same methodology is utilized in the calculation of the revised flow-dependent MAPLHGR and MCPR thermal limits curves (Ref.1). The revised COLR limits ensure operation of the fuel within its design and licensing basis. Therefore, the consequences of a malfunction of Equipment important to Safety previously evaluated in the SAR will not be increased.
B.3.
May the proposed activity cmate the possibility of a diffemnt type of i
malfunction of Equipment important to Safety than any previously evaluated in the SAR7 The possibility of a different type of malfunction of Equipment important to Safety than any previously evaluated in the SAR will not be created. This COLR revision makes no physical changes to the fuel or any plant systems. There is no possibility of the COLR revision creating a different type of fuel failure, or affecting any accident initiator, because the thermal limits provided in the COLR maintain the validity of the original design basis and have been determined in accordance with
. NRC-approved licensing enteria. The reactor and the fuel will continue to operate within the same design and licensing cntena as before. The incorporation of the revised flow dependent MAPLHGR and MCPR thermal limits curves to allow for admir'istration of thermal limits makes no changes to any Equipment important to Safety. Therefore, the possibility of a new type of fuel failure, or new failure mechanism, will not be created.
C.
The TS bases reviewed for potential reduction in the margin of safety were:
2.1 Safety Umits,3.2.1 Average Planer Linear Heat Generation Rate (APLHGR),
3.2.3 Msimum Critical Power Ratio (MCPR), 3.4.1 Recirculation Loops, 3.7.8 Main Turbine Bypass System, and 6.9.1.9 to 6.9.1.12 Core Operating Limits Report.
C.1.
Does the proposed activity reduce the margin of safety as defined in the bas:s of anyTechnicalSpecification?
The margin of safety as defined in the basis of any Technical Specification will not bs reduced The margin of safety inherent in the analytical methods used to determine the Limerick 1 Cycle 8 thermal limit parameters in the COLR is defined in i
' Reference 3.
These methods are NRC-approved. The purpose of the ARTS thermal limits is that the fuel licensing bases shall not be violated during a licensing basis event, while operating within the allowed operating domains of the power and flow operation map. The fuel licensing bases are met by not exceeding the Safety
- Limit MCPR (SLMCPR), the Maximum 1% Cladding Plastic Strain criterion, and the Page 5 of 8
P, t
(
50 59 Review for Revision 2 of LGSt. C8. COLR: Rev. 0
\\
l 1
Fuel Centerline Melt Temperature criterion during AOOs. The incorporation into the l
COLR of the revised flow-dependent MAPLHGR and MCPR thermallimits curves to allow for administration of thermal limits does not affect the SLMCPR value or the standard MAPLHGR limits. The ARTS curves have been revised in Revision 2 of l
the COLR to ensure that the SLMCPR, clad strain, and centeriine malt criteria are not violated during a transient initiated from off-rated conditions. Therefore, the I
margin of safety is preserved.
D.
10CFR50.59 Safety Evaluation Conclusion Based on the results of this 50.59 Safety Evaluation, there are no Unreviewed Safety Questions associated with the Limerick Unit 1 Cycle 8 Core Operating Limits Report, Revision 2.
\\
l E.1.
13 a change to the UFSAR necessary?
E The changes identified in this safety evaluation only affect the COLR. They do not L
change any system, structure, or component identified in the UFSAR. Therefore, this change to the COLR does not require any changes to the UFSAR. The Process Computer databank will be updated to incorporate new parameters l
associated with the revised ARTS flow-dependent thermal limit curves.
i l
E.2.
Is a change to any other SAR document necessary?
i E
The changes identified in this Safety Evaluation affect tne Umerick 1, Cycle 8 COLR only and do not require changes to any other SAR document. These changes have been incorporated irito Revision 2 of the affected COLR. The Process Computer databank will be updated to incorporate the revised flow-l dependent MAPLHGR and MCPR thermal limit parameters as documented in Revision 2 of the COLR.
Page 6 of 8
~
50.59 Review for Revision 2 of LGS 1. C8. COLR: Rev. 0 N.
REFERENCES 1.
' ARTS Flow-Dependent Umits with TBVOOS for Peach Bottom Atomic Power Station and Umerick Generating Station", NEDC-32847P, June 1998, 2.
" Maximum Extended Load Une Umit and ARTS Improvement Program Analyses for Umenck Generating Station Units 1 and 2", GE Nuclear Energy Document No.
NEDC-32193P, Rev. 2, October 1993.
3.
" General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-13, August 1996 and U. S. Supplement, NEDE-24011-P-A-13-US, August 1996.
4.
" Supplemental Reload Licensing Report for Limerick Generating Station Unit 1, Reload 11, Cycle 8", J11-03093SRLR, Rev. O, August 1997.
l Page 7 of 8
50.59 Review for Revisior. 2 of LGS 1. C8. COLR: Rev 0
{
V.
APPROVALS Prepared By:
/hy((///ds,,y f//f/ff Date:
A. J. WWggris
/
Engineer h.'bkb I!lSh9 Peer Review
.m Date:
h J. La. McHale I
Engineer Branch Manager Review.
4 Date:
- J~/ 9
(./
J. M. Carmody 4 Manager Nuclear Design BWR s:%dk\\5059Vic8coWJ2_rfw. doc 1.'
p Page 8 of 8
<