L-13-153, Core Operating Limits Report for Cycle 15
| ML13115A702 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/24/2013 |
| From: | Kaminskas V FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-13-153 | |
| Download: ML13115A702 (23) | |
Text
Perry Nuclear Power Plant p.D. Box 97
, 10 Center Road Perry. Ohio 44081 RrstEnetgy Nuclear Operating Company Vito A. KsmJnskss 440-280-5382 Vice President Fax: 440-280-8029 April 24, 2013 L-13-153 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Core Operating Limits Report for Cycle 15 Enclosed please find Revision 21 of the Perry Nuclear Power Plant Core Operating Limits Report, for Cycle 15. This report is submitted in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)."
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810.
Sincerely, JJ)LY1/W'V'l~
Vito A. Kaminskas
Enclosure:
Core Operating Limits Report for the Perry Nuclear Power Plant Unit 1 Cycle 15 (Reload 14) cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager
ENCLOSURE TO L-13-153 Core Operating Limits Report for the Perry Nuclear Power Plant Unit 1 Cycle 15 (Reload 14)
(21 pages follow)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1 Tille: Use Calegory:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision: lpage:
21 1 of 21 CORE OPERATING LIMITS REPORT FOR THE PERRY NUCLEAR POWER PLANT UNIT 1 CYCLE 15 (RELOAD 14)
Functional Location (J11) .
Plant Data Book Effective Date: _ _4..;. -. :,.1~5--.:1..:;3_ __
Preparer: Pat Curran I 3-4-13 Date Approver: Paul Bordley I 3-6-13 Date
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOO01
Title:
Use Calegory:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I g pa e:
2 of 21 TABLE OF CONTENTS Page
1.0 INTRODUCTION
3
2.0 REFERENCES
4 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (T.S. 3.2.1) 6 4.0 MINIMUM CRITICAL POWER RATIO (T.S. 3.2.2) 10 5.0 LINEAR HEAT GENERATION RATE (T.S. 3.2.3) 19 6.0 REACTOR PROTECTION SYSTEM INSTRUMENTATION (T.S. 3.3.1.1) 21 7.0 OSCILLATION POWER RANGE MONITOR (OPRM)
INSTRUMENTATION (T.S. 3.3.1.3) 21 8.0 SCOPE OF REVISION 21
PERRY NUCLEAR POWER PLANT Procedure Number:
PDB-FOO01
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage:3 of 21
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for the Perry Nuclear Power Plant (PNPP) Unit 1 Cycle 15 is prepared in accordance with the requirements of PNPP Technical Specification Administrative Control 5.B.5. The core operating limits presented herein were determined using NRC-approved methods (Reference 1 and Reference 2). The core operating limits for the Global Nuclear Fuel (GNF) fuel in PNPP Unit 1 for Cycle 15 are documented in References 3, 4, 5, and 14 and summarized herein for the following PNPP Unit 1 Technical Specifications:
- 1. Average Planar Linear Heat Generation Rate (APLHGR) Limits for each fuel/lattice type, including the power and flow dependent MAPFAC curves with the single loop MAPLHGR reduction factor.
(Technical Specification 3.2.1)
- 2. Minimum Critical Power Ratio Operating Limit including the power and flow dependent MCPR curves for Two Loop Operation and Single Loop Operation. (Technical Specification 3.2.2)
Additional power dependent MCPR curves for Two Loop Operation and Single Loop Operation are provided for operation with one pressure regulator out of service.
- 3. Linear Heat Generation Rate (LHGR) Limits for each fuel/lattice type, "including the power and flow dependent MAPFAC curves with the single loop MAPLHGR reduction factor. (Technical Specification 3.2.3)
- 4. The simulated thermal power time constant. (Technical Specification 3.3.1.1, SR 3.3.1.1.14)
- 5. Oscillation Power Range Monitor (OPRM) Instrumentation.
(Technical Specification 3.3.1.3)
Calculation FM-075, Support for the Core Operating Limits Report details the development of the various graphs contained within this COLR.
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOO01 TiUe: Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage:4 of 21
2.0 REFERENCES
2.1 Discretionary None 2.2 Obligations
- 1. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-19, May 2012; and the US Supplement, NEDE-24011-P-A-19-US, May 2012
- 2. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, Licensing Topical Report, NEDO-32465-A, August 1996
- 3. Supplemental Reload Licensing Report for Perry 1 Reload 14 Cycle 1'5, GNF Document 0000-0140-7070-SRLR, Rev 0, December 2012
- 4. Fuel Bundle Information Report for Perry 1 Reload 14 Cycle 15, GNF Document 0000-0140-7070-FBIR, Rev 0, December 2012
- 6. Technical Specification 2.1.1.2, Safety Limit MCPR, Amendment No. 155
- 7. Technical Specification 3.2.1, Average Planar Linear Heat Generation Rate, Amendment No. 112
- 8. Technical Specification 3.2.2, Minimum Critical Power Ratio, Amendment No. 112
- 9. Technical Specification 3.2.3, Linear Heat Generation Rate, Amendment No. 112
- 10. Technical Specification 3.3.1.1, Reactor Protection System Instrumentation (SR 3.3.1.1.14), Amendment No. 115
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOO01
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 l page
- 5 of 21
- 11. Technical Specification 3.3.1.3, OPRM Instrumentation (SR 3.3.1.3.3), Amendment 138
- 12. Technical Specification 5.6.5, Core Operating Limits Report, Amendment No. 136
- 13. Neutron Monitoring System Design Specification, 22A3739, Revision 6
- 14. Calculation FM-075, Support For Core Operating Limits Report, Revision 0, Addendum 1
- 15. FTI-B0012, Single Loop Operation Commitments addressed in this document:
None
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOO01
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage:6 of 21 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (T.S. 3.2.1)
All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall not exceed the result obtained from multiplying the applicable MAPLHGR limit, Figure 3.2.1-1, by the smaller of either the flow dependent MAPLHGR factor (MAPFACf), Figure 3.2.1-2 or the power dependent MAPLHGR factor (MAPFACp) Figure 3.2.1-3.
MAPLHGR Limits and MAPFACf and MAPFAC p are defined in Reference 3.
For Two Loop Operation, MAPFACf and MAPFACp shall not exceed 1.0.
For Single Loop Operation, MAPFACf and MAPFACp shall not exceed O.B.
The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.
Use FTI-B0012 Single Loop Operation to implement the revised MAPLHGR Limits.
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I g pa e:
7 of 21 Figure 3.2.1-1 MAPLHGR Versus Average Planar Exposure Fuel Type GE14 14 12 10
~
'"~~
-~ 8 '-
\
~
\
4 MAPLHGR = 12.82 for Exposures </= 19.13 MAPLHGR = 12.82 + (-0.12526)* (Exposure -19.13) for 19.13 < Exposures </= 57.61 MAPLHGR= 8.00 + (-0.50934)* (Exposure - 57.61,)
2
for 57.61 < Exposures </= 63.50 o
a 5 10 15 20 25 30 35 40 45 50 55 60 65 70 Average Planar Exposure (GWD/ST)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage:
a of 21 Figure 3.2.1-2 Flow Dependent MAPLHGR Factor (MAPFAC,)
Fuel Type GE14 1.1op------r------r----""'T"""----,...---""""T"----.
0.9 . - - - - -~.*-.,..- ----"
GE14 - Clamped at 0.80 During SLO tI if~ 0.8 0.7 ---
MAPFAC,..MIN(1.0,0.4574+0.006759F) 0.6 ---=-- -_._-- ---
0.5 ...... -..........~....................... -.........- . .........""*.-.......-......--.............
o 20 40 60 80 100 120 CORE FLOW (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1 Tille: Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage:g of 21 Figure 3.2.1-3 Power Dependent MAPLHGR Factor (MAPFAC p )
Fuel Type GE14 1.1 1.0 0.9 MAPFACp=1.0+0.0052(P.100) 38%<P<=100%; Core Flow <=105% IGE14
- Clamped at 0.80 During SLO 23.8%<=P<=38%; Core Flow <=50%
i ./
a..
~
0.8 0.7
'f'
/
~ i' MAPFACp=0.6+0.0021 (P-38) 23.8%<=P<=38%; Core Flow >50%
0.5 o 20 40 60 80 100 CORE THERMAL POWER (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOO01
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 IpaQ910 of 21 4.0 MINIMUM CRITICAL POWER RATIO (T.S. 3.2.2)
The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the higher of the flow dependent MCPR (MCPR,) and power dependent MCPR (MCPR p) limits at the indicated core flow and THERMAL POWER.
The MCPR Safety Limit for Cycle 15 for Two Loop Operation is 1.10 and the MCPR Safety Limit for Single Loop Operation is 1.11 <TECHNICAL SPECIFICATIONS 2.1.1.2> (Reference 3 and 8). The change in Safety Limit from Two Loop Operations to Single Loop Operations is accomplished by increasing the Cycle 15 MCPRf and MCPRp limits by 0.01. 3DMONICORE PANACEA Version 11 uses this approach to calculate Single Loop Operation Limits.
The Single Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1 ,"Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.
Use FTI-B0012 Single Loop Operation to implement the revised MCPR Limits.
During Two Loop Operation, the resulting limit from MCPRf and MCPRp shall not be less than the OLMCPR of 1.34. During Single Loop Operation, the resulting limit from MCPRf and MCPRp shall not be less than the OLMCPR of 1.35.
For Cycle 15 no change to MCPR limits is required for planned reduction of feedwater temperature to as low as 325.5°F. Final feedwater temperature may be reduced to 255.5°F after all control rods are withdrawn at the end of cycle if the OPRMs are OPERABLE.
Planned reduction of rated feedwater temperature from nominal rated feedwater temperature Is not permitted during plant operation with the reactor recirculation system in Single Loop Operation.
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I g pa e 11 of 21 The 3DMONICORE Computer software should automatically shift between 2 LOOP ON and ONE LOOP ON modes of operation on transfer to Single Loop Operations. As such the Safety Limit change should occur automatically. The guidance in FTI-B0012 can be used to verify proper functioning of the 3DMONICORE System. If the 3DMONICORE System is not functioning properly, FTI-B0012 will implement administrative limits until such time as 3DMONICORE is properly calculating MCPR values.
The MCPRf and MCPRp Limits are based on whether the plant is operating in Two Loop or Single Loop Operations and whether Two Pressure Regulators or One Pressure Regulator is in service. Select MCPR, ,
MCPRp Limit Curves based on plant conditions:
MCPR, Figure 3.2.2-1, MCPRf - Two Loop Operations Figure 3.2.2-2, MCPRf- Single Loop Operations MCPRp Figure 3.2.2-3, MCPRp - Two Loop Operations Figure 3.2.2-4, MCPRp - Single Loop Operations Figure 3.2.2-5, MCPRp - Two Loop Operations' Pressure Regulator Out of Service Figure 3.2.2-6, MCPRp- Single Loop Operations 'Pressure Regulator Out of Service .
Figure 3.2.2-7 Maximum Fraction limiting Critical Power Ratio Limit (MFLCPR) With One Pressure Regulator Out Of Service The 3DMONICORE Software will not automatically shift to the Pressure Regulator Out of Service Thermal Limits. The 3DMONICORE databank will be manually changed using a software change request. Until such time as 3DMONICORE databank is updated for the Pressure Regulator Out of Service Thermal Limits, an MFLCPR Administrative Limit will be Issued to Operations. Figure 3.2.2-7 can be used as a guide in establishing the MFLCPR Administrative limit. The graph is the ratio of MCPRp to MCPRp - Pressure Regulator Out Of Service.
PERRY NUCLEAR POWER PLANT Procedure Number:
PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 IpaQ812 of 21 Figure 3.2.2-1 Flow Dependent MCPR (MCPR,) - Two Loop Operation Fuel Type GE14 1.8 1.7
-c o
- 1.6
\ PERMISSIBLE
....CD D. \ REGION OF OPERATION
~
o D.
o
~
o 1.5
~
~
A.
U
/" \
- IE 1.4 r\
MCPR, .. MAX [1.34.
(1.7978.o.00675F)*(1.1 0/1.07)] \,
1OLMCPR .. 1.341 1.2 o 20 40 60 80 100 120 CORE FLOW (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1 THle: Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I 13 g
pa e of 21 Figure 3.2.2-2 Flow Dependent MCPR (MCPR,) - Single Loop Operation Fuel Type GE14 1.8 1.7 -
PERMISSIBLE co
- w I!
CIt g,
1.6
\, REGION OF OPERATION o
.9 go CIt
'ij, 1.5 \
~ i\
C
-rZ in MCP... MAXI(l .......
~
A. <<1.7978-o 0.00675F)*(1.1 0/1.07)+0.01)]
1.4
./
V 1.3 I OLMCPR = 1.34 + 0.01 I 1.2 o 20 40 60 80 100 120 CORE FLOW (% RATED)
Procedure Number.
PERRY NUCLEAR POWER PLANT PDB-FOOO1 Tille: Use Calegory:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I 14 g
pa e of 21 Figure 3.2.2-3 Power Dependent MCPR Limit (MCPRp ) - Two Loop Operation Fuel Type GE14 2.5 2.4 --
2.3 \
2.2
,\ - I I MCPRp = 2.02 + 0.0246(38 - P ) t -
For 23.8% <= P <= 38%; Core Flow > 50%
2.1
\'\' ......I MCPRp = 1.99 + 0.0162(38 - P)
I For 23.8%<= P <=38%; Core Flow<=50% I I
c-O
~2.0
.~* "-
cu Q.
oQ.
o 1.9 I l'tr MCPRp = 1.34 * [1.448 + 0.007(50.0 - P))
PERMISSIBLE REGION OF
~ For 38% < P <=50.0%; Core Flow <=105% I OPERATION
- 1.8 t.
rl"
- a. 1.7
~
f-""""
CJ
- e 1.8 I MCPRp = 1.34 * [1.223 + 0.004(66.7 - P)l I For 50.0% < P <=68.7%; Core Flow <=105%)
I '1 1.5 1A I ~
MCPRp = 1.34 * [1 +0.005(100 - P)l For 86.7% < P<= 100%; Core Flow <=105%
" I ~
~
1.3 o 20 40 60 80 100 CORE THERMAL POWER (%RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry. Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage15 of 21 Figure 3.2.2-4 Power Dependent MCPR Limit (MCPRp ) - Single Loop Operation Fuel Type GE14 2 .5 2 .4 t-----
2.3 1---- \ ~ = ,I
\.\~
MCPRp (2.02 + 0.0246(38
- P>>+O.01 For 23.8% <= P <= 38%; Core Flow> 50%
I I 2 .2
- 2 .1 ,\- ......-t MCPRp = (1.99 + 0;0162(38* P>>+O.01 I For 23.8% <= P<=38%; CoreFlow<= 50% I I
~ "-
c o
- I I! 2 .0 11 4>>
a.
o PERMISSIBLE go 1.9 REGION OF
~ MCPRp = (1.34+0.01) * [1.448 + 0.007(50.0
- P)) OPERATION 4>> For 38% <P<"50.0%; Core Flow <=105%
a.
c 1
-en a:.Q. 1.7 ~
a.
u
- E 1.6 I / Ir't
~
MCPRp .. (1.34+0.01) * [1.223 + 0.004(66.7
- P))
For 50.0% < P<=66.7%; Core Flow <=105%
I
.5
./
A I MCPRp" (1.34+0.01)*[1 + 0.005(100* P))
I For 66.7% < P <=100%; Core Flow <=105% I I ~
.3
.2 o 20 40 60 80 100 CORE THERMAL POWER (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 Ipage16 of 21 Figure 3.2.2-5 Power Dependent MCPR Limit (MCPR p) - Two Loop Operation Pressure Regulator Out Of Service' Fuel Type GE14 2.5 2.4 2.3
\
2.2
~\ I MCPRp = 2.02 + 0.0246(38
- P,
......I For 23.8% <= P <= 38%: Cora Flow I
I
'\\~
> 50%
I""'"
. ~ 2.1
~r~
o IX A.
C 2.0
~
o
- 0::
I!
CI) a.
1.9 i MCPRp '1." + {,62138
- PI I
PERMISSIBLE REGION OF
"~
For 23.8%<= P <=38%: Core Flow<=50%
o OPERATION a.
~ 1.8 '"
o
~ 1.7 V
rl' A. /
U 1.8 I MCPRp =1.34*[1.19 + 0.00881(80.00* P))I For 38% < P <=80%: Cora Flow <=105%
1.5 1.4 ~
L 1.3 1.2 o 20 I
40 MCPRp =1.34*[1 +0.005(100* P,]
For 80% < P<=100%: Cora Flow <=105%
60 80 I
I
'"' 100 CORE THERMAL POWER (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I 17 of 21 g
pa e Figure 3.2.2-6 Power Dependent MCPR Limit (MCPRp) - Single Loop Operation Pressure Regulator Out Of Service I Fuel Type GE14 2.5 2.4 2.3
\ ,I
,\~
MCPRp =(2.02 + 0.0246 * (38- P))+O.01 For 23.8% <= P <= 38%; Core Flow> 50%
I 2.2 U) 8 2.1
'\\~ PERMISSIBLE REGION OF OPERATION
~~
~
a::
Q.
C 2.0 o
~ /
o
!.1.9
~
o
.3 1.8 MCPRp" (1.99+ 0.0162* (38 - P)) + 0.01 For 23.8% <= P<= 38%; Core Flow<= 50% ""/
,I i\..
"'\
CP m
.5 t/)
rJf.D.
Q.
1.7 1.8 I MCPRp" (1.34 + 0.01)* [1.19 + 0.00881(80.00 - P))
For 38% < P<=80%; Core Flow <=105%
I CJ
- E
~
1.4 I
1.3 I MCPRp" (1.34+ 0.01)* [1 + 0.005(100 - P))
For 80% < P <=100%; Core Flow <=105%
1.2 o 20 40 60 80 100 CORE THERMAL POWER (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 1 page18 of 21
.Figure 3.2.2-7 Maximum Fraction Limiting Critical Power Ratio Limit (MFLCPR)
With One Pressure Regulator Out Of Service I Fuel Type GE14 I
(23.8. 1.000) I (38. 1.000) I I (50. 0.996) I i l (80. 1.000) J (100. 1.000) 1.000 I
V
~V 0.975 (38. 0.982) o~ 0.950 It:
- a. I (66.7. 0.936) I It:
~
t:
- § 0.925
) ~
~
...I It:
- a. V I (80. 0.924)
~ I
- & / I V 0.900 0.875 I (50. 0.887) I PREMISSIBLE REGION OF (66.7. 0.892)
OPERATION 0.850 CORE THERMAL POWER (% RATED)
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOO01 Tille: Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 IPage:
19 of 21 5.0 LINEAR HEAT GENERATION RATE (T.S. 3.2.3)
All LINEAR HEAT GENERATION RATES (LHGRs) shall*not exceed the result obtained from multiplying the applicable LHGR limit, Figure 3.2.3-1, by the smaller of either the flow dependent MAPLHGR factor (MAPFAC,),
Figure 3.2.1-2 or the power dependent MAPLHGR factor (MAPFACp)
Figure 3.2.1-3.
LHGR Limits and MAPFAC, and MAPFACp are defined in References 3 and 4.
For Two Loop Operation, MAPFAC, and MAPFACp shall not exceed 1.0.
For Single Loop Operation, MAPFAC, and MAPFACp shall not exceed 0.8.
The Single* Loop Operation limits take effect when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating". This is consistent with note "(b)" to Table 3.3.1.1-1 of the Technical Specifications.
Use FTI-B0012 Single Loop Operation to implement the revised MAPLHGR Limits.
Procedure Number:
PERRY NUCLEAR POWER PLANT PDB-FOOO1
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15 (Reload 14) Revision:
21 I 20 of 21 pege Figure 3.2.3-1 LHGR Versus Peak Pellet Exposure Fuel Type GE14 16 14 12 "" ~
'""'"'"" ~
~
~'"'-
6 \' \ ~
4 ~ U02 LHGR LIMIT
~U02lGd LHGR LIMIT
-U02 LHGR LIMIT I
\ ~
LHGR =13.40 for Exposures <1= 14,51 LHGR =13.40 + (-0.12529)* (EJIIlOSUre - 14.51) for 14.51 < Exposures <1= 57.61 LHGR = 8.00 + (-0.50934)* (Exposure - 57.61) for 57.61 < Exposures <1= 63.50 2 I-- U02lGd LHGR LIMIT LHGR =12.00 for Exposures <1= 12.17 LHGR =12.00 + (-0.11410)* (Exposure -12.17) for 12.17 < Exposures <1= 54.59 LHGR = 7.16 + (-0.46207)* (Exposure - 54.59) for 54.95 < Exposures <1= 60.39 o . . 1 o 10 20 30 40 50 60 70 Peak Pellet Exposure (GWD/ST)
PERRY NUCLEAR POWER PLANT Procedure Number:
PDB-FOO01
Title:
Use Category:
Core Operating Limits Report for the Perry Nuclear In-Field Reference Power Plant Unit 1 Cycle 15-(Reload 14) Revision:
21 IpaQ821 of 21 6.0 REACTOR PROTECTION SYSTEM INSTRUMENTATION (T.S. 3.3.1.1)
The simulated thermal power time constant shall be 6 +/-0.6 seconds (Reference 13).
7.0 OSCILLATION POWER RANGE MONITOR (OPRM)
INSTRUMENTATION (T.S. 3.3.1.3)
These-are the Cycle 15 OPRM setpoints for operable OPRMs.
Current Settings:
- 1. Confirmation Count Setpoint (N p = N2): 12
- 2. Amplitude Setpoint (Sp): 1.10 (Reference 5) 8.0 SCOPE OF REVISION Rev. 21 1. Updated for Cycle 15 Operations as defined in References 3 and 4. Note: there were no changes to any limits or setpoints.