ML18065A538
| ML18065A538 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/26/1996 |
| From: | Bates M, Duffy T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18065A537 | List: |
| References | |
| NUDOCS 9603120454 | |
| Download: ML18065A538 (10) | |
Text
-~-~-..-----.
PALISADES PLANT CORE OPERATING LIMITS REPORT Preparer Date
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PRrReviewed 1 ~/l"J/"(t,./ PSL 9trJ -01~'1 9603120454 960226
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PDR ADOCK 05000255:
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- Date*
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- Reference* #.
Date Palisades COLR Revis.ion 2 Date 2-28-:.'E.
Consumers Power Company Docket No. 50-255.
License No. DPR-20 Core Operating Limits Report 1.0 CORE OPERATING LIMITS.REPORT
- palisades COLR Revision 2 Page 1 of 9 This Core Operating Limits Report for.Palisades has been prepared in accordance with the requirements of Technical Specification
. 6;.9.1 * (f).
The Technical Specifications affected by this report are listed below:
Section
- Title
- 2. 1 AS! Limits for T1niet Function*
2.2 Regulating Group Insertion Limits 2.3 Linear Heat Rate (LHR) Limits
- 2. 4 Radial Peaking Factor Limits NOTE:
Specification 3.1.1 3.10.5 3.23.1 3.23.2 Any procedure or document previously referencing the Technical Specifications for any operating limit that has been moved to the COLR should be viewed as.* referencing the COLR until the applicable procedures or documents are revised.
~.
2.0 OPERATING LIMITS Palisades COLR Revision 2 Page 2 of 9 The cycle specific parameter limits for the specifications. listed in Section 1 are presented in the following subsections.
These limits have been developed using the 'NRG-approved methodologies
- specified in Section 3.0.
'2.1 AS! Limits for Tinlet Function (Technical Specification 3.1.1).
The AS! limit for the Tiniet function :Ls shown in Figure 2. 1.
1.2 r--.-----,--,-----,--,---r----,----:~--.---..---~~~
1.1
. 1 I..
~
0.9
-0 0.8
~
0 er 0.1 c. 0.6
.Q ti
~ 0.5 0.4 O.J Unacceptable Operation Acceptable Operation 0.2...._....._......... _""--'_----:-'----'---'---L--....._----L __ J___....._ _ __J
.. -0.6
-0.5
-0.4
-0.J
- -0.2
-0.. 1 0.0 0.1 0.2 O.J 0.4
. 0 5 Axial Shope Index Figure 2. 1 - ASI Limit for T inlet Function Break Points:
-0.550,
- 0. 250
-0.300, 0.700
-0.080, 1.000
-0.080,
- l. 065
+0.400, 1.065
+O. 400, *
- 0. 250
\\
- Palisades COLR Revision 2
- Page 3 of 9*
2.2 Regulating Group Insertion Limits (Technical Specification 3.10.5)
- a.
- b.
- c.
- d.
To implement the limits on shutdown margin, indi Vi dual rod worth and hot channel** factors I the limits on control rod regulating group insertion shall be established as shown on Figure 2.2.
The sequence of withdrawal of the regulating groups shall be 1, 2, 3, 4.
An overlap of control-banks in excess of 40%
shall not be permitted.
The. reactor shall not be made critical with a
.control rod position lower than the insertion limit for zero power shown on Figure 2*.. 2.
a a '°
.. so
~
/. ~
CIC 30
-~
! 20 -
(,J c 10 CIC 0
0 l)O to J.,
J 0
70 t"'I.,,
l"t 60 0
"I. 5IJ CIC 4()
~ 30 u
20 c
~
10 0
TWO 0.. n4AU 111\\JW OPPATlO..
MAXMJM ~WP L!VIL
~
~
l"oo...
~
~
20 4()
to to 1)0 0
~0 I
I 4
I 0
20 40""""" G> 60
~"°° MPTION, N~NT FOO" l'\\JMP OPPATIOH
~
............ K
-~
- ~
~~
- ~
20 4()
0 '° ID 100 0
0 20 4()~ crr
~
~o MMJmOtc. llJllJllCI NT Palisades COLR Revision 2 Page 4 of 9 20 40 QllOJ9I © I
r IQ
'iQO r:
~
~
20
- O
.OIOJI' CD ID IOO Figure 2.2 - Power Dependent Control Rod Insertion Limit I i I
I
l...
Palisades COLR Revisio.n 2 Page 5 of 9 2.3 Linear Heat Rate (LHR) Limits (Technical Specification
- 3. 23. 1 >.
The LHR in the peak.powered fuel rod shall not exceed the following:
Where:
LHR.rs*
=
Maximum allowable LHR shown in Table 2.1.
Allowable LHR function of peak
=
as a power location shown in Figure 2.3.
Table 2.1 - Linear Heat Rate Liinit
- I L!::I=====P=.e=a=k=R=o=d======~======1=5=*=2=8=(=kW=/f=t=)=-:=*
- ,.=====::!lll *
.:~
1.2
~
I
...J I.I E
- I E
. ;(
0
~
o*
c 0 :z 8
it 0.9 a::
I...J jz
.Ll 0. 0.8
~
.Q
- cc 0.7 Unacceptable Operation.
(0.60, 1.00)
Acceptable Operation 0
0.2 0.4 0.6.
Fractiof') of Active Fuel Height Palisades COLR Revision 2
\\
Page 6 of 9 (1:00, O.!J) 0.8 Figure 2.3 - Allowable LHR as a Function of Peak Power Location
~..,
Palisades COLR Revision 2 Page 7 of 9.*
- 2. 4 Radial Peaking Factor Limits *(Technical Specification 3.23.2)
The radial peaking factor shall not exceed the following:
for P
~ 0.5 and for p < 0.5, Where:
FTS r
p
=
=
=
F = FTB x [ 1. 0 + 0. 3 X ( 1 - P) ]
r r
TS Fr = Fr X 1.15 Measur~d ~ or F;,
Maximum allowable ~ or F; (Tabl_e 2. 2),
Fraction of rated power.
Table 2.2 -
Peaking Factor Limits, p;s
- Peaking Factor Reloaci L & M.
. Reload N Reload q Assembly ~
1.57
- 1. 66
- 1. 76 Peak Rod FT r
- 1. 92
- 1. 92 2.04
& p
Palisades COLR Revision 2 Page 8 of 9 3.0 ANALYTICAL METHODS The analytical methods used to determine the core operating.
limits are those previously reviewed and.approved by the.NRC, specifically those described in the following documents:
3.1 3.2 3.3 3.4 XN-75-27(A), and Supplements -1 through 5, "Exxon Nuclear Neutronics Design Methods for. Pressurized Water Reactors," Exxon Nuclear Company, ~ated April 1977, Supplement 1 dated September 19~6, Supplement 2 dated December 1980, Supplement 3 dated September 1981, Supplement 4 dated December 1986, Supplement 5 dated February 1987.
ANF~84-73(P) (A), Revision 5, Appendix Band Supplements 1 and 2, "Advanced Nuclear Fuels* Corporation Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, October 1990.
XN-NF-82-21(P) (A); Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,,; Exxon Nu.clear Company, September 1983.
- ANF-84-093 (P) (A), and Supplement 1, "Steamline Break Methodology for PWRs," Advanced Nuclear Fuels Cotj:>oration, March 1989.
3.5 XN-75-32(P) (A), Supplements 1 through 4, "Computational Procedure. for Evaluating Fuel Rod Bowing," Exxon
~.
Nuclear Company, October 1983.
3.6 EXEM PWR Large Break LOCA Model as defined by:
.. XN-NF-82-20 (A), Revision 1 and Supplements 1 through 4, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, January.1990.
~**
Palisades COLR Revision 2 Page 9 of 9 XN-NF-82-07 (P) (A), Revision 1, Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon 'Nuclear Gompany, November 1982.
XN-NF-81-58(A), Revision 2 and Supplements 1 through 4, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Revision 2 and Supplements 1 and 2dated March 1984, Supplements 3 and 4 dated June 1990.
XN-NF-85-16(A), Volume 1, Supplements 1 through 3, and
_Volume 2, Revision 1 and Supplement 1, "PWR 17x17 Fuel Cooling Tests Program," Exxon Nuclear Company, February 1990.
XN-NF-85-105(A), and Supplement 1, "Scaling of FCTF Based Reflood Heat Transfer Correlation.for other.Bundle Designs," Exxon Nuclear Company, January 1990.
3.7 XN-NF-78-44(A), "A Generic Analysis of the Control Rod Ejection Transient *for Pressurized Water Reactors,"
Exxon Nuclear Company, October 1983.
- 3. 8 ANF-1224 (P) (A), and Supplement 1, "Departure from Nucl.e.ate Boiling Correlation *for High Thermal Performance Fuel,~~
Advanced Nuclear Fuels Corporation, April 1990*.
- 3. 9 ANF-89-151 (P) (A), "ANF-RELAP Methodology for Pres.surized.*
Water Reactors :Analysis of Non-LOCA Chapter 15. Events*,"
Advanced Nuclear Fuels Corporation~ April 1992.
3.10 EMF-92-153(P) (A),
- 11HTP: Departure from_ Nucleate Boiling
.Correlation for High Thermal Performance Fuel," Siemens Power Corporation.
Specific application of these methodologies to Palisades is described in.the cycle's most current Safety Analysis Report.